ML20091K404
| ML20091K404 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/23/1991 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13302B817 | List: |
| References | |
| S023-V-3.5, S23-V-3.5, NUDOCS 9201240182 | |
| Download: ML20091K404 (208) | |
Text
{{#Wiki_filter:__ NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISLON 7 PAGE 1 0F 208 (' COMPLETE REVISION TCN 7-16 () EFFECTIVE DATE INSERVICE TEil@G OF VALVES PROGRAE TABLE OF CONTENTS KClld IME 1.0 OBXCTIVE!, 2 2
2.0 REFERENCES
4 3.0 PREREQUl!.lTES 5 4.0 PRECAUTIONS 5 5.0 CHECKLIST (S) 5 6.0 PROCEDURE 5 6.1 Test interval 6.2 Pre-service Testing 5 6.3 Valve Category 6 6.4 Requirements 7 6.5 Corrective Measures 17 6.6 Exceptions 18 6.7 Instrumentation 19 (' 6.8 E;etermination of Program Scope 19 ( 7.0 RECORDS 21 ATTACHMENTS 1 Inservice Valve Testin9 Table Information 22 2 System Valve List: Unit 2 28 3 Unit 2 Justification for Valves Not Tested Quarterly 80 4 System Valve List: Unit 3 92 5 Unit 3 Justification for Valves Not Tested Quarterly 144 6 ASME XI Table IMV 3510 1 156 7 Valve Relief Requests 157 8 Stroke Time Acceptance Criteria for Valves Required ' To Stroke At Other Than Their Safety Analysis Limits 205 O w/ 01550 7T w51 QA PROGRAM AFFECTING 920124C8102 920120 PDR ADOCK 05000361 P ppg ,
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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNIT 5 2 AND 3 REVISION 7 PAGE 2 0F 208 l TCN 7".16 i INSERVICE TESTlHG OF VALVES PROGRAM 1.0 OBJECTIVES l 1.1 To define the requirements for inservice testing of ASME Code class 1, , 2 and 3 valves, r 1.2 Further, it is the object of this procedure to meet the requirements of References 2.4.5, 2.4.1 and 2.1.1 through 2.1.13 and 2.1.16 through 2.1.19. . A complete description of organizational responsibilities to l meet the requirements of Reference 2.4.5 is provided in Reference 2.2.1. This program is in compliance with References 2.4.2 and 2.4.4, 3 except ar noted in approval valve relief requests, see Attachment 7. 1.3 To describe and delineate applicable-tests and utilize Qe tests for both pre service and inservice testing unless indicated otherwise. 2.0 -REERENCES 2.1 NRC Commitments Letter, K. P. Baskin (SCE) to G. W. Knighton (NRC), Doc,et k 2.1.1 r No. 50 361 (Forwarded Unit 2 Program, Revision 5), July 5,- 1983 2.1.2 Docket No. 50 361 (Forwarded Unit 3 Program, Revision 0)), July 5, L 1983 2.1.3 Letter, M. O. Medford (SCE) to G. W. Knighton (NRC), Docket Nos. 50 361 and 50 362 (Forwarded Unit 2 Program, Revision 6andUnit3 Program, Revision 1), October 31
-1983 2.1.4 Letter, M. O' Medford (SCE) to G. W.. Knighton (NRC), Docket Nos.50-361and50362(ForwardedUnit2 Program, Revision 7 and Unit 3 Program, Revision 2), May 11, 1984 2.1.5 Letter, M. O. Medford (FCE) to G. W. Knighton_(NRC).-Oocket Nos. 50-361 and 50 362 (Forwarded Unit 2 Program,_
Revision 8 and Unit 3 Program, Revision 3), September 26, . 1984 2,1.6 Letter,-M. 0.-Meoford (SCE) to G. W. Knighton (NRC) . Docket Nos. 50 361 and 50 362 (Forwarded Unit 2 Program, Revision 9 and Unit 3 Program, Reviston_4),-April-4, 1985 2.1.7 Letter, M. 0.;Medford (SCE) to G. W. Knighton (NRC). Docket * . Nos. 50 361 and 50-362 (Forwarded Unit 2 Program, i Revision 10 and Unit 3 Program, Revision 5), July 23,1985 p l i Q 2.1.8 Letter, M. O. Medford (SCE) to G. W. Knighton (NRC), Docket Nos. 50 361 and 50 362 (Forwarded Unit 2 Program, . Revision 11 and Unit 3. Program, Revision 6), December 19. 1985
NUCLEAR ORGAN!ZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 3 0F 208 O TCH ?~10 (
2.0 REFERENCES
(Continued) 2.1.9 Letter, M. O. Medford (SCE) to G. W. Knighton (NRC), Docket Nos. 50 36) and 50 362 (Forwarded Unit 2 Program, Revision 12 and Unit 3 Program, Revision 7], October 10, 1986 2.1.10 Letter,l' Rood (NRC) to K. P. Baskin (SCE), Interim Relief From Requo ements for Inservice Pump and Valve Testing Under 10 CFR 50.55a(g)(1). December 24, 1986 2.1.11 Letter, M. O. Medford (SCE) to NRC Document Control Desk, Docket Nos. 50 361 and 50 362 (Forwarded Unit 2 Program, Revision 13 and Unit 3 Program, Revision 8), August 21, 1987 2.1.12 Letter, F. R. Nandy (SCE) to NRC Document Control Desk, Docket Hos. 50 361 and 50 362, inservice Testing Program for Pumps and Valves (TAC 55120/1) (Forwarded Unit 2 Program, Revision 14 and Unit 3 Program, Revision 9), May 18, 1990 2.1.13 Units 2 and 3 Technical Specifications 2.1.14 Topical Quality Assurance Manuti (TQAM) (] 2.1.15 Final Safety Analysis Report (FSAR) 2.1.16 Letter, F. R. Nandy (SCE) to NRC, Docket Nos. 50 361 and 50-362, Status of NRC Safety Evaluation Report, Appendix C ltems for the Inservice Testing Program for Pumps and Valves (Forwarded Unit 2 Program Status), April 12, 1991 2.1.17 Letter, R. M. Rosenblum (SCE) to NRC, Docket Nos. 50 361 and 50 362, Inservice Testing Program for Pumps and Valves TAC Nos. 55120/1 (Forwarded Unit 2 Progr r , Revision 15 and Unit 3 Program Revision 10), June 18, 4'71,1 l 2.1.18 Letter, R. M. Rosenblum (SCE) to NRC, Docket Nos. 50-361 l and 50 362, inservice Testing Program for Pumps and Valves TAC Nos. 55120/1 (Forwarded Unit 2 Program, oevision 16 and Unit 3 Program, Revision 11), July 31,1991 l 2.1.19 Letter, J. E. Oyer (NRC) to H. B. Ray and G. D. Cotton, Safety Evaluation of Licensee Responses to Staff's Technical Evaluation Repcrt items and Revised Relief I Requests to the IST Program for Pumps and Valves (TAC Nos. 80642 and 80643), October 2, 1991 2.2 Qrrier n S0123 IN 1, inservice Inspection Program V 2.2.1 2.3 Ecgsgsun 2.3.1 5023 V 3.5.4, inservice Testing of Check Valves
I NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 4 0F 208 i p TCN 7 - 1 (; '
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2.0 E[fJRENCES (Continued) 2.3.2 S023 V 3.13. Containment Penetration Leak Rate Testing 2.3.3 50123 XV 5, Nonconforming Material, Parts or Components 2.3.4 5023-XV 6, Technical Specification Response Time Surveillance implementing Procedure Master List 2.3.5 Operating Instruction 5023 3 3.31.1, RCS Pressure Isolation Valve Leak Rate Measurement 2.4 Q1htt 2.4.1 Code of Federal Regulations, Title 10, Part 50 2.4.2 NRC Generic Letter 89 04, Guidance on Developing Acceptable Intervice Testing Programs, April 3, 1989 2.4.3 Letter, J. G. Partlow, NRC, to All Licensees, etc. Minutes of the Public Heetings on Generic Letter 89 04, October 25, 1989 2.4.4 NRC Safety Evaluation Report transmitted by letter, L. E. and G. D. Cotton (SDG&E), p v Kokajko (NRC) to H. B. Ray Safety Evaluation Report of the (SCE) Inservice Testing (IST) Program for Pumps and Valves, September 24, 1990 2.4.5 American Society of Mechanical Engineers (ASME), Boiler and Pressure Vessel Code, Section XI, 1977 Edition, including Addenda through Summer 1979 2.4.6 Memo for File, March 27, 1986, Set point Verification Test Requirements 3.0 PRERE0VISITES 3.1 Prior to use of e user controlled copy of this document, it is the user's responsibility to verify that the revision and any TCNs are current by utilizing one of the following methods: 3.1.1 Check it against a Corporate Documentation Management SONGS (CDM SONGS) controlled copy and any-TCNs. 3.1.2 Access the San Onofre D .ument Management System (SDMS) [ San Onofre local are a network (SLAN) or online system). 3.1.3 Contact CDM-SONGS by telephone or through counter inquiry. 3.1.4 Obtain a user controlled copy of this procedure from rm CDM SONGS or SDMS SLAN. U
NUCl. EAR ORGANIZATION ENGINEERING PROCEDURE 5023.V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 5 0F 208 TCN 7 - 1 () U 3.0 PRERE0VISITil(Continued) 3.2 The implementing Procedu ws shall be updated witnin one (1) month after an approved revision or .. * 'his procedure is issued by CDM. The lechn' cal Division IST Cooroi. 'all provide the Station Operations and Maintenance Manager with a copy of the approved revision to serve as notification of a revision. 4.0 PRECAUT1.QRS 4.1 The ASMi. Sr.ction
- selected valves thatXI test can berequirements tested without (Reference placing the2.4.5) Plant in anapply only to unsafe condition. Therefore, care should be exercised that no test will be conducted so a failure of the test would put the Plant in an unsafe condition.
4.2 Special care must be exercised to ensure that the allowed test interval is not excee dd. For valves routinely tested at one (1) or three (3) month intervals, a test interval extension is allowed. This extension shall not exceed twenty five percent (25%) of the inspection interval. 5.0 CHECKLISTfSi l l 5.1 None
-vC) 6.0 ERQIIQEI 6.1 Test interval
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6.l 1 The valve inservice testing program covers a ten (10) year interval commencing on August 18, 1983 and terminating on August 17, 1993 as stated in Reference 2.1.8. 6.1.2 When the Edition and Addendum nf the Code are changed, such as at the beginning af a new ten year interval, the following individuals end agencies shall be notified and provided a copy of the new program: State of California (See Reference 2.1.14, the TQAM), AN!!, NRC. In addition, the following documents may need updating and shall be reviewed and updated as necessary: FSAR [ Reference l 2.1.15), Valve Relief Requests. TQAM and Technical Specifications (Reference 2.1.13). 6.2 Pre service Testina 6.2.1 Each valve, after installation and prior to service, shall be tested as required in Reference 2.4.5, Article IWV 3000. The:e tests shall be conducted under conditions similar tn l those to be experienced during inservice tests. Safety and relief valves which will be removed and bench tested during subsequent inservice tests need not be installed prior to ( the preservice test. l
t NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023 V 3.5 1 UNITS _2 AND 3 REV!SION 7 PAGE 6 0F 208 i TCN ,7 - 16
-O 6.0 PROCEDURE (Continued) 6.3- Vaive Catenorl ,
6.3.1 Valves are categorized as follows: (Reference 2.4.5, < IWV2200):
.1 Category A velves for which seat leakage is limited to a specific maximum amouilt in the closed position for fulfillment of their function. '
.2 Category B valves for which seat leakage in the closed position is inconsequential for fulfillment of their [
function. l
.3 Category C valves which are self actuating in response to some system charac,teristic, such as pressure (relief valves) or flow direction (check valves).
.4 Category 0 4 valves which are actuated by an energy source capable of only one operation, such as rupture disks or ,
explosive actuated valves. ,
;- NOTE: -Valves identified in this Procedure have been -
placed in one or more of these categories. When (' - more than one distinguishing category i characteristic is applicable, all requirements of each of the individual categories are applicable. 4 Duplication or repetition of common testing requirements is not necessary. 4 6.3.2 All check valves are Category "C", however, some require that their seat leakage be limited to a specific amount. In these cases they are categorized at Category "AC". The categorization of-a check valve is not dependent-solely on the function performed by the valve, such as whether it is
- a containment isolation' valve. When determining the '
category of a check valve, as a minimum, the follt M aspects of its performance requirements shall be considered. If any of these considerations indicate that Category "C" testing may not be adequate. .the check valve shall be assigned Category "AC" and shall receive a seat. leak test as required by this program (See Reference 2.4.3. Question 107).
.1 - Determine whether the flow requirements for connected systems can be achieved with the maximum possible leakage through the check valve.
O .2 Evaluate the effect of reduced system flows resulting from the leakage of the check valve on the performance of other systems and components. ~
- . . __ _. _ ~ _ . _ __._--_ _ _. ___ . . _ _ _ . _ _ _ _ .
NUCLEAR ORGANIZATION ENGINE"tlNG PROCEDURE $023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 7 0F 208 TCN 7-16 ! - O 6 .0 PROCEDURE (Continued) 6.3.2.3 Evaluate the consequences of the loss of water from the system.
.4 Evaluate the effect that backflow through the valve may ,
have on piping and components, such as the effect of high temperature and thermal stresses. ,
.5 Determine the radiological exposure to plant personnel and '
the public caused by the leak. 6,4 Reauirements , 6.4.1 -1his program uses the same test interval definitions as those used in the Technical Specifications, namely, one month is defined as 31 days and one quarter is defined as 92 days, 6.4.2 Reference 2.4.5, Subsectioi IWV defines the requirements for in service testing of ' ode Class 1, 2 and 3 valves. Test results are intended to verify valve operational ' readiness on a continuing tasis. 6.4.3 Concerning. valves tested at Cold Shutdown Intervals: O .1 The establishment of the criority and test schedule for cold shutdown velves is the responsibility of the Station Technical Division. The IST Coordinator of the Technichl Division will execute this responsibility.
.2 (See Attachment 7. VRR No. 24). For each outage of greater than-48 hours, the IST Coordinator will. provide two lists 3 of valves to be tested prior.to returning to Mode 2 to Operations and Maintenance.
List'#1: . Valves which must be tested each outage (if it has been greater than 90 days since the last test).
- List #2
- Additional valves which must be. tested for the specific outage, p
NOTE: When a valve is need=1 in cold shutdown for system operability c...mples: the shutdown L cooling system, boric acid flow path or RCS h inventory control), but cannot be tested in - l advance of reaching cold shutdown, the valve shall be tested-within 48 hours of being placed in service. This testing should be incorporated into the proceduro for initiating system O,, operation upon reaching the applicable mode. l^ o l' -. ,_a_ _>.~._ ,. ., _ ._._,___.#.__
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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023 V 3.5 UNITS 2 AND 1 REVISION 7 PAGE 8 Of 208 7 TCN _7 - 10 I V 6.0 PROCEDURE (Continued) i 6.4.3.3 Operations and Maintenance will be required to conduct the testing prior to entering Mode 2 from cold shutdown and, within 30 days, provide the test results to the IST Coordinator. The Operations Supervisor of Plant Coordination and the Unit Maintenance Manager shall have the responsibility for monitoring the surveillance schedule for all valves, except for those listed in Reference 2.3.1. (These are the responsibility of the lechnical Division.)
.4 following each outage, the IST Coordinator will review the valve IST results and create a list (as in step 6.4.2.2.1 above) of the next set of valves requiring tests. This list will be based on four factors:
- a. The importance to safety assigned each valve not tested in the last 90 days,
- b. The maintenance history (reliability) of each valve,
- c. The time since each valve was tested,
- d. As a matter of policy, an initial requirement of 25%
- (minimum) of all cold shutdown valves will be tested
( each Mode 5 for the outage of greater than 48 hours duration. This new list will be sent to Operations and Maintenance, as in step 6.4.3.2 above, and the process repeated.-
.5 The test schedule for valves tested quarterly or at refueling intervals will not be addressed in the memo discussed above. Attachments 2 and 4 of this procedure provide sufficient direction for these tests.
6.4.4 Attachments 2 and 4 itemize all valves subject to the test requirements of this Procedure including the valve category and test mode. 6.4.5 Category A and 8 Valves
.1 Test frequency: Category A and B valves shall be exercised at least-once every three (3) months, with the exceptions defined below and as noted in Attachments 2 and 4.
Tl l L1
NUCLEAR ORGANIZATION ENGINEERikG PROCEDURE 5023 V 3.5 UNITS 2 AND 3 PAGE 9 0F 208 REVisipN7'-10 TCH d 6.0 PROCEDURE (Continued) 6.4.5.2 Exercising Procedure NOTE: Valves tested at cold shutdown intervals shall be tested when and as directed by the Technical Division IST Coordinator. See step 6.4.2.2, above.
.1 Valves shall be exercised to the position required to fulfill their function, unless such operation is not practical during Plant operation. If only limited oseration is practical during Plant operation the valve sia11 be pr.rt stroke exercised during Plant operation and full-stroked during each cold shutdown. Valves that cannot be exercised during normal Plant operation are specifically identified in Attachments 2 and 4 and shall be full stroke exercised during each cold shutdown.
.l.1 In case of freauent cold shutdowns, these valves need not .
be ex6.cisedit. ore often than once every three (3) months.
.2 The necessa:'y valve stem or disk movement shall be
- established by exercising the valve while observing either an appropriate indicator, which signals the reavired change (m'
of valve stem or disk position, or indirect evidence, such V) as changes in system pressure, flow rate or temperature which reflect stem or disk position.
.3 Power Operated Valves NOTE: If a valve exceeds its limiting stroke time it '
shall be considered IN0PERABLE until it is analyzed and the disposition is documented on an NCR. If a valve stroke time increases such that it is still within its Itmiting stroke time, but must be tested once each month as discussed below it shall be considered IN ALERT and may be considered OpEAABLE unless other conditions or circumstances dictate. differently.
.1 The limiting value of full stroke time of each power operated valve is specified, where applicable, in Attachments 2 and 4, Reference 2.3.4 stroke time limits are used where applicable, t
.2 The stroke time of all power operated valves shall be measured to the r.earest second or 10% of the maximum
' allowable stroke time, whichever is less, whenever such a valve is full stroke tested.
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NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023 V 3.5 UNITS 2 AND 3 REVlsipN 7 PAGE 10 Of 208 TCN Y"10
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V 6.0 PRotEDURE (Continued) 6.4.5.3.2.1 The valve stroke time is measured with a stopwatch. The stopwatch is started when the valve is actuated and stopped when the back light for the desired valve position is the only one illuminated.
.3 Test Requirement for valves in ALERT Range is stated in the Code as follows. *lWV3413(c): if an increase in stroke time of 25 % or more from the previous test for valves with stroke times greater than 10 sec. or 50 % or more for valves with stroke times less than or equal to 10 sec, is observed, test frequency shall be increased to 3nce earh month until corrective action is takon at which time the criginal test frequency shall be resumed."
.3.1 [See VRR No, b in Attachment 7) Instead of the previous stroke time, use a ggf.[R[HCE STROKE T1HE.
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.3.1.1 If an increase in stroke time of 25 % or more from the EEEIREFCE STRQXE_Ilh[ for valves with stroke times greater than 10 sec. (or 50 % or more for valves with stroke times less shall than or equal be increase to once 6 to 10 sec.)h eac month until correctiveis observed, test fre action in taken, at which time the original test frequency
{q j shall be resumed.
.3.1.2 REFERENGLSTROKE TlhI is thu average stroke time since the last maintenance that could have affected stroke time (or last three strokes, whichever is greater). The EEEERIEGE LTH9LE.llhE value if used for comoarison of test data shall be established when the valve is known to be in good operating condition.
.3.2 During valve stroke testing, any abnormality or erratic action shall be reported to the SRO Operations Supervisor.
He shall report this to the IST Conrdinator, if, in his judgement and based on his previous experience, this is warranted. (See Reference 2.4.5, Paragraph IWV 3417(a)). The objective of this requirement is to identify and repair valves (where needed) that are not operating properly, in cases where this is not reflected in en unusual or non-conforming stroke time.
.3.3 Power operated valves with normal stroke times of 2 seconds or less are referred to by the NRC staff as " rapid acting valves.* Relief has been granted from the requirements of Section XI, Paragraph IWV 3417(a) for these valves when the maximum limiting value of 2 seconds or less is assigned.
When the 2 second limit is exceeded. the valve shall be declared inoperable and corrective action taken in I. ' b) accordance with Reference 2.4.5, Paragraph IWV-3417(b). Also, see VRR No. 16 in Attachment 7.
NUCLEAR ORGAMIATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 11 Of 200 l TCN 7-10 i I /,T V 6.0 PROCEDilE (Continued) 6.4.5.4 Valves in Regular Use
.4.1 Valves which operate in the course of Plant operation at a frequency which would shtisfy the exercising reqdrements of this Procedure need not be additionally exercised, provided that the observations otherwise required for testing are made and analyzed during such operation and recorded in the Plant record at intervals no greator than three (3) months.
.5 Valves in Systems Out of Service
.5.1 If valves are in a system that is out of service, exercising is not required for such valves except within 30 days prior to the return of the system to service.
.6 Fail Safe Valves
.6.1 Valves with fail safe actuators shall be tested by observing the operation of the valves upon loss of actuator power. If these valves cannot be tested once every three (3) months, they shall be tested during each cold shutdown.
p In case of frequent cold shutdowns, these valves need not j be tested more often than every three (3) months. 6.4.6 Category C Valves
.1 Safety and Relief Valve Tests NOTE: Safety and relief valves which will be removed and bench tested during subsequent inservice -
tests need not be installed prior to.the preservice tests (Reference 2.4.5, Article IWV 3000). Otherwise, each valve, after installation and prior to service, shall be tested as required by Reference 2.4.5, Article IWV 3000. These tests shall be conducted under conditions similar to those to be experienced during subsequent inservice tests.
.l.1 Test frequency
.l.1.1 The safety and relief valves will be tested with the following frequencies:
.l.1.1.1 There are 18 safety valves (of the same type) per unit in
,-~ tha main steam system for which testing is required. All
( valves will be tested on a schedule determined using i} Reference 2.4.5, Table IWV 35101 as shown in Attachment 6.
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023.V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 12 Of 208 6.0 PROCEDURE (Continued) 6.4.6.1.1.1.2 There are 2 pressurizer relief valves per unit. Each will be tested on a schedule determined using Reference 2.4.5, Table IWV 35101 as shown in Attachment 6.
.l.1.1.3 There is onewill unit. Each (1) be tested on a 30 month cycle. shutdown cooling
.1.1.1.4 The scheduling and bookkeeping required fur these tests shall be the responsibility of Maintenance.
.l.2 Testing Procedure
.l.2.1 Safety and relief valve setpoints will be tested in accordance with ASME Performance Test Code 25.31976 aid Reference 2.4.6. Bench testing with suitable hydraulic or pneumatic equipment, testing with system pressure or testing in place with hydraulic or pneumatic assist equipment may be used.
.l.3 Additional Tests
.l.3.1 If any valve in a system fails to function properly during a regular test, additional valves in the system O shall be tested as determined by the requirements of U Reference 2.4.5, Paragraph IWW3513. If any of these additional valves fail to function properly on test, all valves in the system in this category shall be tested.
.2 Check Valve Tests
.2.1 Test Frequency
.2.1.1 Check valves shall be exercised at least once every three months, with exceptions as defined below and in Attachments 2 and 4. Certain check valves are tested during the corresponding pump IST (See Reference 2.3.1).
.2.1.1.1 Check valves tested at Cold Shutdown intervals shall be tested when and as directed by the IST Coordinator in the Technical Division.
.2.1.2 The scheduling and bookkeeping required for these tests will be the responsibility of Station Engineering. To determine the operational mode required for valve testing, refer to Attachments 2 and 4, Test Mode Column.
.2.1.3 The responsibilities for testing (including scheduling and bookkeeping) of check valves are explained in Reference 2.2.1.
i NUCLEAR ORGANIZAT10h ENGINEERING PROCEDURE $023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 13 0F 208 m TCN 7-10 (V ) 6.0 PROCEDURE (Continued) 6.4.6.2.2 Exercising Procedure 2.2.1 Check valves shall be exercised to the position required to fulfill their function, unless such operation is not pri.;tical duritig plant operation. Normally closed check valves that cannot be operated during normal Plant operation art identified in Attachments 2 and 4 and shall be exercised during each cold shutdown or refuelings. In case of frequent cold shutdowns, these check valves need not be execised more often than once every three (3) months.
.2.2.1.1 Normally Open Valves: Valves normally open during plant operatior,, whose function is to prevent reverse flow, shall be tested in a manner which proves that the disk travels to the seat promptly on cessation or reversal of flow. Confirmation that th disk is on its seat shall be 9y visual observation, by observation of appropriate pressure ladicatid.s in the system, or by other positive means.
.2.2.2 Normally Closed Valves: Valves normally closed during
,e , plant operation, whose function is to open on reversal of
(' pressure ditierantial, shall be tested by proving that the disk moves promptly N ay from the seat when the closing presscre differential is renoved and flow through the valve is initiated, or a mechanical opening force is applied to the .tisk.
.2.2.2.1 Confirmation that the disk moves away from the seat shall be by visual observation, by observation of substantially free flow through the valve. as indicated by appropriate pressure indications in the system, or by other positive means. This test may b( made with or without flow through the valve.
.2.2.2.2 Full Stroke testing (open) of check valves is normally done using flow.
NOTE: The following may be a new requirement for certain tests. Station Techni<,a1 Division and Operations will jointly develop the revised test techniques, document the bases :Pd implement them during the upcoming refueling cycles for Units 2 and 3 (to be completed prior to cycle 7).
.2.2.2.2.1 The flow test shall be designed such that degradation p]
s A of check valve performance can be detected. This means that rather than specifying only the minimum flow fore the test (exampit: " greater than 2000 gpm"), a range of :ccep. table flow shall be used (examples:
"2000 1 150 gpm", or, "1850 to 2150 gpm").
4
1 1 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 14 Of 208 i TCN _l ._1 6 6.0 ERQt @ B[ (Continued) 6.4.6.2.2.2.2.2 The test setup and alignment shall be standardized to the extent possible to allow comparison of results and examination of trends.
.2.2.2.2.3 The criteria and the basis for the critoria shall be documented and available for the auditors. (See Reference 2.4.3, Question 7).
6.4.7 For valves identified in Attachments 2 and 4 that are to be tested by disassembly, the internals shall be visually inspected for worn or corroded parts, and the valve disks shall be manually exercised. It shall be verified that the valve is capable of full stroking and that the internals of the valve is structurally sound. This testirg shall be conducted at each refueling outage on a rotating basis. One valve of this group (a group is identified as all the valves of the same manufacturer, sire, model and service will be tested each successive refueling outage, until)the entire group has been tested. If the disassembled valve is not capable of beinn full stroke exercised or there is binding *or failure of the valve internals, the remaining valves in this group n shall also be disassembled, inspected, and manually full stroke exercised during the same outage. A partial (-) .flgLtjtilshill.}e performed on the disassembled valve fallowino rejtssembiv. but before it is returned to . Afr.Y.Kt.
.1 If a check valve within a sample group is' disassembled and inspected in a non refueling outage, the interval may altered for the balance of the group if it is justified in writing by the Technical Division Cog. Engineer and L approved by the Cog. Engineering Supervisor. The justification shall address the effect of the proposed disassembly and inspection schedule on the sampling program. The justification shall address the maintenance history and known valve condition from the previous inspections rather than sub,iective qualitative judgement.
Position 2 of Reference 2.4.2 indicates the criteria that need to be addressed (See Reference 2.4.3, Question 14). ^ 6.4.0 Category D Valves
.1 Th re are no Category D Class 1, 2 or 3 valves at San Onofre Units 2 and 3. Therefore, the %ction XI test requirements pertaining to this catego , are not applicable.
6.4. 9 Contatnment isolation Valves Requiring Seat Lcak Tests U .1 These valves are identified in Attachments 2 and 4 and shall be tested at least once every two (2) years in accordance with Reference 2.4.1, Appendix J.
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023.V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 15 Of 208 r3 ICH _7 _] 6 ! \ C' 6.0 PROCEDURE .(Continued) 6.4.9.1.1 These valves are containment isolation valves and will be tested with a pressure differential in the same direction as when the valve is performing its function, with the following exceptions:
.l.1.1 Globe type valves may be tested with pressure under the seat.
.1.2 Butterfly valves may be tested in either direction, provided their seat construction is designed for sealing against pressure on either side.
.l.3 Leakage Rate t.nalysis
.l.3.1 Leakage rate measurements will be compared with previous measurements and with the permissible leakage rates specified using Reference 2.3.2. The acceptance criterion detemined(semissibit Leak Rate) for each valve can beay taki rates of all penetrations in the Appendix J Program except the valve under test. These are available from the records created in accordance with Reference 2.3.2.
.r~ The result is the acceptance criterion of the valve onder
( ) test in SCCH or other appropriate units. NOTE: Where a question of the acceptability of the valve leak rate measurement may exist, the allowable leakage can be calculated using the rules of Reference 2.4.5, Subarticle IWV 3423(e).
.l.4 Test Medium valve repair, replacement and maintenance
.l.4.1 The test medium used for the leak rate tests will be specified in Reference 2.3.2 for the various valve tests.
6 a.10 Reactor Coolant System Pressure Isolation Valves Requiring Seat Leak Tests
.1 These valves are identified in Attachments 2 and 4 and shall be tested in accordance with appitcable Operating Instructions.
.l.1 These valves are reactor coolant system pressure isolation valves, and will be tested with the pressure differential in the same direction as when the' valve is performing its function, with the following exception:
O
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 16 Of 208 TCil 7*16 O d 6.0 M I M (Continued) 6.4.10.1.1.1 Leakage tests involving pressure differentials lower than function pressure differentials are permitted in those types of valves in which service pressure will tend to disinish the overall leakage channel opening, as by pressing the disk into or onto the seat with greater force. Gate valves, check valves and globe type valves having function pressure differential applied over the seat, are examples of valve applications satisfying this requirement.
. l.1.2 When leakage tests are made in such cases using pressures lower than function maximum pressure differential, the observed leakage shall be adjusted to function maximum pressure differential value. This adjustment shall be ,
made by calculation appropriate to the test media and the
- ratio between test and function pressure differential, assuming leakage to be directly proportional to the pressure differential to the one half power.
. 2 Leakage Rate Analysis
. 2.1 Leakage rate measurements shall be compared with previous measurements and with the permissible leakage rates
.n specified in Reference 2.3.5.
Q .3 lest Medium i
. 3.1 The test medium used for the leak rate tests will be specified in applicable Operating Instructions.
6.4.11 Valve Repair, Replacement and F .itenance
. 1 ' After'a valve or its. control system has either been >
replaced, repaired or has undergone maintenance that . could affect its performance, and prior to the time it is t returned to service, it shall be tested as necessary to demonstrate that the performance parameters which could be affected by the replacement, repair, or maintenance are within acceptable limits. Adjustment of stem packing, removal of the bonnet, stem assembly or actuator, or disconnection of hydraulic or electrical lines are examples of maintenance that could affect valve performance parameters. 6.4.12 Position Indication Test (PIT)
. 1 All valves with remote position indicators which are inaccessible for direct observation during Plant operation shall be visually observed at the same (or
/3' - greater) frequency as scheduled refueling outages, but-
_V not less than one observation every two (2) years to confirm that remote valve indications accurately reflect valve operation. wr -w't e # "i--ggpa-'m n d,- y *-'f- - - y'gM 7 ir + - - -' mv+-v- - eg ' yrDmm g'
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023.V 3.5 PAGE 17 Of 208
)
, UNITS 2 AND 3 VISgN } 6 i
l ( U 6.0 PROCEDUR[ (Continued) NOTE: The requirements to initiate an NCR apply to the 151 Program. See Reference 2.3.3 for NCR initiation criteria. 6.5 Corrective Measures NOTES: 1. It will be the Shift Superintendent's responsibility to determine the Technical Specification requirements for operability of the affected system.
- 2. The requirements to initiate an NCR apply to the IST Program. See Reference 2.3.3 for criteria applicable to the initiation of NCRs.
- 3. THE TECtLNICAL SPECIFICATION CLOCKi in cases during valve testing in systems covered by the Technical Specifications, if the valve is declared inoperable, this would result in the plant entering an action statement of the Technical Specifications. When a valve fails its IST, the valve is considered inoperable and the Technical Specification Action Statement time starts. Recalibration of instrumentation and retesting to show the valve is still capable of fulfilling its function are an p)
V alternative to replacement or repair and not an additional action that can be taken before declaring the valve inoper.ble, in summary, the NRC has taken the position (Reference 2.4.2. Attachment 1, position 8) that as soon as the data is recognized as exceeding the limiting value of full stroke time for valves, the associated valve must be declared inoperable and the Technical Specification Action time must be started, i>j Category A and B valves
.- l If a valve fails to exhibit the required change of valve stem or disk position, notify the Shift Superintendent immediately. Corrective action shall be initiated immediately. The valve shall be declared inoperable as required by the Technical Specifications (Reference 2.1.3).
6.5.1.2 When corrective action is required as a result of tests made during cold shutdown, the condition shall be corrected before startup. A retest showing acceptable operation shall be run following any required corrective action before the valve is returned to service.
, 6.5.2 Category C Valvas t .1 Safety and relief valves failing to function properly I
during testing shall be repaired or replaced, and shall successfully pass a retest before being returned to service.
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 ! UNITS 2 AND 3 PAGE 18 0F 200 i REVISg0N7
, TCH " 1.0 *
't> 6.0 12E10JF.1{ (Continued) 6.5.2.2 If a check valve fails to exhibit the required change of dish position, notify the Shift Superintendent immediately. Corrective action shall be initiated immediately. The valve shall be declared ir.'te able immediately per Technical Speciff tations. When corrective action is required th a result of u sting during cold shutdown, the condition shall be enected before startup. A retest showing acceptable vorformance thall be run following any required correctivo actica before the valve is returned to service.
6.S.3 Valves Requiring Seat Lea 4 Tests
.1 Valves with leakage ra'es exceeding the permissible leakage rates will b9 replaced or repaired.
.2 Reference 2.4.5, Paragraph IWV 2427(b), specifies additional requirements on increased test frequencies for valve sizes of six inches and larger and repairs or replacement over the requirements of IWV 3427(a). The NRC has determined that the usefulness of Paragraph IWV 3427(b) does not justify the burden of complying with this requirement.
impleme'ited in this Accordingly[,thisParagraphisnot program. See Reference 2.4.2, (Vc) Position 10). 6.6 [gerligni NOTE: Valves which fall into the classifications below are identified in Attachments 2 and 4 and shall be cycled,-as practicable, t.t each cold shutdown or refueling, but not more often than once nyery three (3) menths, 6.6.1 Any valve which, when exercised (cycled),,could put the Plant in an unsafe condition, should not be tested. Below are examples of the *,ypes of valves excluded from exercising (cycling) tests during Plant operation.
;) All valvos whose failure in a nonconservative position during the cycling test would cause a loss of system function.
l .2 All' valves whose f silure to close during a cycling test would result in a loss of Containment integrity. l _, .3 All valves which, when cycled, could subject a system to L( ) _ pressures in exces t of their design presst:res. l }
I NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023.V 3.5 : i UN115 2 AND 3 REVISION 7 PAGE 19 Of 208 n TCN .1 _L6 . 6.0 ftQCIDEI (Continued) 4 6.7 Instrumentation 6.7.1 Instrumentation used shall meet the requirements of Reference 2.4.5. Instruments, together with their transmitters, where used, shall be calibrated in accordance with the appropriate Maintenance Procedures. 6.8 Determination of Proaram Scone 6.8.1 Dur strategy for determining the valve IST program scope involvesthefollowing[SeeReference2.4.2, Attachment 1, Position 11):
. 1 Review of design changes by the IST Coordinator.
. 2 Guidance on IST Scope rules is provided to the engineering organizations associated with the design process.
. 3 Criteria used for determining IST Program scope includer, References 2.4.5, 2.4.2 and 2.4.3 and Regulatory Guide 1.26. In addition Engineering judgement and prudence are applied when reference criteria are not directly .
applicable. 6.8,2 _ The following activities apply to cases where plant conditions prevent full stroke testing with flow for
- check valves to be tested in the open direction. The IST
> Coordinator and the Cog Engineer will periodically evaluate whether plant conditions have been altered in
- such a way that full stroke testing'using flow is-possible. If so, the program'shall be revised as well a's the test procedures to provide for such testing.
[ Reference 2.4.3,-Question 11.) i 6.8.3 Determination of Reasonableness of Stroke Time Acceptance Criteri- for Power Operated Yalves .
. 1 Position 5 of Attachment 1-to Reference 2.4.2 states.-in part:
... !WV 34)3(a)'of the ASME Code requires that the licensee specify-the limiting value of full stroke time of each power operated valve. -The corrective action of IWV 3417(b) must be followed'when these limiting values are exceeded. The Code does not provide.any requirements or guidelines for ,
establishing these limits nor does it identify the relationship that should exist between .these limits and any limits identified for the relevant valves in
% the plant Technical Specifications or safety analysis.
M -- M ** ---g:1gi- c g y, e .y->w.y_+y-- 9 gr -+v y---e.nw s, 9W4 +g -++-yw.fy ., .,e 9 g y g ,- e.,yw ya,-pawg-i spa.,-- ir +pg,- yqu ryi - y -+.- gs,wy- - - , . - msw w- W+
NUCLEAR ORGANIZATION ENGINEERING PROCEDURL S023 V+3.5
-UNITS 2 AND 3- REVISION 7- PAGE 20 Of 208 TCN 7-16 6.0 PROCEDURE (Continued)-
6.8.3.1 (Continued) 3 "The purpose of the limiting value of full-stroke time is to estsblish a value for taking corrective action on a degtaded valve before the valve reaches the point where there is a high probability of failure to perfom its safety function if called upon. The NRC has, the N fore, established the guicelines described
-below regarding limiting values of full-ctroke time for power operated valves.. ,
"The limiting value of full stroke time should be
-based on the valve reference or average stroke time of
. a valve when it is known to be in good .:ondition and
- operating properly. The limiting value would be t reasonable deviation from this rcference stroke time based on-the valve size, valve type, and actuator-type. The deviation should not be so restrictive that it-results in a valve being declared inoperable-due to reasonable stroke time variations. However, the deviation used tc establish the limit should be such m- that corrective action would be taken for a-Valve that
+ may not perform its fntended function. ,
"When the Tschnical Specifications or safety analysis limit for a valve is less than the val.ue established using the above guidelines, the Technical Specifications or safety analysis limit should be used as the limiting value of the full-stroke time.
"When the Technical Specifications or safety analysis limit for a valve is greater than the value-established using the above guidelines, the-limiting
- value of-full-stroke time thould be based on the above guidelines instead of the Technical Specifications or
--safety analysis limit."
6.8.3.2- Periodically the IST Coordinator will review the stroke time history and average stroke times.for each_ valve in-the. Units-2 and 3 IST Programs and determine the approariate stroke time limits. This determination will use tie above guidelines. Revised stroke time limits will be incorporated into the IST Program documents. 6.8.4 Des'ign reviews _ discussed previously will provide the IST - Coordinator with a mechanism to reverify that Relief Requests are still valid based on ongoing plant modification activities. In addition, the IST fe. Coordinator will keep. abreast of changes in technology for this same purpese. (Reference 2.4.3, Question 69).
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.3 UNITS 2 AND 3 REVISION 7 PAGE 21 0F 208 k TCN 7
- 10
( ) V 6.0 PROCEDUBI (Continued) f.8.5 Application of Post-Modification Results B
.1 in addition to changes in scope of the IST Program, ,
design modification may also possibly affect the testing even though no component additions or deletions occur as a result. For example if any valve operator is modified or replaced, the stroke time might be affected for a valve alrndy in the IST Program,
.2 Accordingly, these design changes will be identified as
"!ST Program Affecting'. By the engineer developing'the change package in accordance with the design procedures currently in effect. The IST Coordinator will review these changes, and determine if there is an impact on the IST programs such as a stroke time limit change.
.3 The IST Coordinator is responsible for determining if an IST Program change is needed an implementing it as soon as reasonably achievable.
.3.1 This might include requesting additional non routine stroke tests to determine if the stroke time has been p' : hanged substantially for a modified valve and then i
changing the IST Program to reflect the newly developed requirements. 7.0 RECOR05 7.1 Records pertaining to inservice testing of valves snall be maintained
-in accordance with Reference 2.4.5 Article IW 6000 of Section XI.
The records shall include, as a minimum, the following: 7.1.1 A summary listing consisting of a schedule check-off list for valve testing an:1 bookkeeping processes, and 7,1,2 Records of tests and examinations. 7.2 Records of tests and examinations shall be provided to the Technical ' Division IST Coordinator (or made available for inspection) within 30 days of completion of the test or examination (copy), and to CDM-SONGS (original) as soon as possible thereafter by Operations and H>intenance. () L C' l PCroy:0155d-7T.wS1
NUCLEAR ORGANIZATION ENGINEERING PROCEDilRE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 22 0F 208 ATTACHMENT 1 [~N, TCH 7-10
.)
jl(SERVICF VALVE TESTING TABLE INFORMATION A. Attachments 2 and 4 dispiny the following columns:
- 1. Lode Class: ASME Section Ill Class of the valves listed.
- 2. Sec XLC.jkt : ASME Section XI Category, See IWV-2200.
- 3. Yalve and Actuator Twog: Abbreviated as follows:
yalve Tvom Abbreviation Gate GA Globe GL Check CK Safety SV Relief RV Butterfly BTF Stop Check SrK Ball LALL [m). Split Disc Check SOCK v- Angle AV Aq1. gator Tvoe @lffliation Motor Operated M0 Air Operated A0 Solenoid Operated 50 Hydraulic Operated HY Self Actuate.1 SA Manual H Electro Hydraulic EH
-4. Norm Pos._: Normal position of the valve.
S. Jest Tvoe and Mode: Test lists the test or tests that will be performed for each valve to fulfill the requirements of Reference 2.4.5, Subsection IWV. The following tests and abbreviations are used: Seat Leak Test AT Valve will be seat leak tested at the appropriate functional di f ferential . pressure. Full Stroke Exercise Teit BT
~T Valve will be full stroke exercised for operability in the direction L (d necessary to fulfill its safety function.
ATTACHMENT 1 PAGE 1 0F 6
NUCLEAR ORGANIZAi!ON: ' ENGINEERING "ROCEDURE' S023-V-3.5 UNI'S 2 AND 3 REVISION 7 PAGE 23 0F 208.
.. ATTACHMENT 1
{g} TCN __7 11 0 INSERVICE VALVE TESTING _ (Continued)
' 5.-(Cont'inued)~ _
Partial-Exercise Test BTP Valve will be part-stroke exercised when full stroke exercisina is impractical, check Valve Exercise Test CVT . Check ~ valve will- be exercised to the position required to fulfill its function. .This functional test will be verified by the operation of
-the required system.
4 Check Valve Partial Exercise Test CVP Check valve will be aart stroke exercised. (i.e., disc moves away- from seat) when full ctro(e exercising is impractical. - Fail Safe Test FST All valves with f ail safe actuators will _be tested to verify proper fail: safe operation upon loss of actuator power. d Position' Indication Check- PIT All _ valves with remote' position indicators will be checked to verify that remote valve indications accurately reflect valve position. DRelief Valve-Setooint Check 'RVT Relief and, Safety vavle setpoints will be verified in accordance with Reference 2.4.5-IWWV-3510. g' ATTACHMENT 1 PAGE 2 0F 6
o NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V.3.5 l UNITS 2 AND 3 REVISION 7 PAGE 24 0F 208 ATTACHMENT 1
/' TCN 7-10 (S)
INSERVICE VALVE TESTING (Continued) Test Mode indicates the frequency at which the tests will be performed. The following abbreviations are used: Cold Shutdown CS (See Attachment 7, VRR No. 24) Valve testing at cold shutdown is valve testing which comences not later than forty eight (48) hours after cold shutdown and continues until required testing is comple'.ed or plant is ready to return to service. " Cold Shutdown" testing will be initiated within 48 hours of entry into Mode 3 for valves requiring testing in Mode 3, within 43 hours of entry into Mode 4 for valves requiring testing in Mode 4, and within 48 hours of entry into Mode 5 for valves requiring testing in Mode 5. Completion of all required valve testing is not a requisite to plant startup. Valve testing which is not completed during a cold shutdown will be performed during
. subsequent cold shutdowns to meet the Code specified testing requirements. No valve need be tested more often than once every 90 days. Section XI of the Code uses Cold Shutdown "CS" for all modes other than Operating and Refueling and therefore "CS" as used in the IST Program can include Tech Spec Modes 3, 4 or 5. All CS valves are not testable in all modes and therefore applicable implementing procedures (Operating Instructions) will specify which valves can be tested in a given Mode,
( v} 8011: For planned cold shutdowns, where testing of all the valves identified in the IST program for testing in the cold shutdown mode will be completed, exceptions to the 48 hours may be taken.
- Normal Oneration OP Valve tests with this designation will be performed once every three months.
Reactor Refuelino RR Tests with this designation shall be conducted at least once every two years [See Reference 2.4.5, Paragraph IWV-3422] except for relief valve tests which are scheduled in accordance with Reference 2.4.5, Paragraph
-IWV-3511,
- 6. Str. Time: Stroke time upper limit. The valve under test may stroke at any duation up to and including this value, unless otherwise noted in the table.
\_/
ATTACHMENT I PAGE 3 0F 6 l
JNUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5
--UNITSi2 AND:3L -REVISION 7 PAGE 25-OF 208
.. ATTACHMENT-1
- [xj N TCN 16
' ~
INSERVICE VALVE TESTING (Continued)
'7. Test Oraanization-(Procedure): "0" indicates that the Operations Division is responsible for conducting this test, "M" indicat$s the Maintenance Division and'"T* indicates the Station Technical Division.
- The entry in parentheses is the Procedure number used to conduct the test.-
8.- Notes and Valve Relief Reauests: Self explanatory (see Section B,
-Explanation of Notes).
9 .' . Operational modes as defined by the Technical Specifications are as follows:- a Reactivity % of Rated Average Coolant 59.iit Condition, K,,, Thermal Power
- Temnerature-1 --Power Operation- 2 0.99 > 5% 1 350'F 2 -
Startup 2 0.99 s 5% 2 350*F L3.-:-Hot-Standby -< 0.99 0 > 350*F
~ .O N/ 4 Hot Shutdown- < 0.99 0 350'F>T ,, >200'F ,
5 - Cold Shutdown < 0.99 -O s 200'F 6' - Refuelin9_ ** ' s 0.95 0 $ 140'F >
=* Excluding Decay Heat 4
t** Fuellin-the reactor vessel with the vessel head closure bbits less than fully tensioned or.with the head removed. S' O ATTACHMENT 1 PAGE 4 0F 6
.-4., . ._ . _ _ _ . - . . .
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 26 0F 208 ATTACHMENT 1 (~'j - TCN 7 .10
-t/
B. LXPLANATION OF NOTES NOTES:
- 1. This valve will be tested by disassembly, the valve internals shall be visually inspected for worn or corroded parts, and the valve disk shall be manually exeicised. .See Section 6.4.6 for additional details of the testing requirements for this valve.
- 2. This valve is a safety valve or relief valve and will be tested at the frequency stated in reference 2.4.5, IWV-3511,
- 3. The maximum stroke time associated with these valves are protected values and may only be changed under certain circumstances. See
-Attachment 8.
- 4. The maximum allowable stroke times for valves 2(3)HV4705, 2(3)HV4706,'.2(3)HV47)5, 2(3)HV4716 and 2(3)HV4730 are protected values and may not be relaxed without revision to the disposition of
- Non conformance Report (NCR) G-992.
- 5. This valve cannot be partially stroke exercised during Plant operation.
O)
'v'
- 6. All motor operated valves fail as is and, therefore, do not require a fail-safe test as. described in Reference 2.4.5, IWV-3415, 7.- This valve is stroked manually only. It does not function as a power operated valve during the design basis event'and is therefore tested by local manual actuation. Accordingly, there is no acceptance limit for stroke time.
- 8. This valve is tested when the Containment spray system is tested per the Technical Specifications,
- 9. Main Steam Isolation Valves 2(3)HV8204 and 2(3)HV8205 shall be part stroke tested quarterly and full stroke tested at cold shutdown intervals. Solenoid pilot valves 2(3)HY8204XI . 2(3)HY8204X2, 2(3)HY8205XI and 2(3)HY8205X2 shall each be exercised semi-annually, Solenoid pilot valves 2(3)HY8204Yl, 2(3)HY8204Y2, 2(3)HY8205Y1 and 2(3)HY8205Y2 shall be exercised at cold shutdowns. ("X1" and "Yl" are train "A" and "X2" and "Y2" are train "B".) This testing is in accordance with NCR 3-2504 and cannot be changed without a revision of this NCR, Also, see Technical Specification Requirement 4.1,6.3,
- 10. The seat leakage test for this valve will be performed in accordance with 10 CFR 50 (Reference 2.4.!), Appendix J requirements (see Procedure paragraph 6,4,8),
- 11. Inservice Testing of Unit 2 and Unit 3 Main Steam Dump Valves will
/~') -commence with completion of design changes identified in NCR G-949.
J ATTACHMENT 1 PAGE 5 0F 6
- NUCLEAR ORGANIZATION - ENGINEERING PROCEDURE S023 V-3.5
. UNITS 2 AND 3- REVISION 7 PAGE 27 0F 208 .
ATTACHMENT 1
.j(jl.. -TCN _7_ I6 ns _
zEXplANAT10N OF NOTES (Continued)
-12. Inservice Testing of valves S2(3)130lMUO27 and S2(3)l301MUO34 will commence with completion of facility changes _(PFCs) 2 89 6753 for Unit 2 and 3 89 6753 for Unit 3.
-13. The nitrogen supply valves to the CCW Surge Tanks are tested in pairs. That is to sav each pair is treated as a single valve for purposesoftheseatle,aktest. These valves are in' series and therefore cannot be tested for seat leakage separately.
- 14. The maximum allowable closure times for valves 2(3)HV-6212, 2(3)HV-6213, 2(3)HV 6218 and 2(3)HV-6219 are protected values and may not be changed without revision to the disposition of Nonconformance Report:(NCR) G-852.
-15. : 2(3)PSV9349 is a pressure relief valve and will .be tested at the frequency stated in the Technical Specifications.
- 16. Not used.
- 17. This valve is tested by indirect indication. The 10 second time hv duration is the nominal time required to start the diesel engine, During this time intcrval while engine is cranking to-start, the air start solenoid valves 'and air relay valves.are open.- A1_1 moving parts of t' .se valve are internal to the valve body. No position
, indicators external to the valve body' exists.-The-only positive means of indication that valve has stroked open during is either by
-witnessing the operation of the-air start motors or witnessing the-misting of exhaust air from the air start motors. Valve degradation or malfunction of operation will reduce diesel engine- starting E speed. These valves were purchased as part of the diesei generator skid and:are non-code valves (therefore, no-Valve Relief Request is necessary).
- 18. This check valve is required to undergo a partial stroke test (as a minimum)_ using flow following disassembiy,, inspection' and reassembly (see the various VRRs).
i [\ k) ATTACHMENT 1 PAGE 6 0F 6
, . --. - - ~ .- - - . - . . .. .. . .
NUCLEAR ORGAN 17AT10N- ENGINEERING PROCEDURE S023-V.3.5. UNIT'; 2 AND 3 REVISION 7- PAGE 28 0F 208 ATTACHMENT 2 N
^
TCN 16 INDEX P_aste h). tam. 29
. Air Con 6 1oning System- ......................... .
29 Auxil'.4ry Boiler System _. . . . . . . . . . . . . . . . . . . . . . . . . 30 Au x il i a ry F eedwa te r . . . . . . . . . . . . . . . . . . . . . . . . . . . . 32 . Boric Acid Makeup .-. . . . . .~. . . . . . . . . . . . . . . . . . . . . 33 Chemical - and Volume Control . . . . . . . . . . . . . . . . . . . . . . . 35 Chilled Water-.--. ..'.-. . . . . . . . . . . . . . . . .-. . . . . . . . 36 Component Cooling Water . ... .z. ..................... 42
- Condensate and Feedwater . . . . . . . . . . . . . . . . . . . . . . . .
44
' Containment HVAC (Normal) . . . . . . . . . . . . . . . . . . . . . . .. .. 45 Containment Spray!. . . . . . _ . . . . . . . . . . . . . . . . . . . . -
47 Diesel: Fuel Oil' System ._, . . . . . . . . . . . . . . . . . . . . . . . 47 > M Diesel Generator _ Air Start System .-. . . . . . . . . . . . . . . . . . . 49 l Diesel Generator System'. . . . . . . . . . . . . . . . . . . . . . . . . 50 ,
- Fire Protection-. . . . . . . . . . . . . . . . . . . . . . . . . . . . .
, . . . . . . . . 50-Fuel Stor Pool & Refueling . . . . . - . . . . . . . .
- Gas-Radweste- .- . . . . . . . . . . . . . . . . . . . .- . . . . . . . . . .-50 Liquid Radwaste~.1. . . . ........................51- 51:
Nitrogen Gas = . . . . . ..... . . . . . . . . . . . . . . . . . . . . . . 77 Nucl ear S ampl i ng . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 56 2 Nucl ear Servi ce Yater . . . . . . . . . . . . . . . . . . . . . . . . . . X'f ' Reactor Coolant . . . . . .-. . .-. . . . . . . . . . . . . . . . . . . . 56
; Resp. & Service Air System . .- . . . .-. . . . . . .-. . , . . . . . . 59
- Safety injection- ...........................6072 , . . . . . . . .
Salt Water Cooling . . ._, ... .-. . . . . . . . , Steam:. .;.:... . . . . . , ,_. . , . . . . . . . . . . . . . . . . . . . 75
. Sumps and'Orains . ... . . . . . . . , . . . . . . .._ . . . . , , . 79
}
LA ATTACHMENT 2 PAGE 1 0F 52
. NUCLEAR.0RCANIZATION- ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3- REVIS10N:7 PAGE 29 0F 208
~ ATTACHMENT , (~' TCN in-v i _. ;
10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station . (Test.Org's: M-Maintenance, 0 - Operations, T. Technical) Discussion of Cold Shutdown Intervals,:See Next Att. Valve Test Notes and-
'Sec' and- .
Type. Test Valve Code 'XI Size Actuator Norm and Str. Organizatil.i Relief-ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
** System:. Air %nditioning System
- 2HCV9918,= Hydrogen Purge Exhaust Control Valve l (Dwg.-: 40172B/G-2) Valve Mfg.: Fisher 2 'A. 6 BTF/M C AT/RR T(5023-V-3.13) 10
- 2HCV9945, Hydrogen Purge Unit A 080 Discharge Valve (Dwg.-: 401728/H-5) Valve Mfg.: Fisher- .
2 A. 6 BTF/M. C. AT/RR T(5023-V-3.13) 10 4
-* 2HV9917, Containment Hydrogen Purge Outlet Valve .. (Dwg.:.40172B/G-3)ValveMfg.: Fisher ~ (_'T :2' . A -. 5 'BTF/MO- C AT/RR T(S023-V-3.13) 6&lo U
- 2HV9946, Containment Hydrogen Purge Inlet IV Mfg. sher (Owg.{4072B/G
-*-'S21500 MOO 38 (3/4-038-C-396), ILRT Pressurization Connection
-(Dwg.: 40171B/C-2)- Valve Mfg.: - Kerotest .
2 A- 3/4 GL/M C~ AT/RR .T(S023-V-3.13). 10 i S21500MUO39 (3/4-039-C-396),'ILRT Pressurization Connection' ! (Dwg.: 40171B/D-1). Valve Mfg. :- Kerotest ' -1 2- .A- 3/4- GL/M- C AT/RR' T(S023-V-3.13) 10 i
** System: Auxiliary Boiler System
- S21312MUO37 '(2-037-C-387), Auxiliary. Steam-Inside Containment '
Isolation ' Valve 4
.(Dwg.: 40169C/D-4) Valve Mfg.: Vogt . .
2 A. 2 GA/M ~C -AT/RR T(5023-V-3.13) 10 L- S21312MUO38- . (2-038-C-~387),- Auxiliary Steam' Outside- Containment E Isolation Valve (Dwg.: 40169C/E-4) Valve Mfg.: Vogt !' -2: A 2- GA/M C AT/RR. T(S023-V-3.13) 10 { i.h ATTACHMENT 2 PAGE 2 0F 52 i
7, .
- NUCLEAR ORGANIZATION EC!NEERING PROCEDURE- 5023-V-3.5 UNITS'2'AND 3- RhiS10N 7- -PAGE 30 0F 208-ATTACHMENT 2
[:]-
- TCN 7-16 UM 10/16/91:
Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's:-M= Maintenance,-O.= Operations, T = Technical) Discussion of Cold Shutdown Intervals,-See Next Att. Valve' Test- Notes and See and~ Type Test Valve Code - XI' Size,: Actuator Norm and . Str. . Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
-** System: _ Auxiliary Feedwater1
- _ 2HV4705, AFW Control Valve - Steam Generator E088 3(Dwg.: 40160A/E-3) Valve Mfg.:'.WKM-B 6- C BTC/0P- - 33.5 0(S023 3-3.30 3,4&6
-GL/M0 3 B 6- 'GL/MO C- BT0/0P 35- 0(S023-3 3.30 3,4&6 3- B= 6; -C PIT /RR. 0(5023-3-3.30) 3,4&6 GL/MO
*'f2HV4706, AFW Control-Valve - Steam Generator E089 (Dwg;:i40160A/D-3) Valve Mfg.: WKM
- ' :; B -_ . 6 - -GL/MO C BTC/0P- 33.5 0(S023 3 3.30)_ 3,416 3 :B -6 GL/M0- C- 3,4&6.
BT0/0P . 35. 0(5023 0(S023-3-3.30);
. ;3 8 6~ GL/MO C PIT /RR- 3-3.30) 3,4&6
- 2HV4712, AFW Pump 2P504 Discharge to Steam Generators
~(Dwg.: 40160A/G-3) Valve Mfg.: WKM _ -
3 ,B- 4 :GL/MO- C- BTC/0P 36 - 0(S023-3-3.30)- 3&6 - 31 -B- 4 -GL/M0 C- BT0/0P' 36 0(5023-3)3.30) 3&6 133 :B _4 GL/MO C- PIT /RR: 0(5023-3 3.30) 3&6
*P 2HV4713, AFW Pump:2P141 Discharge to Steam Generators
. -(Dwg~ := 40160A/B-3) Val _ve Mfg. : WKM:
3- B; 4: GL/MO- :C STC/0P 36 <0(S023-3-3.30) 3&6
'3 8 4 -GL/MO- C BT0/0P 36 0(5023-3-3.30)- 3&6 3; ,B: 4 GL/MO 'C- PIT /RR: 0(S023-3-3,30)- 3&6 2HV4714.? AFW Isolation Valve to Steam Generator E088
--(Dwg. :; 40160A/F-1)~ Valve Mfg. : Fisher 12LB: 16 GL/EH. C BTC/0P 10- -0(S023-3-3.30) 3 B: L6- _GL/EH_ C: BT0/0P 10 0(5023-3-3.30) 3
'B 6 -GL/EH- C FSTC/0P 0(5023-3 3.30) 3
- 2D .B 6 -GL/EH C PIT /RR. 0(S023-3-3.30) 3-
- -' 2HV4715,: AFW Isolation Valve to- Steam Generator E089 g - (Dwg.: 40160A/0-2) ~ Valve Mfg.: WKM 2=' B L6' GL/MO- ~C BTC/0P 10 0(S023-3-3.30) 3,4&6 B .6 -GL/MO C BT0/0P 10 0(5023-3-3.30) 3,4&6
.2 B 6 GL/M0 C PIT /RR 3,4&6 0(S023-3-3.30)
L t
- ATTACHMENT 2 PAGE 3 0F 52 L - -
' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3- REVISION 7- PAGE 310F 208 ATTACHMENT 2 C.)-
TCN 7-18
; k/
W11_2 10/16/91
. inservice Testing Program for Valves
-San Onofre Nuclear Generating Station
- (Test Org's: M Maintenance, 0 Operations. T Technical)
Discussion of Cold Shutdown Intervals, See Next Att.
.. Valve Test Notes and Sec and- Type . Test Valve Code XI ' Size' Actuator Norm and Str. Organization Relief ClassCat.(in.) Type .Pos. Mode Time (Procedure). Requests
- 2HV4716,' AFW Pump Turbine Trip and Throttle Valve-
- (Dwg.: _401608/E-3) Valve Mfg.: Gimpel Inc.
3' B_ 4 GA/MO- .C BT0/0P ~ 13.5 0(5023 3-3.30) 3,4&6
.3 B- _4_ =C PIT /RR' 0(5023-3-3.30) 3,4&6 GA/MO
* . 2HV4730, AFW ~Isolatior. Valve to Steam Generator E088 (Dwg.:-'40160A/F-2) Valve Mfg.: WKM 2 B- 6 GL/MO .C BTC/0P 10 0(S023-3-3.30 -3,4&6 21 , -B 6' GL/MO:: .C - BT0/0P 10- 0(S0233-3.30 3,4&6 2- ~B .6 GL/MO- ,C PIT /RR 0(S023 3-3.30 3,4&6
*1 2HV4731, AFW ! solation Valve to Steam Generator E089 1p.) . (Dwg.:'40160A/D-1) Valve Mfg.: Fisher b -2 'B .6 GL/EH C .BTC/0P 10 0(S0233-3.30) 3 2 B_ 6 GL/EH -C BT0/0P 10 0(5023-3-3.30) 3 2- -- B 6 GL/EH C FSTC/0P 0(5023-3-3.30) 3 2- -
B ~6 GL/EH.-. C PIT /RR- 0(5023-3-3.30) 3
- 2HV4762',-E/H Bypass Valve for AFW. Valve 2HV4712 (Dwg.: 40160A/F-3) Valve Mfg.:' Control Components 3- -B~ GL/EH C BTC/0P .40 0(5023-3-3.30) 3 B~ 4. GL/EH- C- FSTC/0P 0(S023-3-3.30)
- 3~ 'B - 4 GL/EH- C PIT /RR 0(5023-3-3.30) 2HV4763. E/H Bypass Valve' for AFW Valve 2HV4713 (Dwg.: 40160A/C-3) Valve Mfg.: Control Components 3 B- 4 'GL/EH- C BTC/0P 40 0(S023-3-3.30) 3
-- 3 B 4 GL/EH. C FSTC/0P _0(5023-3-3.30) 3' B ;4 GL/EH C PIT /RR 0(5023-3-3.30)
- S21305MU121 (6-121-D-598), AFW Pump 2P140 Supply to Steam Generator E089 (Dwg.: 40160A/D-3) Valve Mfg.: Anchor / Darling 3- LC 6- .CK/SA C CVT0/CS 0gS023 3-3.31.2) 5
- S21305MU126'(6126-D-598), AFW Pump 2P141 Discharge Check Valve L (Dwg.: 40160A/B-4) Valve Mfg.: Anchor / Darling 3' C 6 CK/SA C- CVT0/CS -0(5023-3-3.31.2) 5 RcO f ATTACHMENT 2 PAGE 4 0F 52 4
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5' UNITS 2 AND 3 REVISION 7 ~ PAGE 32 0F 208 ATTACHMENT 2 / TCN 7-16
)
UNIT 2 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance. 0 - Operations, T Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code- XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S21305MU532 (6-532-D-598), AFW Pump 2P504 Discharge Check Valve (Dwg.: 40160A/G 4) Valve Mfg.: Anchor / Darling 3 C 6 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5
- S21305MU547 (6-547 D 598) AFW Pump 2P140 Discharge Check Valve (Dwg.: 40160A/E-3) Valve Mfg.: Anchor / Darling 3 C 6 CK/SA C CVT0/CS O(5023-3-3.31.2) 5
** System: Boric Acid Makeup
- 2FV9253, Makeup Water to Volume Control Tank m (Dwg.: 40125B/G 2) Valve Mfg.: ITT J
) 3 B 3 GL/A0 C BTC/0P 2 0(S023-3-3.30) w/ 3 8 3 GL/A0 C FSTC/0P 0 3 B 3 GL/A0 C PIT /RR 0(S023-3-3.30) l5023-3-3.30)
- 2HV9231, Boric Acid Makeup Pump 2Pl75 Recirculation to Tank T072 (Dwg.: 40125A/D 8)-Valve' Mfg.: ITT ,
- 3. B 2 GL/A0 C BTC/0P 2 0(S023-3-3.30) 3 B 2 GL/A0 C FSTC/0P 0(5023 3-3.30) 3 B 2 GL/A0 C PIT /RR 0(S023-3-3.30)
- 2HV9235 BAMU Tank T072 to Gravity Feed to Charging Pump suction (Dwg.: 40125A/B-5) Valve Mfg.: Target Rock 3 B 3 GA/MO C BT0/CS 12 0(S023-3 3.31) 5&6 3 8 3 GA/M0 C PIT /RR 0(5023-3-3.31) S&6
- 2HV9236, Boric Acid Makeup Pump 2Pl74 Recirculation to Tank T071 (Dwg.: 40125A/D-1) Valve Mfg.: ITT 3 B 2 GL/A0 C BTC/0P 2 0(S023-3-3.30) 3 B 2 GL/A0 C FSTC/0P 0(5023-3-3.30) 3 B 2 GL/A0 C- PIT /RR 0(S023-3-3.30)
- 2HV9240, BAMU Tank T071 to Charging Pump Suction Header Control Valve (Dwg.: 40125A/B-4) Valve Mfg.: Target Rock 3 B -3 GA/MO C BT0/CS 12 0(S023-3-3.31) 5&6 3 B 3 GA/M0 C PIT /RR 0(S0'23-3-3.31) 5&6 73 ATTACHMENT 2 PAGE 5 0F 52
_ .-= - - _ _ - _ _ _ _ _ _ -_ _ _ . _ _ __ _. _ _ _ ..-_. __ - _ _ - . _ _ . - _ _ _ _ _ _ . _ _
--T' E _
r
- 'NUCLEIR' ORGANIZATION ENGINEERING PROCEDURE S023-V 3.5 '
['
; UNITS 2 AND 3i ~REVIS10N'7 PAGE.33 0F 208'
-- ATTACHMENT 2 zTCN 16 j
E c. 10/16/91--
'-> Inservice Testing Program for Valves-
__ . San Onofre Nuclear Generating Station _ (Test;Org's:-MMaintenance,0-Operations,T.. Technical)_ Discussion of Cold Shutdown intervals, _ See Next Att. . Valve - Test Notes and _ See and Type - Test _ Valve Code -XI Size Actuator Norm and -Str. Organization Relief C1assCat(in.) Type l Pos.. Mode -Time-(Procedure) Requests
- *- 2HV9247, BAMU Pump to Chargihg Pump-Suction Control Valve
~(Dwg.: 40125B/E-5) Valve Mfg.r Target Rock .
;3J B 3z . GA/MO. .C BT0/CS ;12 5&6 -
0{S0233-3.31) OgS023 3,3.31) S&6 3 : 8 -. - 3 GA/MO: iC: ' PIT /RR-
' ' S21218MUO334(3-033 D-675),:BAMU Pump D 175~ Discharge Check _ Valve
- J(Dwg.:-~ 40125B/B 5) Valve Mfg.: Aloyco/Walworth.
3- ;C _3 - lCK/SA C- 1CVT0/CS 0(5023-3-3.31.2) 49 : *-- S2121SMUO35 '(3-035-D-676), BAMU Pump 2Pl74 Lascharge; Check Valye m (Dwg.-: 4012bB/D 5) ~ Valve Mfg.:' Aloyco/Walworth pq 3 CD 3/ - CK/SA? qC- CVT0/CS O(5023-33.31.2) bi
~
* - S21218MUO46 (3-046-Y 675), _ Deniineralized Water.to Boric Acid Mixing Tee .
'(Dwg.::40125B/G-3) Valve' Mfg.: Aloyco/Walworth 2: C' 3 CK/SA ,--:C CVTC/0P ~ T(S023 V-3.5.4)
** System: Chemical and Volume Control
'*L 2HV9200, Charging Pumps to Regenerative Heat Exchanger E063 '
J - -(Dwg.:J40123A/D-3); Valve Mfg.: Fisherj ,
,2J ' !AT '2;' ~ GL/A0;; 0-' AT/RRx - T(5023 V-3.'13)- S&lo . -t
;A1 L2 z2' GL/A01 10- <BTC/CSL8' . 0(S023-3-3.31) = 5&l0-2:- <A : GL/A0 -_0 BT0/CS 25 0(5023-3-3.31) 5&l0
.2 A ~ ! 2- _GL/A0; .0f 'FST0/CS- .
0(5023-3-3.31) S&l0 - 2 ~A-- 2- GL/A0 0 PIT /RR- 0(S023-3-3.31) 5&lo
* '2HV9205L Regenerative Heat Exchanger to Letdown Heat Exchanger-
.(Dwg.: 40123A/F 3) Valve ~ Mfg.:- ~ Fisher r
. '2 ~ A; 121 lGL/AOL 0 AT/RR .
T(5023-V-3.'13 ) : 3,5&l0-2: 1A- -2 GL/A0 0 BTC/CS - -~ 4 - 0(5023-3-3.31) 3,5&l0 , 2 H2 A" ' 2 ;GL/A0- 0 FSTC/CS O(5023-3 3;31) _ 3,5&l0 2 A' _2l -- GL/AO-- 10 . PIT /RR 0(50233-3.31): . 3,5&l0
- *L ;2LV02278, VCT Outlet Valve
-(Dwg.: 401'24A/B-5) Valve Mfg.: . Target Rock
.2~~=B'4 ~ 'GA/M03 BTC/CS '11 - 0(S023-3 3.31) S&6-
. .. s , ._ .2- B: '4l GA/MO-- 0 PIT /RR' 0(5023-L3.31) 5&6
- ATTACHMENT 2 PAGE 6 0F 52
-4 *r y--w,y e g- F
_ 4 .
. _-- . - _ - _ _ -_.__m . _. . --- . .
, , J
' NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE- S023 V 3.5 x ~ UNITS 2=AND 3- -REVISION 7 PAGE 34 0F 208
;,s, ATTACHMENT 2 s TCN t ~ y g.
_ .IRil ! 10/16/91' - 9
.: Inservice Testing Program for Valves 1 San Onofre Nuclear Generating Station g
i (TestOrg's: .M-Maintenance, Operations, T = Technical)
' Discussion of Cold Shutdown Intervals, See Next Att.
Valve- Test Notes and Soci and- Type; - Test Valve Relief Code 1XI : Size -Actuator Norm and- Str.. Organization ClassCat'(in.) Type - Pos. Mode Tirne (Procedure) Requests
- 2TV9267,s Letdown Containment Isolation Valve '
3A/F 3 alve Mfg. stinghou e j2; "9'h40
.: 2 A: 2- :GA/M0- 0- .BTC/CS 13- 0 5023-3-3.31 3,5,6110 -
;2 A- 2 GA/MO: : 0 PIT /RR- 0(5023-33.31 3,5,6&l0 -
- S21208MU015 (4-015 C-675),rVCT to: Charging Pump Suction Check Valve ,
(Dwg.:"40124A/B-4) Valve Mfg.:- Aloyco/Walworth
-s 2 C. 4 CK/SA : 0- CVTC/CS 0(S023-3-3.31.2)
* . S21208MU017;(2-017-C-554),: Charging Pump 2P192 Discharge Check Valve W
g 2
- (Dwg.: 40124B/C-3) Valve Mfg.: - Kerotes; C. 2.: LCK/SA C--
CVT0/0P T(5023-V-3.5.4) ' -.
- S21208MU067L(2 067 C-554), Charging, Pump 2P190 Discharge Check Valve
. -(Dwg.: 40124B/G;2) Valve Mfg.:--Kerotest-2= C 2 CK/SA C~- CVT0/0P :T(S023-V-3.5.4)
*:- S21208MUO691(2-069'C-554).-Charging Pump:2P191 Discharge Check Valve (Dwg.: 401'24B/D-2) Valve Mfg;:' Kerotest 2- ' C :2 sCK/ SAL sC" CVT0/0P =. .T(5023 V-3.5.4) w J*M S21208MUO82, (3 082 CJ 675), Gravity Feed:-' BAMU Tanks to Charging .
Pump 2P190 Suetion: . (Dwg.: 140124B/H;5) Valve Mfg.:? Alovco/Walworth: _ c2" - C l3 ' i CK/SA -- - CL .CVT0/C. '0(S023-3-3.31.2).:S
"* -521208MUO83l(3-083;C-675),<BAMU Pumps to Charging Pumps Suction Header
-(Dwg.: 40124B/F 7) Valve Mfg.:- Aloyco/Walworth-y29 5C3 i3j ~ jCK/SA Cf CVT0/CS- 0(5023-3-3.31.2) 5 2**;S21208MU1221
;(2-122 C-554), Charging' Primps Check '/alve to Regen Heat n ,
Exchanger E063 .. . .
- (DW. 40123A/D-4): Valve Mfg.:- Kerotest
- 2;: AC1 2i ' CK/SA- C 10 VRR-14 AT/RR T(COD-V-3.13) 4 -
>Zs 'AC CK/SA: C} 'CVTC/RR- T(S023 V 3.13) 10 VRR 2 AC L2 3/SA C CUO/0P M 023- R 5.4) 10 6 .
1 ATTACHNENT 2 PAGE 7 0F 52 w ~- w t e v a w - v --e
em
- NUCLEAR ORGANIZATION- ENGINEERING-PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7-- PAGE 35 0F 208
-- s -ATTACHMENT 2 g/~~Y TCN 7-1s d lHilI__&
10/16/91-Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M-Maint nance. 0 = Operations, T = Technical) ' Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and Valve See and~ Type. Test
- Code 'XI Size Actuator Norm and Str. Organization Relief Class: Cat (in.) Type Pos. Mode Time (Procedure) Requests
* -521208MU130 (2-130-C-334), Contmt Isol - Chg Pump Disch to Aux Spray Regen HX Bypass
-(Dwg.: 40123A/B 2) Valve Mfg.: Kerotest 2 A' 2 GL/M C- -AT/RR' T S023-V-3.13) 7&lo 2 A- 2- GL/M C BTC/CS 0 S023-3-3.31) 7&l0 2 A 2- GL/M C .BT0/CS 0 50?3-3-3.31) 7&l0
- 2. -A 2 GL/M C PIT /RR 0 S023-3-3.31) 7&l0 ,
'** System: Chilled Water-
* : 2HV9900,- Containment Cooling Supply Isolation Valve Penetration 45
-- (Dwg . : _40170A/G 4) Valve Mfg.: Fisher 2- 'A "8- .BTF/MO 0- -AT/RR T(S023-V-3.13) 3,6&l0 i e%
2 -A 8 BTF/M0 0 BTC/0P 14 0(5023 3-3.30) 3,6&l0 - 2 _A 8= BTF/MO 0 PIT /RR' 0(S023-3-3.30)- 3,6&l0
* -2HV9920, Containment Isolation Valve - Cooling Supply
(- (Dwg.: 40170A/G-3) Valve Hfg.: Fisher-2- A1 81 .BTF/AO 0 AT/RR T S023-V-3.13) 3&l0 2 A 8 'BTF/A0= 0- BTC/0P _12- 0 5023-3-3.30) 3&lo "
- 2- A <8- ,BTF/A0 0 FSTC/0P- 0 5023-3 3.30) 3&l0'
- 2: A :8- BTF/A0 0: PIT /RR -0(5023-3-3.30) 3&l0
- *> 2HV9921, Containment Isolation- Valve - Cooling Return (Dwg,: 40170A/F-3) Valve Mfg.: Fisher
- 2. A 8- -BTF/A0 AT/RR T(S023-V-3.13)- 3&l0 A: -8 BTF/A00 - 0 BTC/0P - 26 0(S023-3-3.30) 3&l0 2 'A.
8 -- BTF/A0' 0- FSTC/0P 0(S023-3-3.30) 3&lo
- 2- 'A: 8 BTF/AO. O PIT /RR~ 0(S023-3-3.30) 3&l0
-* 2HV9971,' Containment Isolation Valve - Cooling Return, Pen 46
-(Dwg.: 40170A/F-4) Valve Mfg.: Fisher 21 ' A- '8- :BTF/MO O AT/RR T(5023-V-3.13) 3,6&l0 h -- 2 A- -8 BTF/MO -0 BTC/0P 13 0(S023-3-3.30) 3,6&l0
- 2 A: 8 BTF/MO: ,O PIT /RR 0(S023-3-3.30) 3,6&l0
- SA1513MUB30, (l'l/8-830-D *), Aux 01dg Emerg Chiller E336 Oil Cooler
__ . Outlet Check Valve 4-V Q-_ -(Dwg.: 40179E/G-7) Valve Mfg.: l
- 3. C 1-1/8 CK/SA C CVT0/0P 0(S023-3-3.20) l- ATTACHMENT 2 PAGE 8 0F 52 L
~ .
LNUCLEARORGANIZATION ENGINEERING PROCEDURE S023 V 3.5
._ UNITS 2TAND 3 REVISION 7 PAGE 36 0F 208 c ATTACHMENT-2
'!. c1 TCN 7-16 L/
UMl_2 10/16/91 1.n ervice Testing Program for Valves San Onofre Nuclear Generating Station
-(TestOrg's: M Maintenance. 0 Operations, T - Technical)
Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See _and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time-(Procedure) Requests
*- SA1513M0835 (1 1/8 835-D *), Aux Bldg Emerg Chiller E335 011 Cooler
- Outlet Check Valve l (Dwg.: 40180D/G-7) Valve Mfg.: , 3 C- 1 1/8 CK/SA C CVT0/0P 0(S023 3-3.20)
** System: Component Cooling Water-
*' 2HCV6537,' CCW Pump 2P024 Miniflow Block Valve
.(Dwg.: 40127A/F-2) Valve Mfg.:' Fisher _
'3- B 10- BTF/A0 0 BTC/0P 5 0(5023-3-3.30) 3 B- 10 BTF/A0 0 FSTC/0P. 0(S023-3 3.30) 3~ B 10 BTF/A0 0 - PIT /RR 0(5023-3-3.30) -
U
- 2HCV6538, CCW Pump 2P025 Miniflow Block Valve (Dwg.: 40127A/E-2) Valve Mfg.: Fisher 3 8 10 BTF/A0 -0 BTC/0P 5 0 3 .B _10 -BTF/A0 0 FSTC/0P- .0(5023-3-3.30)
(5023-3-3.30) 3 B _10 BTF/A0 0 PIT /RR. 0(S023-3-3.30)
* -2HCV6539, CCW Pump 2P026 Miniflow Block Valve
_ (Dwg.: 40127A/B-2) Valve Mfg.: Fisher-13- B 110 BTF/A0 :0_ BTC/0P 5 0(5023-3-3.30)
-3; -b= -10. BTF/A0- 0 FSTC/0P- 0(5023-3-3.30) 3 -B 10 BTF/A0. 0- PIT /RR 0(S023-3-3.30)
- 2HV6211 Containment isolation Valve - CCW Non-Critical Loop (Dwg.:'40127F/G 3)1 Valve Mfg.: Fisher 2- -A 10~ BTF/M0 .O AT/RR T(5023-V-3.13) 3,5,6&l0-
'2 A ~10 BTF/M0 -0 3,5,6&l0 BTC/CS 15 _ 0{S023-3-3.31) 2: A- 10 BTF/M0 0 ' PIT /RR 0 45023-3-3.31) 3,5,6&l0
.'2HV6212, CCW from Heat Exchanger E001A to Non-Critical Loop
- (Dwg.: 40127D/E-7) Valve Mfg.: Fisher 3 B 28 BTF/A0' 0 BTC/CS 13 0(S023-3-3.31) 14
~3- B 28. _BTF/A0- 0 FSTC/CS 0(S023-3-3.31) 14
-3 B' 28 BTF/A0 0 PIT /RR' 0(S023-3-3.31) 14 2HV6213, Component Cooling Discharge to Non-Critical Loop l _O. (Dwg.: 401270/D-7) Valve Mfg.: Fisher i: V- 3 B 28 BTF/A0- 0 BTC/CS 14 0(5023-3-3.31) 14 3 B 28- BTF/A0 0 FSTC/CS 0(S023-3-3.31) 14
! 3 B 28 BTF/A0 0 PIT /RR 0(5023-3-3.31) 14 ATTACHMENT 2 PAGE 9 0F 52
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 37 0F 208 ATTACHMENT 2 j TCN ,,,,7_
- 16 U111.2 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: MaMaintanance, 0 9perations, I o Technical)
Discus. tion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- 2HV6216, Containment Isolation - CCW Non Critical loop Return (Dwg.: 40127F/C-5) Valve Hfg.: Fisher 2 A 10 BTF/MO O AT/RR T(5023-V-?.13) 3,5,6&l0 2 A 10 BTF/MO O BTC/CS 15 0(5023-3-3.31) 3,5,6&l0 2 A 10 BTF/MO O PIT /RR 0(S023-3-3.31) 3,5,6&l0
- 2HV6218, Component Cooling Water Pump Suction From Non-Critical Loop (Dwg.: 40127A/E-7) Valve Mfg,: Fisher 3 B 2B BTF/A0 0 BTC/CS 16 0(5023-3-3.31) S&l4 3 8 28 BTF/A0 0 FSTC/CS 0(S023-3-3.31) 5&l4 3 B 2B BTF/A0 0 PIT /RR' 0(5023-3-3.31) S&l4
)
- 2HV6E19, Component Coeling Vater Pump Suction From Noa-Critical loop
' (Dwg.: 4012/A/D-7) Valve Mfg.: Fisher 3 B 28 BTF/A0 0 BTC/CS 16 0(S023 3-3.31) 5&l4
. 3 B 28 BTF/A0 0 FSTC/CS 0(S023-3 3.31) 5&l4 3 8 28 BTF/A0 0 PIT /RR 0(5023 3-3.31) 5&l4
- 2HV6223, Containment Isolation - CCW Non Critical Loop Supply (Dwg.: 40127F/G-4) Valye Mfg.: Fisher 2 A 10 BTF/MO O AT/RR TM023-V-3.13) 3,5,6&l0 2 A 10 BTF/M0 0 BTC/CS 15 C(5023-3-3.31) 3,5,6&l0 4 2 A 10 BTF/M0 0 PIT /RR 0(S023-3-3.31) 3,5,6&l0
- 2HV6236, Containment isolation CCW Non Critical Loop Return (Dwg.: 40127F/C-5) Valve Mfg.: Fisher 2 A 10 BTF/MO O AT/RR T(5023-V-3.13) 3,5,6&l0 2 A 10 BTF/MO O BTC/CS 15 0(S023-3-3.31) 3,5,6&l0 ',
2 A 10 BTF/MO O PIT /RR 0(5023-3-3.31) 3,5,6&l0
- 2HV6366, Component Cooling Water to Emergency C< 'ng Unit E-401 (Dwg.: 401726/C-7) Valve Mfg.: WKM 2 A 10 GA/MO O AT/RR T(5023-V 3.13) 3,6&l0 2 A 10 GA/MO O BTC/0P ;2 0(5023 3 3.30) 3,6&l0 2 A 10 GA/MO O BT0/0P 12 0(SCd3-3-3.30) 3,6&l0 2 A 10 GA/MO 0 PIT /RR 0(S023-3-3.30) 3,6&l0 7
ATTACHMF,NT 2 PACE 10 0F S2 l _ , d
, g _ _
> , , , --_ ,-- . - - . -~ .. 4 - . - _ -
ki n 4 ( q-
, TNUCLEAR-ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5
? UNITS 2:AND-3 -REVIS10N-7 PAGE 38 0F 208- ,
' T2
-Vr ATTACH TCN 16-hMu). s r
UNIT 2 10/16/91 . - inservice Testing Program for Valves San Onofre Nuclear ~ Generating Station ba (Test Org's:-M-Maintenanco, 0 Operations, T = Technical)
/
Discussion of Cold Shutdown Intervals, see Next Att.- Valve- Test Notes and Sec - and - Type Test Valve ? Str. Organization As11ef Code- XI Size Actuator Norm and -Requests Class . Cat (in.) -Type _ Pos. Mode-- Time (Procedure) .
* . 2HV6367 Component Cooling Water to Emergency Cooling Unit E-401-'
(Dwg.: 40172B/D 7) Valve Mfg.: WKM 2 A 10 C AT/RR =T S023-V 3.13) 3,6&l0
~GA/MO.
2- A '10 C BTC/0P 12 0 5023-3-3.30 3,6&lo GA/MO
- 2. A GA/MO C BT0/0P 12 0 5023-3-3.30 3,6&l0 2' A- 10 GA/MO, C PIT /RR, 0(S023-3 3.30 3,6&l0
* -2HV6368, Component Cooling Water to Emergency Cooling Unit E-400
- (Dwg.:: 401728/E 7) Valve Mfg.:- WKM 2- .A :10. lGA/M0 0- -AT/RR T(5023-V 3.13) 3,6&lo
'2. A 10= :GA/MO 0 . BTC/0P .12: 0(5023 3-3.30 3,6&l0 10 , GA/MO- 0 .BT0/0P 12 0(5023-3-3.30 -3,6&l0 -
eA '2-~ -
-A 0; 3,6&l0 gj' 2: Af 10- GA/M0 PIT /RR .0(5023-3-3.30
- 2HV6369, Component Cooling Water to Emergency Cooling Unit E-400 (Dwg.:^ 401728/F-7) Vah'e Mfg.: WKM 2 -- A -10 'GA/MO .C. AT/RR -
T(S023-V-3.13) 3,6810 2: CAT loi GA/MOL C- BTC/0P 12 0(S023-3-3.30) 3,6&l0
> 2,' : A? :10' -GA/M0. C BT0/0P 12 0(S023 3-3.30). 3,6&l0 .
f, : 2, 'A 10 GA/MO C' PIT /RR - 0(5023 3-3.30)- 3,6&lo-4
- L 2HV6370,LComponent i tooling Water to Emergency Cooling Unit E-399- '
%- :2(Dwg.:: 40172B/0 2) Valve
.,N ^A 10 ~ GA/MO O-'Mfg.: -AT/RR-WKM - T(5023 V-3.13) 3,6&l0-
[It:H 2s A 10 GA/MO- 0 ' BTC/0P .12 - 0(5023-3-3.30) L3,6&l0
- 2 LA H 110 ' GA/M03 0' lBT0/0P - 12 O(S023-3-3.30) 3,6&l0-J 2 -- <A; 10 GA/M0 ' O PIT /RR -0(5023 3-3.30) 3,6&l0 J2HV6371, Component Cooling Water Ret, from Emerg Cooling Unit E 399
.~ (Dwg.f 401728/C-2)- Valve Mfg.: WFM
> 2 J A . - 10 , GA/M0- TC ' AT/RR .
~T(S023-V-3.13) 3,6&l0
=2; :A L10 GA/MO. C BTC/09 12 0(S023-3-3.30)-- 3,6&l0 2i A; :10- GA/M0 - C: Bi0/0P 12. 0(5023-3-3.30) 3,6&l0 (22 lA4 -GA/MO C PIT /RRf 0(5023-3-3.30) 3,6&10 E2HV6372, Component Cooling. Water to Emergency Cooling Unit E-402 p.:e (Dwg. :;401720/F-2) Valve Mfg.: WKM 2-~~ A 10 GA/MO O AT/RR .T(5023-V-3.13) 3,6410 Qfy;-f- 2 A 10' -GA/MO_ 0 BTC/9P 12 0(5023-3-3.30) 3,0&l0
'2 A 10- GA/MO. 0 BT0/0P 12 0(5023-3 3.30) 3,6&l0 Ly g 2- .A' 10: <GA/MO O PIT /RR- 0(S023-3-3.30) 3,6&l0 u< '
ATTACHMENT 2 PAGE 11 0F 52 m , l; t . , ,v ' ( , ,s 5 , I'# ! <
~ ;_ '. .;.
, . . _ , , , , . _ _ , _ . , . ,u, ., ,, _._ _ ,
NUCLEAR ORGANIZATION. ENGINEERING-PROCEDURE S023 V 3.5
- UNITS 2 AND-3 REV1SION 7 PAGE 39 0F 208 ,
x_ ATTACHMENT 2 [nf h TCN 7-in t 10/16/91-
=lnservice Testing Program for Valves San Onofre: Nuclear Generating Station (TestOrg's: M Maintenance. 0 = Operations. T = Technical)
Discussion of Cold Shutdown Intervals, see Next- Att. Valve Test _ Notes and
.- Sec. and Type. Test. Valve Code XI Size Actuator Norm and Str. Organization Relief
- Class Cat _ (in.)- Type - Pos._ Mode Time (Procedure) Requests
- 2HV6373, Component Cooling Water to Emergency Cooling Unit E-402 (Dwg.:: 40172B/E 2) Valve Mfg.: WKM 2- A- 10 GA/M0 C- AT/RR. T S023~V-3.13) 3,6&l0 2 A 10- GA/MO C- BTC/0F- 12 0 5023-3 3.30) 3,6&l0 2 'A 10 GA/MO. C BT0/0P 12 0 S023-3-3.30 3,6&l0 2 A: --- 10 GA/M0_ - C PIT /RR 0 S023-3-3.30 3,6&l0
- 2HV6500, Component Cooling Water from SDCS Heat Exchanger E003
-(Dwg.: 40127E/F-4) Valve Mfg.: Fisher 3 B 18 BTF/AO- _C BT0/CS 8' ;0(5023 3-3.31) 3&S 3 'B 18 ;BTF/A0 C FST0/CS 0(5023 3 3.31) 3&5
-3= B: ~18 BTF/A0 C PI1/RR 0(5023-3 3.31) 3&5 p
Y * :2HV6501, Component Cooling Water from-SDCS Heat Exchanger E004 (Dwg.: 40127E/C-4) Valve Mfg.: Fisher 3 B. 18= BTF/A0 C- BT0/CS 8 0(S023e3 3.31 3&5 3 B 18 BTF/A0 C FST0/CS- 0 S023-3 3.31 3&5 3~ B 18- BTF/A0 C PIT /RR 0 S023-3-3.31 3&5
* .2PSV6356, CCW Surge Tank T003 Relief Valve
-(Dwg.: 401278/H-5) Valve Mfg.:- Crosby 3 C 1- SV/SA- _C RVT/RR _M(S023-I-8.88) 2
-* 2PSV6359, CCW Surge Tank T004 Re':1ef Valve-
;(Dwg.: 40127B/D-5). Valve Mfg.: Crosby 3.' C_.I ~SV/SA C- RVT/RR M(S023-I8.88) 2
* 'S21203MR229, Drain' Valve, CCW Pump P026 Drain Line
-(Dwg.: 40127A/B 5) Valve Mfg.: Vo0t'
_3.- B,1 GATE /M C-- BT0/0P 0(Later). 7 p h)- ATTACHMENT 2- PAGE 12 0F-52
-NUCLEAR ORGANIZATION = ' ENGINEERING PROCEDURE S023 V 3.5 REVISION 7- PAGE 40 0F 208 .
LUNITS 2 AND 3-
-ATTACHMENT 2 TCN 7-16 t
THIS PAGE LEFT BLANK .
'() INTENTIONALLY E
l t 1 L , i. i.; l
-- \
-ATTACHMENT 2 PAGE 13 0F 52
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 41 0F 208 s ATTACHMENT 2
; TCN 7~1a v
1 1 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance, 0 Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S21203MR232, Drain Valve, CCW Pump P025 Drain Line (Dwg.: 40127A/D 6) Valve Mfg.: Vogt 3 B 1 GATE /M C BT0/0P 0(Later) 7
- S21203MR233, Drain Valve, CCW Pump P024 Drain Line (Dwg.: 40127A/G 5) Valve Mfg.: Vogt 3 B 1 GATE /M C BT0/0P 0(Later) 7
- S21203MU101 (28-101 0-725). CCW Pump 2P024 Discharge Check Valve (Dwg.: 40127A/G-4) Valve Mfg.: TRW/ Mission
-3 C 28 SDCK/SA OC CVP0/0P T(5023-V-3.5.4)
-, 3 C 28 SDCK/SA OC CVTC/CS 0(S023-3-3.31.2)
) 3 C 28 SDCK/SA OC CVT0/CS O(5023 3-3.31.2)
- S21203MU102 (28-102-D 725), CCW Pump 2P026 Discharge Check Valve
-(Dwg.: 40127A/8 4) Valve Mfg.: TRW/ Mission 3 C 28 SDCK/SA OC CVP0/0P T(5023-V-3.5.4) 3 C 28 SDCK/SA OC CVTC/CS 0(S023-3-3.31.2) 3 C 28 SDCK/SA OC CVT0/CS 0(S023-3-3.31.2)
- S21203MU103 (28-103-D-725), CCW Pump 2P025 Discharge Check Valve (Dwg.: 40lt.7A/D-4) Valve Mfg.: TRW/ Mission 3 C 23 SDCK/SA OC CVP0/0P T(S023-V-3.5.4) 3 C 28 SDCK/SA OC CVTC/CS 0(S023-3-3.31.2) 3 -C 28 SDCK/SA OC CVT0/CS 0(S023-3-3.31.2)
- S21203MU264 (1-264-D-627), Nitrogen Supply to Component Cooling Water Surge Tank T003A (Dwg.: 40127B/H-S) Valve Mfg.: Kerotest 3' AC 1 CK/SA C AT/RR T(5023-SPT-2) 13 3 AC 1 CK/SA C CVTC/RR T(S023-SPT-2) i3 S21203MU265 (1-265-D-627), Nitrogen Supply to Component Cooling Water Surge Tank T003A (Dwg.: 40127B/G-5) Valve Mfg.: Kerotest 3 AC 1 CK/SA C AT/RR T(5023-SPT-2) 13 3 AC 1 CK/SA C CVTC/RR T(S023-SPT-2) 13
,,~
LJ ATTACHMENT 2 PAGE 14 0F 52
(M3 fW D
, .w I
..\
h NUCLEAR ORGANIZATION 1: UNITS 2 AND 3 ENGINEERING PROCEDURE S023 V-3.5 REVISION 7 PAGE 42 0F 208 Skg 4 ~ ATTACHMENT 2 J p TCN _7 - 1 a , N W( M!ill Z
%'i Jf. ,
- 10/16/91 inservice' Testing Progran for Valves 2
-San Onofre Nuclear Generating Station ' P: t .(TestOrg's:-MMaintenance,0= Operations.T= Technical) y _ Discussion of Cold Shutdown Intervals, See Next Att, Notes and h 6 Sec Valve and Test-Type Test . Valve Relief Code XI Size: Actuator Norm and. Str. Organization ClassCat(in.) Type Pos. Mode Time (Procedure) Requests !
- L21203MU266 ,(1 266 0-627), Hitrogen Supply to Component Cooling Water. Surge Tank T0048
-(Dwg.: 40127B/0 5) Valve Mfg.:: Kerotest lCL T(S023 SPT-2): 13 3 ~ AC - ~ 1 CK/SA AT/RR 13 T ACL.1 1CK/SA- .C CVTC/RR T(S023SPT-2)-
- *OS21203MU267 (1-267-D 627), Nitrogen Supply to Component Cooling ,
-Water Surge Tank JT004B l' (Dwg.f 40127B/D 5) Valve Mfg.: Kerotest 3 AC 1 - CK/SA C .AT/RR T(50?3 SPT-2) 13 3 AC 'l -CK/SA C CVTC/RR T(5023-SPT-2)- 13
- S21203MU268- '(1-268 D 627), Nuclear Plant Service Water Supply to CCW V Loop A
-(Dwga ~ 40127B/D-3) Valve Mfg.: . . Anchor Darlint 3 AC 1; CK/SA. C' AT/RR T(S02'l SPT 2)
~ 3 .' AC.=1 CK/SA . C' CVTC/RR T(S023-SPT-2)
*1 521203NU269' (1-269 D 627), Nuclear Plant Service Water Supply to CCW w Loop B-(Dwg.: 40127B/B-3) Va' lye Mfg.: Anchor Darling-s3- AC 1: '
CK/SA- C AT/RR T(S023-SPT-2) T(S023 SPT-2); y- 3- AC; l .CK/SA' C. -CVTC/RR
** System: Condensate and Feedwater
- 2HV1105, Feedwater Bypass Valve ~:for Steam Generator E089
-(Dwg.: 40156B/B-6). Valve Mfg.:' Copes Vulcan, Inc.
B- 6 GA/A0 C BiC/CS 10 0(5023-3-3.31) 3 -i
-- ,B 6 GA/A0 C FSTC/CS 0(S023 3-3.31) 3
- B 6 GA/A0 C PIT /RR- 0(S023-3-3.31) 3
- 2HV1106,' Feedwater Bypass Valve for Steam Generator E088 (Dwg.: 40lS6B/E-6) Valve Mfg.: Copes Vulcan, Inc.
- B' 6 GA/A0 C BTC/CS 10 0(S023-3-3.31) 3
- B GA/A0 C FSTC/CS 0(5023-3-3.31) 3 B 6 GA/A0 C- PIT /RR 0(S023-3-3.31) 3 O-ATTACHMENT 2 PAGE 15 0F 52
+ NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V 3.5 UNITS'2 AND.3. ~ REVISION 7 . PAGE 43 0F 208 -
,_p ATTACHMENT 2 TCH : 7 " 16 '
y UNIT.2 10/16/91 Inservice' Testing Program for Valves
~
- San Onofre Nuclear Generating Station
-(Test 0rg'st M Maintenante,-0 = Operations. T < Technical)
- Discussion of Cold Shutdown latervals,.See NextLAtt. ;
Valve- Test - Notes and i Sec- and Type Test. Valve
' Code XI Size' Actuator Norm and Str. Organization Relief '
- Class Cat _ (in.) Type Pos. Mode Time (Procedure) Requests
- 2HV4047,:Feedsater Block Valve - Steam Generator E088 *
- (Dwg. :-' 40156B/F-4) Valve Mfg. : - ' WKM -
-B -204 GA/EH- -0 ~BTC/CS 10- 0(S023-3-3.31) 3&5
'B: 20) GA/EH 0 PIT /RR- -(5023-33.31) 0 3&5
'* 2HV4048,,Feedwater Isolation Valve Steam Generator E088
-(Dwg.+ 401568/F-2) Valve Mfg.: WKM~
20: ' GA/EH. :0
~2 ;B -
BTC/CS 10 10(S023-3-3.31) 3&5 2: -B' 20 GA/EH -0; FSTC/CS 0(S023-3-3.31)- 3&5 2: -B- GA/EH 0 PIT /RR 0(S023-3-3.31). -3&5
~
- TZHV4051, Feedwater Block Valve - Steam Generator E089 rf 3" ;(Dwg.: 40156B/B-4) Valve Mfg.: WKM
-. ' B 20= GA/EH- -0 BTC/CS 10 0(5023-3-3.31) 3&5 ,
B- -201 GA/EH; 0: . PIT /RR - 0(5023-3-3.31)- 3&5 ,
* '2HV4052,: Feedwater Isolation Valve"- Steam Generator E089
. (Dwg.: 40156B/B-2) Valve Mfg.: _WKM- ',
2; :B !20 GA/EH .O BTC/CS 10 0(S023-3-3.31) 3&5-2: B 20- .GA/EHf 'O FSTC/CS- 0(S0233-3.31) 3&5 2 :81 ' 20 GA/EH' >0 PIT /RR .0(S023-3-3.31) 3&5
*:-$21305MUO36:J(20-036-C-609),: Main Feed Check;at~ Steam Generator E089 :
(Dwg.: 40141A/C 7) Valve Mfg.:' . Anchor / Darling ; 2: C , 20 CK/SA= 0 CVTC/RR M(5023-I-6.160) 1&l8 VRR-20 2 C J20 CK/SA ~0 ~CVT0/CS- ~0(Later) 1&l8 VRR-20 -
*: 'S21305MU124 (6-124-C-599), AFW Check Valve at Steam Generator E089 -
J(Dwg;: 40141A/B-7)LValve Mfg.: Anchor / Darling - 2'" C 6' CK/SA 'C CVT0/CS:' 0(S^23-3-3.31.2) 5-
- p. *:'S21305MU129 (20-129-C-609), Main: Feed Check at Steam Generator E088-
-(Dwg.:'40141A/F-7) Valve Mfg.: Anchor / Darling _
p' 2' C CK/SA 0: CVTC/RR- ' .M(5023al-6.160)_ 1&l8 VRR 20
~2- C- -201 LCK/SA 0 CVT0/CS 0(Later) 1&l8 VRR 1* : S21305MU448 ~(6-448-C-599), AFW Check Valve at Steam Generator E088 E M; .(Dwg.:- 40141A/F-7) Valve Mfg.:- Anchor / Darling 'G 2 --- .C 6. ~ CK/SA- C .CVT0/CS 0(S023-3-3.31.2) 5 L
ATTACHMENT 2. PAGE 16 0F 52
-q j
- NUCLEAR ORGANIZATION:: ENGINLFRING PROCEDURE S023-V-3.5 i UNITS 2 AND-39 REVIS10d 7 PAGE 44 0F 208 !
ATTACHMENT 2
.. g ;
x)'; i TCN 7 -i n UNIT.2 R _ _ 10/16/91 Inservice Testing Program for Valves
' San Onofre Nuclear Generating Station >
(Test Org's: M Maintenance, 0 Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att.
. Valve Test Notes and Sec:- and -Type Test Valve t Code XI Size Actuator Norm and- Str. Org&nization Relief Class Cat (in.)_ Type 'Pos. Mode Time (Procedure) Requests ,
- System: Containment'HVAC (Normal)
* :2HV9821, Containment Isolation Valve . Mini) urge Supply
_ (Dwg.: ,40171A/C 6) Valve Mfg.: -Fisher 2 _A 8 BTF/A0- 0 AT/0P- T(S023-V-3.13) 3&l0 12 .. A 8 BTF/A0 0 -BTC/0P 5 OfS023-3-3.30) 3810
'2 A 8 BTF/AO- 0 FSTC/0P 0(5023-3-3.30) 3&l0 2 A- 8 0- PIT /RR 0(S023-3-3.30)_ 3&l0, t BTF/A0- < * - 2HV9823 Containment .lsolation Valve - Minipurge Supply (Dwg.: 40171A/B-4) Valve Mfg.: Fisher 0
W < 2 2- A A
;8 8'
BTF/A0 BTF/A0 0_~
.O.
AT/0P-BTC/0P 5 T(S023-V-3.13)
.0(5023-3-3.30) 3&l0 3&l0
- d. i2- A 8 BTF/AO- 0 FSTC/0P 0(5023 3-3.30) 3&l0 12__ A BTF/A0 0 PIT /RR- 0(5023-3-3.30)- 3&l0 ,
~
2HV9824,-Containment Isolation Valve ~- Minipurge, Exhaust ~ (Dwg.: 40171A/E-3) Valve Mfg.: Fisher , 2 A- 8. BTF/A0 0 AT/0P T(5023-V3.13) 3&l0 2 ~A. 8- BTF/A0 0 BTC/0P 5. :0(5023-3-3.30) 3&l0 2 -- -A- 8- BTF/A0--0 .FSTC/0P' 0(S023-3-3.30)- 3&l0 2 -A: 8 BTF/A0 0 PIT /RR 0(5023-3-3.30) '3&l0-
*L: 2HV9825, Containment Isolation Valve - Minipurge Exhaust (Dwg.: 40171A/E-7) Valve' Mfg.: Fisher-2 -- :A- 8-- BTF/A0- 0 AT/0P- T 3&l0 2: Ai 8 BTF/A0- 0- BTC/0P -5 OjS023-V-3.13) 3&l0 sS023-3-3.30)-
12 A. 8- BTF/A0- FSTC/0P' 0(5023-3-3.30)' 3&lo 2 A 8: - BTF/A0 '0- PIT /RR 0(S023-3-3.30) 3&l0 2HV9948,' Containment Purge Supply (Dwg.:140171A/B-6) Valve Mfg.: Fisher
~2' - Ai 42 o BTF/A0 C AT/0P- T(5023-V-3.13) 3&l0
-- 2 : -C .42 .BTF/A0 C BTC/CS: _12 0(5023-3-3.31) 3&l0 L
i: 2-- A- 42 BTF/A0' C FSTC/CS 0(S023-3-3.31) S&lo
* '2HV9549, Containment Purge Supply (Swg.: 40171A/D-4) Valve Mfg.: I uher
.2- A '42 BTF/MO C AT/0P T(5023-V-3.13) 3,6&l0
, _ {v,} L 2 A 42 BTF/MO C BTC/CS 12 3,6&l0 0(5023-3-3.31) ATTACHMENT 2 PAGE 17 0F 52 p
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 ' UNITS 2 AND-3' REVISION 7 PAGE 45 Of 208 ATTACHMENT 2 t TCN 7 'IL '/- UNIT 2 10/16hil Inservice Testing Program for Valves San f nofre Nuclear Generating Station (Test Org's: M. Maintenance, Operations, T = Technical) Discussion of Cold Shutdown Intervals, see Next Att. Valve Test Notes and See and - Type Test Valve ; Code. XI Size Actuator Norm and- Str. Organization Relief ClassCat(in.)-Type- Pos. Mode Time (Procedure) Requests
* -2HV9950, Containment Purge Exhaust (Dwg.: 40171A/C-3) Valve Mfg.: Fisher 2 A 42 BTF/MO C AT/0P T(5023-V-3.13) 3,6&lo 2 A 42 BTF/MO -C BTC/CS 12 0(50233-3.31) 3,6&l0
" 2HV9951, Containment Furge Exhaust (Dwg.: 40171A/E-6) Valve Mfg.: Fisher .
2 A' 42 BTF/A0. C AT/0P T(S023-V-3.13 3&l0 2 A 42 BTF/A0 C BTC/CS 12 0(S023 3 3.31 3&lo 2 A 42 BTF/A0- C FSTC/CS 0(S023-3-3.31 3&l0 j~ - ** System: Containment Spray
- l2HV8150, Isolation Valve - SDCS HX E004 to LPSI Header (Dwg.: 40114B/D 5) Valve Mfg.: Walworth 2 B 12 GL/MO C BTC/CS-90 _0(S023-3-3.31) 6 L
2 8 12 GL/MO C B10/CS- 90 0(5023-3 3.31) 6 . 2 B 12- GL/MO C ' PIT /RR 0(S023-3-3.31) 6
- 2HV8151,-Isolation Valve - SDCS HX E003.to LPSI Header
'(Dwg.::40114B/F-5) Valve Mfg.: Walworth 2 8 12. GL/M0 '- C BTC/CS 90 0(S023-3-3.31) 6 2 B 12 .GL/MO C -BT0/CS 90 0(S023-3-3.31) 6
;2 B~ 12 GL/M0 C PIT /RR 0(S023-3-3.31) 6-
- 2HV9367,- Containment Isolation Valve - Spray Header #1 (Dwg.:- 40ll4B/C-4) Valve Mfg.: Target Rock 2- A 8- GA/MO C- AT/RR . T(S023-V-3.13) 3,6&l0 L2 AL 8 GA/M0 C BT0/0P 12 0(S023-3-3.30) 3,6&l0 2 A 8' GA/MO C' PIT /RR 0(5023-3-3.30) -3,6&10
- 2HV9368, Containment Isolation Valve - Spray Header #2 (Dwg.: -40ll4B/G-4) Valve Mfg.: Target Rock 2 A C- GA/MO C AT/RR T(SO23-V-3.13)- 3,6&l0
- 2. -A- 8 GA/M0 C BT0/0P 12 0(5023-3-3.30) 3,6&l0 2 A- 8 GA/MO C PIT /RR 0(S023-3-3.30) 3,6&l0
\_/
ATTACHMENT 2 PAGE 18 0F 52
4 ,
- ENGINEF.RIE PROCEDURE S023.V-3.5 NUCLGR OMANIZATION UNITS 2 AND 3 REVISION 7 PAGE 46 0F 208 s ATTACHMENT 2 m
TCN - 2' - 1 6
'J UHil. 2 10/16/91 Inservice lesting Program for Va es San Onofre Nuclear Generating Sta. ion (Test Org's: H Maintenance. 0 - Operations, ( . Technical)
Discussion of Cold Shutdown Intervals, see Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Time (Procedure) Reques t.s C: ass Cat (in.) Type _Pos. Mode
* $21206MU004 (8-004-C-405), Containment Isolation Stop Check Valve -
Spray Header #1 (Dwg.: 40114B/C-3) Valve Mfg.: Anchor / Darling 2- AC $ AT/RR T(S023-V-3.13) 1,5,8,10&l8
%K/SA C VRR-13 2 AC 8 C CVP0/RR T(M.O.) 1,5,8,10&l8 SCK/SA VRR 13 2 AC S C CVT0/RR M(RMO) 1,5,8,10&lb SCK/SA VRR 13
- S21206HU006 (8 006 C-406), Containment Isolation Stop Check Valve -
m Spray Header #2 ( ) (Owg.: 40ll4B/G 3) Valve Mfg.: Anchor / Darling
~' 2 AU 8 SCK/SA C AT/RR T(S023-V-3.13) 1,5,8,10&l8 VRR-13 2 AC 8 SCK/SA C CVP0/RR T(M.O.) 1.5,8,10&l8 VRR-13 2 AC- 8 SCK/SA C CVT0/RR M(RMO) 1,5,8,10&I8 VRR-13
- S21206HUO10 (2-010-C 329), Pump 2P012 Miniflow Stop Check Valve (Dwg.:.40ll4A/D-3) Valve' Mfg.: Rockwell Edwards 2 C 2 SCK/SA C CVT0/0P T(S023-V-3.5.4)
- S21206MUO11 (2 Oll-C-329), Pump 2P013 Miniflow Stop Check Valve (Dwg.: 40ll4A/H-3) Valve Mfg.: Rockwell Edwards 2 C- 2 SCX/SA C CVT0/0P t(S023-V-3.5.4)
- S21206MUO12 (8-012-C-406), Spray Puap ~2P012 Discharge Stop Check Valve (Dwg.: 40ll4A/C-3) Valve Mfg. : Anchor / Darling 2 C 8 SCK/SA C CVTC/CS 0(S023-3-3.31.2) 5 2 C 8 SCK/SA C CVT0/C3 0(S023-3-3.31.2) 5
- S21206MUO14 (8-014-C-406), Spray Pump 2P013 Discharge Stop Check Valve (Dwg.: 40ll4A/G-3) Valve Mfg. : Anchor / Darling 2 C 8 SCK/SA C CVTC/CS 0(S023-3-3.31.2) 5 2 C 8 SCK/SA C CVT0/C3 0(5023 3-3.31.2) 5 ATTACHMENT 2 PAGE 19 0F 52
-NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S0;'3-V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 47 0F 208 '
,, ATTACHMENT 2 -l
't TCN 7-16 s
/
' l 10/16/91 Inservice Testing Program for Valves '
San Onofra Nuclear Generating Station (TestOrg's: M Maintenancs, 0 - Operations T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. , Valve Test Notes and See and Type Test Valve Code XI- Size Actuator Norm ata Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S21206MUO29 (8 029 C-645), Spray Pump 2P012 Discharge Check Valve to SDCS HX E004 (Dwg.: 40114A/C-3) Valve Mfg.: Anchor / Darling 2 C 8 CK/SA .C CVTC/CS 0(5023-3-3.31.2) 5 2 C 8 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5
- S21206MUO30 (8 030 C-645), Spray Pump 2P013 Discharge Check Valve to SDCS HX E003 (Dwgi: 40ll4A/G-3) Valve Mfg.: Anchor / Darling 2 C 8 CK/SA C CVTC/CS O(SCt.3-3-3.31.2) 5 2 C B CK/SA C CVT0/CS 0(S023-3-3.31.2) 5
.( )- ** System: Diesel Fuel Oil
- S22421MUO39 (2-039-D 627), Diesel Fuel Oil Transfer Pump 2P096 Discharge Check Valve (Ng. : 40ll6A/C 6) Valve Mfg.: Keroust 3 C 2- CK/SA C CVT0/0P T(5023-V-3.5.4)
- S2242' (2 048-D-627), Diesel Fuel Oil Transfer Pump 2P093 Discharge Check Valve (Dwg.: s J/D-7) Valve Mfg.: Kerotest 3 C z CK/SA C CVT0/0P T(S023-V-3.5.4)
- S22421!N54 (2-054 D-627), Diesel Fuel Oil Transfer Pump 2P095 Discharge Check Valve (Dwg.: 40116A/C-3) Valve Mfg.: Kerotest 3 C 2 CK/SA C CVT0/0P T($023 V-3.5.4)
'* .522421MUO63 (2-063-D-627), Di Asel Fuel Oil . Transfer Pump 2P094-Discharge Check Valve (Dwg.: 40ll6A/D-4) Valve Mfg.: Kerotest 3 C 2 CK/SA C CVT0/0P T(S023-V-3.5.4)
** System: Diesel Generator Air Start
- 2HV5931A, Diesel Generator 2G002, 20 Cyl., Air Start Relay Valve (Dwg.: 40110A/E-1) Valve Mfg.: Later
'( q -, 3 B GL/A0 C BT0/0P 10 0(S023-3-3.23) 17 v ATTACHMENT 2 PAGE 20 0F 52
, . _ _ _ _ _ . ._ ~. _ . . . _ . . _ _ _ _ . . _ . - _ . . _ . _ _ _ . _ _ _ . . _ _
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 - UNITS 2 AND 3 REVISION 7 PAGE 48 0F 208 ; ATTACHMENT 2 7-16_ TCN i Os ! 1E11.1 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintena"ce. 0 Operations. T = Technical) Discussion of Cold shutdown Intervals, See Next tit. Yalve Test Notes and See and Type Test Valve M.e XI Site Actuator Norm and Str. Organiration Relief ClassCat(in.)lype Pos. Mode Time (Procedure) Requests l
*- 2HV59318, Olesel Generator 2G002,16 Cyl., Air Start Relay Valve :
o-3(Dwg.: 8 40210B/E+2
- GL A0 ValveC Mfg.:
B10/0P Later 10 0(S023 3 3.23) 17
- 2HV5931C, Diesel Generator 2G002, 20 Cy)., Air Start Relay Valve 3(Owg.:
8 40110A/E2)A0Yalve GL/ C Mfg.: Later BT0/0P 10 0(502333.23) 17 ;
- 2HV59310,= Diesel Generator 2G002, 16 Cyl o Air Start Relay Valve 3(Dwg.: D 40110B/C - GL/Ai
- 1) Valve C Mfg.:BT0/0P Later10 0(5023 3 3.23) 17 3 * - hfV5931E, Diesel Generator 2G003, 20 Cyl., Air Start Relay Valve j
3(Dwg.: B- 40110C/E 1) Valve Mfg.: Later10-GL/A0' C BT0/0P 0(5023 3 3.23) 17
- 2HV5931f,; Diesel G.nerator 2G003, 16 Cyl., Air Start Relay Valve
- (Dwg. ' 401100/E 2), talve Mfg.:' Later
.3 8 GL/A0 .C BT0/0P 10 0(5023 3-3.23)- 17
- 23V5931G,-Diesel Generator 20003, 20 Cyl., Air Start Relay Valve ,
3 (D'ig.B': 40110C/E-2). Valve Mfg.: Later GL/A0 C BT0/0P 10 0(502333.23) 17 s
*--2HV5931Hi Diesel Generator 2G003,16 Cyl., Air Start Relay Valve s -(Dwg.:-401100/E 1) Valve Mfg.: Later '
, 3 8- GL/AO- C BT0/0P 10 0(5023-3 3.23) 17 e *: 2HY5955A1- Air Start Sol. - Diesel Generator 2C,002, 20 Cyl., Right Bank (Owg.: 40110A/L 4 Valve Mfo : MKW . -
$ w%, -
NA B 3 Way/50 C BT0/0P-10 0'S02333.23) 17
- 2HY5955B1, Air Start Sol. Diese1~ Generator 2G002, 16 Cy1., left Bank (Dwg.: _40110B/E 2) Valve Mfg.: HKW
-NA ' 8' 3 Way/SO C. BT0/0P-10 0(5023 3-3.23) . 17
" 2HY595501, Air Start 501. - Diesel Genuator 2G002, 20 Cyl., Left Bank f(Dwg.: 40110A/E 2) Valve Mfg.: MKW-
' 3 Way/50 C
[Au) NA B BT0/0P 10 0(5023 3 3.23) 17 - l ATTACHMENT 2 PAGE 21 0F 52
, . - , , . . , ~ - - + -
, - - . . - - aen.. e...p,,4,_,. c.-,~- , a J , , , , . , -,.......,.a, , , ,-n. .-~..,--n, ,-a..> - . . , . . . . ..n.,. . nn e r,, w - - . , - , - -
NUCLEAR ORGANIZATION . ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 49 0F 206 ATTACHMENT 2 YCN 7-18 UNIT 2 10/16/91 inservice T :, ting Program for Valves San Onofre Nucivar Generating Station (Test.Org's: M. Maintenance. 0 = Operations. T = Technical) Discussion of Cold Shutcown Intervals, See Next Att. Vahe T6st Notes and Sec and Type Test Yalve Code X1 Sir.e 4ctuator Norm and Str.-Organization Relief ClassCat:(in.) Type. Fos. Mode Time (ProcedJre) Requests
- 2HY5955D1, Air Start Sol. Diesel Generator 2G002, 16 Cyl., Right Bank !
- (Dwg.: 4011Cd/E 1) Valve Mfg.: MKW l BT0/0P 10 - 0(5023 3 3.23) 17
.. HA B 3 Wa)/50 C ;
4 2HY5955E2, Air' Start Sol. - Diesel Generator 2G003, 20 Cyl., Right Bank (Owg.: 40110C/E1)ValveMfg. MKW NA B - 3 Way/S0-C BT0/0P. 10- 0(S02333.23) 17
- 2HYS955F2, Atr Start Sol. Diesel Generator 2G003. 16 Cyl., left Bank (Dwg.: 401100/E 2) Valve Mfg.: MKW NA B 3 Way/SO C BT0/0P 10 0(S023 3 3.23) 17 ;
O
- 2HY5955G2, Air Start 501. Diesel Generator 2G003.- 20 Cyl., lef t Bank l T
.V -(Dwg.: 40110C/E 2) Valve Mfg.: -MKW-NA =B - 3 Way/SO C- BT0/0P 10 0(5023 3 3.23) 17
- 2HYS955H2, Air Start Sol. Diesel Generator 2G003, 16 Cyl,, Right Bank i
WA(Dwg. : 401100/E 1) C ValveBT0/0P.. Mfg.: MKW 10 . .0(50233-3.23) B . 3 Way/50 17 . . ** System!-Diesel Generator System
* -$22420MU135 (11/21352*), Diesel Air Receiver 1338 Air-Inlet '
Check Valve (Dwg.:401100/G3)ValveMfg.: Later C 1:1/2 CK/SA C CVTC/0P - 0(502333.30)
-* S22420Mul46' - (11/2146 Z *), Olesel Air-Ritceiver T-335 Air inlet 1
,. . . Check Valve- ;
(Dwg.: 40110E/H 1) Valve Mfg.: Later
'C 1 1/2 CK/SA C CVTC/0P 0(S023 3 3.30)-
* '522420MU160 (1L1/2160 Z *), Diesel Air Receiver T 336 Ab lalet Check Valve (Dwg.: 40110E/G 3) Valve Mfg.: Later
- C . 1 1/2 CK/SA- C CVTC/0P- 0(5023-3 3.30)
* $22420Mul68- (1 1/2-168 2 *), Diesel Air Receiver T 337 Air-Inlet .
. /. _T Check Valve h (Dwg.: 401100/H 1). Valve Mfg.: Later
.C .I'1/2 CK/SA C CVTC/0P 0(5023 3-3.30)
ATTACHMENT 2 PAGE 22 0F $2
~
a y - -- , - - it g m = p---ww,rg ,, u,*5- m g -, -enwg-- y gy w w p y yy6d% 1
NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S0t3 V 3.5 ! UNITS 2 AND 3 REVISION 7 PAGE $0 0F 706 ! ATTACHMENT 2 TCN _,72 LQ_ , WI_t i i 10/16/91 Intervice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's:HMaintenance.0. Operations.T= Technical) Discussion of Cold Shutdown Intervals. See Next Att. , Valve Test Notes and ; See and- Type Test Valve ; Code XI Size Actuator Norm and Str. Organization Relief , ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
** System: Fire Protection
- 2HV5686, Contet Isolation Valve, Outside Fire Prot. System Water (Dwg.: 40184B/D3)ValveMfg.: WKM .
2 A 4 CA/MO C AT/RR T S023.V 3.13 3&lo
'2 A' 4 GA/MO C BTC/CS 33 0 5023 3 3.31 3&l0 .
2 A, 4 GA/MO C PIT /RR 0 5023 3 3.31 3110 SA230lMUO61 (4 061-C 681), Containment Isolation Valve Fire Protection System Water 3 (Dwg.: 401848/D 4) Valve Mfg.: Anchor / Darling 1 2: AC 4 CK/SA C AT/RR T(5023V3.13) 10 ,
** System: Fuel Stor. Pool & Refueling
*- 2LV0227C. RWST.To Charging-Pump Suction (Dwg.: 401248/A 7) Valve Mfg.: Target Rock 2 B 4 GA/M0- C BT0/CS 11 0(502333.31) S&6 2 B 4- GA/M0 C PIT /RR 0(S02333.31) S&6
* . S21219MUO52-(6 052 C 675), RWFT T006 to Charging Pump Suction Header-
-(Dwg.: 40124B/8 7) Valve Mfg.: Aloyco/Walworth 2 C 6 CK/SA C- CVT0/CS 0(S023-33.31.2) S
- S212!9MU100 (10 100 C 212), Refueling Pool-Outlet Inside Containment (Dwg.: 40122A/G 4) Valve Mfg.: Walworth 2 A 10 GA/M C AT/RR- T(5023 V 3.13) 10 ,
- S21219MU101 (10101 C 212), Refueling Pool Outlet Outside Containinent to Pump 2P014..
(Dwg.: 40122A/G 4) Valve Mfg.: Walworth 2 A- 10 GA/M C AT/RR T(S022 V-3.13) 10
** Systemi Gas Radwaste
* -2HV7258, Containment ' Isolation Waste Gas to Surge Tank
~(Dwg.: 40131A/F 3) Valve Mfg.: WKM 2 -A 3 CA/MO O- AT/RR T S023-V-3.13 3,6&l0 LN O ,/
-2 A A
3 3 GA/MO O O-BTC/0P 31 0 S023 3 3.30 0 5023 3 3.30 3,6&l0 3,6&l0 _2 GA/MO PIT /RR ATTACHMENT 2 PAGE 23 0F S2
NUCLEAR ORGAHlZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 51 0F 208 ATTACHMENT 2 () v ICN 7 - 1 n, L!!llL2 10/16/91 Inservice itsting Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance, 0 . Operations. T Technical) Discussion of Cold Shutdown Intenvals, See Next Att. Valve Test Notes and See and Type Test Valve # Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
- 2HV7259 Containment isolation Safety injection Tank Vent Header (Dwg.: 40131A/F 2) Valve Mfg.: Fisher 2 A 3 GA/A0 0 AT/RR T S023 V 3.13 3&l0 2 A 3 GA/A0 0 BTC/0P 5 0 S023 3 3.30 3&lo 2 A 3 GA/A0 0 FSTC/0P 0 5023 3 3.30 3&l0 2 A 3, GA/A0 0 PIT /RR 0 S023 3 3.30 3&lo
** System: Liquid Radwaste
- 2HV7512, RCDT Pump Discharge from Containuent to Radwaste (Dwg.: 40131A/B 3) Valve Mfg.: WKM 2 A 3 GL/MO C AT/RR T 5023 V-3.13 a,6&lo (c) v' 2
2 A A 3 3 GL/MO GL/MO C C BTC/0P 40 PIT /RR 0 5023 0 5023 3 3.30 3 3.30 3,6&l0 3,6&l0 lTua
- 2HV7513, Containment Isolatten RCS Drain to Radwaste (Dwg.: 40131A/B 2) Valve Mfg.: Fisi.er 2 A 3 GL/A0 C AT/RR T S023 V 3.13 3&l0 2 A 3 GL/A0 C BTC/0P 7 0 S023-3 3.30 3&l0 2 A 3 GL/A0 C FSTC/0P O S023+3 3.30 3&l0 2 A 3 GL/AD C PIT /RR 0(5023 3 3.30) 3&l0
* $2190lMU321 (2 321 C 376), Isolation Valve - Coolant Polishing Demin to Quench Tank (Dwg.: 40lllC/G 6) Valve Mfg.: Kerotest 2 A 2 GL/M C AT/RR T(5023 V 3.13) 10
* $21901MU573 (2 573-C 611), Check Valve Coolant Polishing Demin to Quench Tank
(&*g.: 40111C/G 5) Valve Mfg.: Kerotest 2 AC 2 CK/SA C AT/RR T(S023 V-3.13) 10
** System: Nitrogen Gas
- 2HV5434, Nitrogen to Safety injection Tanks (Dwg.: 40192C/D 6) Valve Mfg.: Fisher 2 A 2 GL/A0 C AT/RR T(S023 V 3.13) 3&l0 g 2 A 2 GL/A0 C BTC/0P 4 0(5023 3 3.30) 3&l0 4
2 A 2 GL/A0 C FSTC/0P 0(5023 3-3.30) 3&l0
- d 2 A 2 GL/A0 C PIT /RR 0(5023-3-3.30) 3&l0 l
l ATTACHMENT 2 PAGE 24 0F 52 l
** t . ,-.
NUCLEAR' ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5
- REVISION 7 PAGE 52 0F 208 UNITS 2 AND 3 .
ATTACHMENT 2 l O V TCN - 7*16 UNIT 1 10/16/91 Inservice Testing Program for Velves ' San Onofre Nuclear Generating Station ; (Test Org'st M. Maintenance. 0 Operations. T Technical) Discussion of Cold Shutdown Intervals, see Next Att. Test Notes and Valve - Type Test Valve See and Relief
+
Code XI- Size Actuator Nors and Str. Organization I As, quests Class Cat (in.) Type Fos. Mode Time (Procedure)
- 2HV5437, Nitrogen Supply to Containment ;
Fisher ' 2(Dwg.: 40192C/F 5) Valve 0- Mfg.: AT/RR T 5023 Y 3.13) 3&lo A 3/4 GL/A0 - 2 A 3/4 GL/A0 'O B1C/0P 2 0( ) 3&lo ' 2 A 3/4 GL/A0 0 0 FSTC/0P 0 ((S02333.30 5023 3 3.30J OLS023 3 3.301 3110 3110 : 2 A 3/4- GL/A0 PIT /RR !
+
- S22418 nun 02 (3/4 002 C 611), Nitrogen Supply to Containment 2(Dwg.: AC 403/4/2C/E
.CK/SA 5) Valve C Mfg.:
AT/RR Kerotest- T(5023 V 3.13) 10
- S22418MU108 (2108 C 627), Nitrogen Supply to Safety injection Tanks (Dwg.: 40lg2C/C 6) Valve Mfg.: -Kerotest dt 2 AC' 2 CK/SA C AT/RR -T(S023-V3.13) 10
** System:l Nuclear Sampling. ,
- 2HV0500. Post LOCA Hydrogen Monitor ,
-(Dwg.: 40172A/C3)ValveMfg.: Target Rock
-A 1- C AT/RR T(5023 V-3.13) 10 2 GA/50
*- 2HV0501.-Post LOCA Hydrogen Monitor ,
(Dwg.: 40172A/D 2) Valve Mfg.: Target Rock 2 A 1 GA/SO C AT/RR .T(5023-V3.13) 10
- 2HV0502, Post LOCA Hydrogen Monitor ;
(Dwg.: 40172A/B 3) Valve Mfg.: Target. Rock A- 1_ C. AT/RR T(5023 V 3.13) 10 2 GA/50
** 2HV0503.--Post LOCA Hydrogen Monitor
-(Dwg.: 40172A/B 2) . Valve Mfg.: Target Rock 2 A GA/SO C AT/RR T(5023-V 3.13) 10
-* 2HV0508 Containment isolation -RCS Hot Leg i
(Dwg.: 40134A/G 7) Valve-Mfg.: WKM , c 2- A 3/4 GL/M0 -C AT/RR- -T(5023-V-3.13) 3,6&l0 , ! .2i A 3/4 .GL/M0 C BTC/0P 3J 0(S023 3 3.30) 3.6&l0 2 A- 3/4 GL/MO C PIT /RR 0(S02333.30) 3,6110 -lf} , L ATTACHMENT 2 PAGE 25 0F 52 i
~ . _ _ . . - _ . , - _ , . . _ . _ , _ . , . _ . . 4 -. . - _ _ . , , , _ _ _ . . _ --r, . _ _ _ , . ,
y- _ - - - - . - - -- - - - - _ NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023.V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 53 0F 208 ATTACHMENT 2 ( TCN 7*10 MIL 2 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: H. Maintenance. 0 = Operations. T = Technical) Discussion of Cold Shutdown Intervals See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
- RCS Hot Leg 2HV0509. Containment Isolation (Dwg.: 40134A/G 5) Valve Mfg.: Fisher 2 A 3/4 GL/A0 C AT/RR T S023 V 3.13 3&l0 2 A 3/4 GL/A0 C BTC/0P 4 0 S023 3 3.30 3&l0 2 A 3/4 'GL/A0 C FSTC/0P O S023 3 3.30 3&l0 2 A 3/4 GL/8 C PIT /RR 0 5023 3 3.30 3&l0
- 2HV0510. Containt,ent isolation Pressurizer Vapor Sample Line (Dwg.: 40134A/E 7, Valve Mfg.: WKM
. 2 A 3/4 GL/eio C AT/RR T S023 V 3.13) 3.6&l0 2 A 3/4 c.' /M0 C BTC/0P 24 0S02333.30) 3,6&l0 2 A 3/4 GL/MO C PIT /RR 0 S023 3 3.30) 3,6&l0 b
- 2HV0511. Containment Isolation Pressurizer Vapor Sample Line (Dwg.: 40134A/E 5) Valve Mfg.: Fisher r 2 A 3/4 GL/A0 C AT/RR T(5023 V 3.13 3&l0 2 A 3/4 GL/A0 C BTC/0P 5 0(5023 3 3.30 3&l0 2 A 3/4 GL/A0 C FSTC/0P O S023 3 3.30 3&l0 2 A 3/4 GL/A0 C PIT /RR 0 5023 3 3.30 3&l0
- 2HV0512, Containment Isolation Pressurizer Surge Line Sample (Dwg.: 40134A/C-7) Valve Mfg.: WKM 2- A 3/4 GL/MO C AT/RR T $023 V 3.13 3.6&l0 2 A 3/4 GL/MO C BTC/0P 31 0 S023 3 3.30 3,6&l0 2 A 3/4 GL/MO C PIT /RR 0 5023 3 3.30 3,6&l0
- 2HV0513, Containment Isolation Pressurizer Surge Line Sample (Dwg.: 40134A/C 6) Valve Mfg.: Fisher 2 A 3/4 GL/A0 C A1/RR T $023 V 3.13 3&l0 2 A 3/4 GL/A0 C. BTC/0P 5 0 5023 3 3.30 3&l0 2 A 3/4 GL/A0 C FSTC/0P 0 S023 3 3.30 3&l0 2 A 3/4 GL/A0 C PIT /RR 0(5023-33.30 3&l0 2HV0514, Isolation Valve - Quench Tank to Waste Gas System (Dwg.: 40lllC/F-3) Valve Mfg.: WKM 2 A 3/4 GL/MO O AT/RR T(S023V3.13) 3,6&l0 2 A 3/4 GL/MO O BTC/0P 31 0(S023-33.30) 3,6&l0
,q 2 A 3/4 GL/MO O PIT /RR 0(S023 3-3.30) 3,6&lo l
V ATTACHMENT 2 PAGE 26 0F 52
i NUCLEAR ORGANIZAT10N: -ENGINEERING PROCEDURE S023.V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 54 Of 208 I ATTACHMENT 2 AJ TCH 7-16 , m1L2 ; 10/16/91 ' Inservice Testthg Program for Valves San Onofre Nuclear Generating Station t (TestOrg's: M Maintenance. 0 Operations. T . Technical) Discussion of Cold Shutdown Intervals, See Next Att. ! Valve Test Notes and - See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief , ClassCat-(in.) Type Pos. Mode Time (Procedure) Requests l 9
- 2HV0515.-! sol, Valve - Quench Tank /RCOT to Waste Gas Sampling System i' Fisher "
2 (Dwg.: A 40lllC/G 3/4 GL/ 2)A0 Valve C Mfg.: AT/RR T S023 V 3.13 3&l0 2! A 3/4' GL/A0- .C BTC/0P-4 0 5023 3 3.30 3&l0 'lTrA 2 A 3/4- GL/A0 - C- FSTC/0P 0 5023 3 3.30 3&lo 2 A 3/4 GL/A0 C PIT /RR 0 5023 3 3.30 3110
* .2HV0516,' Isolation Valve RCDT to' Waste Gas Sampling System i
2(Dwg.: 40111C/G 3) Valve 0 Mfg.: WKM T 5023 V 3.13 3,6&lo - A 3/4 GL/M0 AT/RR 2 A 3/4 GL/M0 0 BTC/0P 25 0 5023 3 3.30 3,6&l0 2- A' 3/4 GL/MO- 0. PIT /RR 0 5023 3 3.30 3,6&l0
* #2 Sample Isolation Valve 2HV0517.RCSHotLe!1veMfg.:
(Dwg.: 40134A/G.7) V WKM 2 ,-A 3/4- GL/MO C- AT/RR- T S023 V 3.13 3,6110 ; 2 A 3/4 GL/M0 C BTC/0P -29 0 5023+3 3.30 3,6&l0-2 A' 2/4 Gt/MO C PIT /RR 0 5023 3 3.30 3.6&l0
- __ 2HV7800, Containment' Airborne Rad Monitor Train _ *A" Isol (Pen 308) .
- Target Rock 2 (-Dwg.:'40170A/E-3)
A 3/4-'GA/SO - 0 .- -AT/RR-Velve Mfg.. T S023 V 3.13 3110 ; 2 A 3/4 GA/50 0 BTC/0P~ l 0 S023 3 3.30 3&l0 ; 2 A 3/4 GA/50- 0- FSTC/0P- -0 S023 3-3.30 .3&l0
- 2 A. 3/4 GA/50 0 PIT /RR 0 5023 3 3.30 3&l0 2HV7801 Containment Airborne Rad-Monttor Train-"A" 1s01 (Pen 30B)
.(Dwg.: 40170A/E 4) Valve Mfg.: Target Rock 2- A 3/4 -GA/SO O- AT/RR T S023 V 3.13 3110
- 2. AL 3/4 GA/SO O. BTC/0P 1 0 5023 3 3.30 3&l0
-2 .A 3/4 GA/50 0 FSTC/0P- 0 5023 3 3.30 3&l0 -
2 A 3/4 GA/SO: 0< PIT /RR 0 S023 3 3.30 3&l0 n . L
- 2HV7802, Containn'ent Airborne Rad Monitor Train "A" Isol (Pen 30A)
L -(Dwg.: 40170A/0 4): Valve Mfg.: Target Rock L 2- A 3/4 GA/SO -0L AT/RR T S023 V 3.13). 3&l0 2 A. 3/4 GA/SO- 0 BTC/0P 1 -0 5023 3 3.30). 3&l0 2 .A 3/4 GA/SO O FSTC/00 0 $023 3 3.30) 3&lo n -2 A 3/4 GA/SO- -0 PIT /RR 0 5023 3 3.30) 3110 l N ATTACHMENT 2 PAGE 27 0F 52 L -
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 55 0F 208 (') Ib v URILt 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M Maintenance. 0 Operations. T Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and lype Test Valve Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
- 2HV7803, Containment Airborne Rad Monitor Train "B" isol (Pen 3A)
(Dwg.: 40170A/D 3) Valve Mfg.: Target Rock 2 A 3/4 GA/50 0 AT/RR T 5023 V 3.13) 3&l0 2 A 3/4 GA/SO O BTC/0P 1 0 5023 3 3.30) 3&l0 2 A 3/4 GA/SO O FSTC/0P 0 5023 3 3.30) 3&l0 2 A 3/4 GA/SO O PIT /RR 0 S023 3 3.30) 3&l0
- 2HV7805, Containment isolation - Airborne Rad Monitor Train *B" (Dwg.: 40170A/C 4) Valve Mfg.: Target Rock 2 A 3/4 GA/SO O AT/RR T 5023 V 3.13 3&lo 2 A 3/4 GA/SO O BTC/0P 1 0 5023 3 3.30 3&l0 2 A 3/4 GA/50 0 FSTC/0P 0 5023 3 3.30 3&l0
;g) 2 A 3/4 GA/50 0 PIT /RR 0 S023 3 3.30 3&l0 v
- 2HV7806, Containment isolation - Airbot..e Rad Monitor Train "B" (Dwg.: 40170A/C 4) Valve Mfg.: Target Rock -
- 2. A 3/4 GA/SO O AT/RR T S023 V-3.13) 3&l0 2 A 3/4 GA/SO O BTC/0P. 1 0 5023 3 3.30 3&l0 2 A 3/4 GA/50 0 FSTC/0P O S023 3 3.30 3&l0 2 A 3/4 GA/SO O PIT /RR 0(5023 3 3.30 3&l0
- 2HV7810. Containment Airborne Rad Monitor Train "B" Isol (Pen 160)
(Dwg.: 40170A/C 3) Valve Mfg.: Target Rock 2- A 3/4 GA/SO O AT/RR v J23-V 3.13) 3&l0 2 A 3/4 GA/50 0 BTC/0P 1 0502333.30) 3&l0 2 A 3/4 GA/SO O FSTC/0P O S023-3 3.30 3&l0 2 A 3/4 GA/50 0 PIT /RR 0 5023 3 3.30 3&l0
- 2HV7811. Containment Airborne Rad Monitor Train "B" Isol (Pen 270)
(Dwg.: 40170A/C-3) Valve Mfg.: Target Rock 2 A 3/4 GA/50 0 AT/RR TS023V5.13) 3 3&l0 2 A 3/4 GA/SO O BTC/0P 1 0 S023 3 3.30) 3&l0 2 A 3/4 GA/SO O FSTC/0P O S023 3-3.30) 3&l0 2 A 3/4 GA/50 0 PIT /RR 0 S023 3 3.30) 3&l0
- 2HV7816, Contmt Isolation - Airborne Rad Monitor Emergency Sample (Dwg.: 40170A/F 3) Valve Mfg.: Target Rock 2 A 3/4 GA/SO O AT/RR T(5023V3.13) 3&l0
,_) 2 A 3/4 GA/SO O BTC/0P 1 0(5023 3 3.30) 3&l0 t
l (V 2 A 3/4 GA/50 0 FSTC/0P 0(5023 3-3.30) 3&l0 2 A 3/4 GA/50 0 PIT /RR 0(S023 3 3.30) 3&l0 ATTACHMENT 2 PAGE 28 0F 52
d l i I. . l 1 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE- 5023~'3.5 REVISION 7 PAGE j6 0F 200 i UNITS 2 AND 3 Q ATTACHMEN1 2 i 3 TCN T-18 UNIT
- l 4
10/16/91 Inservice Testing Program for Valves -
- San Onofre Nuclear Generating Station (Test Org's
- M Maintenance. 0 Operations. T . Technical) q Discussion of Cold Shutdown Intervals, see Next Att.
Valve. Test Notes and t 1 Type fest Valve i 9 See and Code XI Site Actuator Norm and Str. Organtration Relief i n Requests j ClassCat(in.) Type Pos, Mode Time (Procedure) d 0 -** System: Nuclear Service Water ;
- Nuclear Service Water 2HV7911. Containment' isolation i Fisher 2(Dwg.t.401408/F5)ValveMfg.:
A 3- GA/A0 0- AT/RR T 5023.V.3.13 3610 4 2 A 3 GA/A0 0 OTC/0P 7 - 0 S023 3 3.30 3110 .
'2 A 3 GA/A0 0. FSTC/0P 0 5023 3 3.30 3&lo - '
.2 A 3 GA/A0 0_ PIT /RR 0 5023 3 3.30 3310 i
* $21415MU236- (3 236 C 675), Containment 1 solation Check Valve - i Nuclear Service Water Aloyco/Walworth 2(Dwg.:
AC 40140B/G 3- CK/SA
- 5) Valve .C Mfg.AT/RR -T(5023 Y 3.13) 10 i
** Systems Reactor Coolant- ;
- 2HV0296A Reactor Head Vent
+
't(Dwg.: .B 40lllC/F 1
- 6) ValveCMfg.:BTC/CS GL/50 Target5 Rock 0(5023 3 3.48 i 2 - B' 1 GL/50 C- BT0/CS S- 0 5023 3 3.48 2 BJ ! ' GL/501 C FSTC/CS. 'O $023 3 3.48 2 B 1 GL/50 C P!T/RR 0 5023 3 3.48
-* 2HV02968, Reactor Head Vent
'(Dwg.: 40lllC/F.6) Valve Mfg.: Target Rock-2 B 1 GL/50- C BTC/CS 5 0 5023 3 3.48 2 --
B -l' GL/SO C BT0/CS 5 0 5023 3 3 48 , 2 B 1 GL/50 C .FSTC/CS 0 5023 3 3.48 2 B l' GL/50 _C PIT /RR 0 5023 3 3.48
- 2HV0297A. Pressurizer Vent Valve 1
-(Dwg.: 401110/D6)ValveMfg.: Target Rock
- 2. B- 1 GL/50; C BTC/CS 5 0 5023 3 3.48 2- B - ' l' GL/50- C BT0/CS. 5 0 5023 3 3.48
-2 B; I GL/50 C FSTC/CS -0 S023 3 3.48 .
-2 B- 1- GL/50' C PIT /RR 0 5023-3 3.48)
O
~
ATTACHMENT 2 PAGE 29 0F $2 i d ' i' t -< w--,-+N-- e ~r v -n vw rN .v w e . - w ' v w--m ' < A-e--w w- ~ +,w vw--w ----~,=~w-~~- . - w e, e .-ev n -e - -r - v e w- -'-e. w,-=-~m,-~~~~*+~~sv<~~wa < e ~ ~ " -
NUCLEAR ORGANIZATION ENGIN(ERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 57 0F 208 ; ATTACHMENT ,2 i l c TCN 7 10 UNIT 2 10/16/91 Inservice Testing Program for Valves i San Onofre Nuclear Generating Station (Test Org's: M. Maintenance. 0 = Operations T = Technical) ' Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size- Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Frocedure) Requests t 2HV02978, Pressurizer Vent Valve (Dwg.: 40lllC/E 6) Valve Mfg.: Target Rock , 2 B 1 GL/50 C BTC/CS 5 0S023&33.48)
-2 B 1 GL/50 C BT0/CS 5 0 S023 3 3.481 2 8 1 GL/50 C FSTC/CS 0 5023 3 3.48) 2 B 1 GL/$0- - C PIT /RR 0(5023 3 3.48)
- 2HV0298. Vent to Contmt from Reactor Head / Pressurizer (Dwg.: 40111C/t 3) Valve Mfg.: Target Rock 2 B -! .L/50 C BTC/CS 5 0(S023 3 3.48 2 B 1 -GL/50 C' BT0/CS 5 0 S023-3 3.48
~7 2 B 1 GL/50 C FSTC/CS 0 S023 3 3.48 2 B 1 GL/SO C PIT /RR 0 S023 3-3.48
(
- 2HV0299, Quench Tank Inlet from Reactor Head / Pressurizer Vent L (Dwg.: 40lllC/E 4) Valve Mfg.: Target Rock 2 B 1 GL/SO. C BTC/CS 5 0(5023 3 3.48 2 B 1 GL/SO C BT0/CS 5- 0 S023 3-3.48 2 -B 1- -GL/50 C FSTC/CS 0 S023-3 3.48 2 B- -GL/50 _C PIT /RR -- - 0 S023-3 3.48)-
- 2HV9201, Regenerative Heat Exchanger E063 to Auxiliary Spray (Dwg.: 40123A/C-6) Valve Mfg.: WKM 1 B 2 -GA/MO- C BTC/CS 17 0(S0233-3.31) S&6 1- B 2 GA/MO C B10/CS 17 5&6 0(502335.31l 0(5023-3-3.Ji, 5&6
-1 B~ 2_ GA/MO C_ _ PIT /RR
* - 2HV9202, Regenerative Heat Exchanger E063 to RCS Loop 2A l (Dwg.: 40123A/E 6) Valve Mfg.: WKM 1 B -2~ GA/MO O BTC/CS 23: 0(5023 3-3.31) _6-1 ' B -- 2 GA/MO O BT0/CS 0(5023 3-3.31) 6
,1 B- 2 GA/MO 0 PIT /RR - 0(S023 23 3 3.31) 6
-* 2PV9203, Regenerative Heat Exchanger E063 to RCS Loop 1A -
L (Dwg.: 40123A/E 6) Valve Mfg.: WKM
.1 B 2 GA/MO 0 BTC/CS 20 0(5023 3 3.31) 6 L
1 B 2- GA/MO O BT0/CS_ 20 0(S023-3-3.31) 6 1 -B 2- GA/MO O PIT /RR 0(S023-3 3.31) 6 V ATTACHMENT 2 PAGE 30 0F 52 i y i..*,- m.- -- ,,s. . . .,. . , , . - . . , . - ,
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 REVISION 7 PAGE 5B 0F 208 UNITS 2 AND 3 ATTACHMENT 2 I ) TCN _7 - 1,,(L U WIL2 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (lestOrg's: M Maintenance, 0 Operations T = Technical) Discussion of Cold shutdown Intervals, see Next Att. Valve Test Notes and and Type Test Yalve See Code X1 Size Actuator Norm and Str. Organization Relief Time (Procedure) Requests Class Cat (in.) Type Pos. Mode
- 2HV9204, RCS Loop 2B Letdown to Regenerative Heat Exchanger Fisher 1(Dwg.: B 40123A/F 2 GA/A0
- 6) Valve 0 Mfg.:
BTC/CS 4 0 S023 3 3.31 5 1 B 2 GA/A0 0 FSTC/CS 0 5023 3 3.31 5 1 B 2 GA/A0 0 PIT /RR 0 5023 3 3.31 5
- 2HV9217 Reactor Coolant System Bleed Off to Volume Control Tank
' (Dwg.: 40124A/G 3) Valve Mfg.: WKM 3,5,6&l0 A 3/4 GL/MO O AT/RR T S023 V-3.13)
O BTC/CS 15 0 5023 3 3.31) 3,5,6&lo 2 A 3/4 GL/MO 3,5,6&l0 2 A 3/4 GL/MO O PIT /RR 0 S023 3 3.31)
)
2HV9218. RCS Bleed Off to VCT Isolation V '"e Inside Containment
(Dwg.: 40124A/F 3) Valve Mfg.: Fisher 2 A 3/4 GL/A0 0 AT/RR T(S023V-3.13) 3,5&l0 2 A 3/4 GL/A0 0 BTC/CS 5 0(5023 3 3.31) 3,5&l0 2 A 3/4 GL/A0 0 FSTC/CS 0(502333.31) 3,S&l0 2 A 3/4 Gl./A0 0 PIT /RR 0(5023 3 3.31) 3,5&l0
- 2PSV0200, Pressurizer Safety Valve (Dwg.: 40lllB/G 7) Valve Mfg.: Dresser 1 C 6 SV/SA C RVT/RR M(S023-1 2.1) 2
- 2PSV0201 Pressurizer Safety Valve (Dwg.: 40lllB/G 5) Valve Mfg.: Dresser 1 C 6 SV/SA C RVT/RR M(5023 1-2.1) 2 2TV0221. Letdown Isolation Valve (Owg.: 40123A/F-6) Valve Mfg.: ITT 1 B 2 GL/A0 0 BTC/CS 4 0(5023 3-3 a1 5 1 B 2 GL/A0 0 FSTC/CS 0 5023-3-3.31 5 9
1 B 2 GL/A0 0 PIT /RR 0 5023-3-3.31 5
- S2120lMU019 (2 019 A 554), Auxiliary Spray Check Valve (Dwg.: 40123A/C-7) Valve Mfg.: Kerotest 1 C 2 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5 g
- 52120lMUO20 (2 020 A-554), Charging Line Check Valve to RCS Loop 2A (Dwg.: 40123A/E 7) Valve Mft.: Kerotest (d i 1 C 2 CK/SA C CV10/CS 0(5023-3 3.31.2)
ATTACHMENT 2 PAGE 31 0F 52
NUCLEAll ORGANIZATION ENGINEERING PROCEDURE $023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 59 0F 208 ATTACHMENT 2 (~) TCN 7-16 \_k 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M Mc'-+enance. 0 = Operations T = Technical) Discussion on d Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
* $2120lMUO21 (2 021 A 554), Charging 'ine Check Valve to RCS Loop 1A (Dwg.: 40123A/E-7) Valve Mfg.: Kerotest 1 C 2 CK/SA C CVT0/CS O(5023 3 3.31.2)
S2120lMU129 (2 129 A 554), Auxiliary Spray to RCS from Charging Pumps (Dwg.: 40123A/B 3) Valve Mfg.: Kerotest 1 AC 2 CK/SA C AT/RR T(5023 V 3.13) 10 1 AC 2 CK/SA C CVT0/CS 0(5023 3 3.31.2) 10
- S2120lMV200 (14 200 C 645), Pump 2P016 Suction Check Vaive (Dwg.: 40ll2B/F 6)-Valve Mfg.: Anchor / Darling 2 C 14 CK/SA C CVTC/CS 0(5023-33.31.2)
(\)).
^
2 C 14 CK/SA C CVT0/CS O(5023-33.31.2)
~
- S2120lMU202 (14 202-C-645), h.mp 2P015 Suction Check Valve (Dwg.: 40112B/G 5) Valve Mfg.: Anchor / Darling 2 C 14 CK/SA C CVTC/CS 0(502333.31.2) 2 C 14 CK/SA C CVT0/CS O(502333.31.2)
** System: Resp. & Service Air System 2HV5338 Containment Isolation Valve - Instre- at Air (Dwg.: 40191G/G-6) Valve Mfg.: Fisher 2 A 1 1/2 GL/A0 0 AT/RR * 'su2! .) 3&l0 2 A 1-1/2 GL/A0 0 BTC/CS 2 0 502.5 < 4) 3&l0 2 A 1 1/2 GL/A0 0 FSTC/CS 0 5023-3 3.31) 3110 2 A 1-1/2 GL/A0 0 PIT /RR 0 5023-3 3.31) 3&l0
- S22417MU016 (1-1/2-016 C 617), Instrument Air Contmt isol Check -
Inside Containment (Dwg.: 40191G/G 6) Valve Mfg.: Kerotest 2 AC 1 1/2 CK/SA C AT/RR T(5023 V-3.13) 10 S22423MU017 (2 017 C-627), Containment Isolation Valve - Service Air (Dwg.: 40191E/C-5) Valve Mfg.: Kerntest 2 AC 2 CK/SA C AT/RR T(S023 V-3.13) 10
- S22423MUO55 (2-055-C 387), Containment isolation Valve - Service Air p)
\ Z (Dwg.: 4019'~/C 6) Valve Mfg.: Vogt A 2 GL/M C AT/.1R T(S023 V-3.13) 10 ATTACHMENT 2 PAGE 32 0F 52
i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 - UNITS 2 AND 3 REYlSION 7 PAGE 60 0F 20B MTACHNENT 2 TCN 7-16 UNIT 2 10/16/91 - Inservice' Testing Program for Valvas " San Onofre Nuclear Generating Station (TestOrg's:M-Maintenance.0= Operations.T=' Technical) Discussion of Cold Shutdown Intervals. See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests System: Safetyinjection , 2HV0396. Flow Control Valve LPSI Pumos tu Shutdown Cooling System (Dwg.: 40ll2B/C 2) Valve Mfg.: Borg Warner , 2 B -10 GL/MO C B10/CS 80 0($023 3 3.31) 6 2 B 10 .GL/MO C PIT /RR 0(502333.31) 6
- 2HVB152. Isolation Valve SDCS Heat Exchanger E004-Inlet (Dwg.: 40ll28/F 2) Valve Mfg.: Walworth 1 2 B 12 GA/MO C BTC/CS 100 0 5023 3 3.31 6 2 B 12L GA/MO C BT0/CS 100 0 5023 3 3.31 6 2 B 12 GA/MO~ C- PIT /RR 0 5023 3 3.31 6 2hV8153. Isolation Valve SDCS Heat Exchanger E003 Inlet (Dwg.: 40ll28/G 2) Valve Mfg.: Walworth 2 8 12 GA/MO C BTC/CS 100 0 5023 3 3.31 6 2 B 12 GA/MO C B10/CS 100 0 S025-3 3.31 6 2 8 12- GA/MO C PIT /RR 0 $023 3 3.31 6
' 2HV8160.- Flow Control- Valve SDCS Heat- Exchanger Bypass (Dwg.: 40ll28/C-3) Valve Mfg.: Fisher 2 B- 10 .GL/MO- 0 BTC/CS 40 0(3023 3 3.31) 6 2 B 10 GL/MO O PIT /RR - 0(502333.31) 6
* ; 2HV8161. Block Valve SDCS Heat Exchanger Bypass _ to LPSI (Dwg.: 40ll28/C 3) Valve Mfg;: Walworth 2 - B - - 14 . GA/MO 0 BTC/CS 105 0(S023-33.31) 6 B 14 GA/MO- 0 PIT /RR 0(5023 3 3.31) 6 ,
- 2HV8162. LPSI Pump 2 Pols Miniflow Block Valve !
(Dwg.: 401128/H 2) Valve Mfg.: Westinghouse. Inc. 2' B 2 GA/MO -0 BTC/CS 12 0 5023 3 3.31 6
- 2 - BL ,2 GA/MO O' PIT /RR 0 5023:3 3.31 6-2HV8163. LPSI Pump 2P016 Minifiow Block.Vilve .
(Dwg.: 40ll2B/E3)-ValveMfg.: Westinghouse. Inc. 2 B- 2 GA/MO .0 BTC/CS 12 0(5023 3 3.31) 6 2- -B 2 GA/MO .0 PIT /RR 0(S023-3-3.31) 6 - O ATTACHMENT 2 PAGE 33 0F 52 p % ---mer <-sus,re-tr wu-deM+-p-- gd' urge'e+ '-P-- wa y + _ Wt % q w -M- Y-w '9+4
- D'M' ' e F 't
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V.3.5 UNITS 2 AND 3 REVISION 7 PAGE 61 0F 20B
, ATTACHMENT 2
( TCN 7 - LQ.. utdL2-10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M. Maintenance. 0 Operations, T = Technical) Discussion of Cold Shutdown Intervals, see Next Att. Valve Test Notes and , See and Type Test Valve - Code XI Size Actuator Norm and Str. Organization Relief ' ClastCat(in.) Type Pos. Mode lime (Procedure) Requests
*- 2HV9302, Control Valve Contmt Emergency Sump to Spray. Pump 2P013 (Dwg.: 40ll2A/B 6) Valve Mfg.: Fisher 316
'2 B 24 BTF/MO C BT0/0P 39.5 0(5023 3 3.30)
*2 8 24 BTF/MO C PIT /RR 0(502333.30) 3&6 ,
- 2HV9303. Control Valve - Contmt Emergency Sump to Spray Pump 2P012 (Dwg.: 40112A/B6)ValveMfg.: Fisher 2 8 24 BTF/MO C BT0/0P 39.5 0(5023 3 3.30) 316 2 B 24 BTF/MO C PIT /RR 0(502333.30) 3&fs
- 2HV9304, Control Valve - Containment Emergency Sump Outlet (Dwg.: 40ll2A/B3)ValveMfg.: Fisher '
2 8 24 BTF/MO 0 BT0/0P 39.5 0 3023 3 3.30 6 (d-- 2- B 24 BTF/MO O PIT /RR 0 S023 3 3.30 6
- 2HV9305. Control Valve - Containment Emergency Sump Outlet
-(Dwg.: 40ll2A/B 31 Valve Mfg.: Fishee
'2 B 24 - BTF/MO O B10/0P 39.5 Of5023 3 3.30) 6 2 B - 24 BTF/MO O PIT /RR OfS023 3 3.30) 6
- 2HV9306, Isolation Valve - 51 Recirculation to RWST 1005 -
(Dwg.: 40114D/8 3) Valve Mfg.: WKM 2 B 4- -GA/MO, O DTC/0P 30 0 5023 3 3.30 3&6 2 B 4 GA/MO 0- PIT /RR 0 S023 3-3.30 3&6
- 2HV9307, Isolation Valve - SI Recirculation to RWST T005 (Dwg.: 401140/B 4) Valve Mfg.: WKM 2 0-4 .GA/MO O BTC/0P 30 0(5023 3 3.30) 3&6 2L .B 4 GA/MO O PIT /RR 0(S023 3 3.30) 3&6
- 2HV9322, Control-Valve - LPSI Header to RCS Loop 1A a . (Dwg.: 40ll20/G 4) Valve Mfg.: Target Rock- :
' 2, B 8 GL/MO C BT0/0F 16 0 5023-3 3.30 3&6-2- B_ 8 GL/MO. C PIT /RR 0 S023 3 3.30 3&6
*/-2HV9323, Control Valve HPSI Header #2 to RCS Loop 1A (Dwg.: 40112C/D-4) Valve Mfg.: Target Rock 2 B' 2 GL/M0 C BT0/0P 15 0(5023 3 3.30) 3&6
] 2 B 2 GL/MO C PIT /RR 0(S023 3 3.30) 3&6 ATTACHMENT 2 PAGE 34 0F S2 M w'e e - = m r~ n +- erw,--w--e-r,e-s: -m ,e- aren -n---rr---e-s" = ~ - = - --
y _U o Ji I NUCLEAR ORGANIZATION j . ENGINEERING PROCEDURE 3023 V<3.5 , UNITS 2 AND 3 i REVISION '/ PACE 62 t$ 20B ! ATTACHMENT 2 , TCN ,,_t ,1f., MU' I ;
, 10/16/91 flnserviceTestitg>ProgramforValves San'Onofre Nuclear Generating Station '
(Test.Org's:MMaintenance.0= Operations.T=Techntcal) r Discussion of Cold Shutdown ~1ntervbis. See Next Ah. 1, j Velve . T6st Notes and ; Sec and Type Test , Valve ' Code XI Size Actuator Norm and, Str. Organization MeWef Class. Cat (in.) Type Pos. Mode fina .(Proced:tre) Requests
- 2HV9324. Contrcl Valve - HPSI Header #1 to RCS Loop 1A (Dwg.: 40112C/0 5) hi m Nfg.: Target Rock 2 B J2- r.L/MO C BYO/SP 15 ' ot5013 3 3.30) 316 -
2,-B'2 Gl./MO C PIT /RA 0($02333.30) 'J46 ' I
* .2HVg325, Cutrol Valve LPSI Header to RCS l.oop 1B '
I- (Dwg.: 4011RD/l 4) Valve Mfg.: Target Rock- . 2 B 6.t' GL/MO ' C Bt0/0P '16 0($023-3 3.30) 316 ' 2 0 C TIT /RR. 0(5023 3-3.30) 316 6\ ; i ,.GL/W
. s
'4 2HV9326. Control Valve'. HPSI 11eader $2 to RCS tcop 18-
' . (Cwg :40ll2C/C 4) Valve Mfg. ' Target Rcck
, ..(,,.T - y2 B 2 ,.,GL/h0 C' B10/0P'15 Of$023-3.3.30)t 3&O i
,- Q
;2., B 2 -GL/MO- 0' PIT /RR 0(50/343.30) 3&6 i 31
'~ i
*1' 2HV9321. I,0nthol '.'alve
~
Y HPT,I Hee 6ers H to RCS Loop 1B '
. (Dwg :J40)12C/B 5) Vnive Mfn.v Target kock 2 Bs A1 -GL/MO:
C ' BT0/0F 15' 0(5023 3 3.30) 3&S-2s t- B. 2l,;GLMO C PIT /RR, , 0($023-3-3.30) 3% , W [(Dwg.:. 40ll20/E-4)- Valn Mfg.:: Target Ack2'iV9328. C(ntrol Valve . LPSI Heade 1 2 'B ,8' . GL/MO ~ lC BT0/0P 16' 0(S023 3 3.30) 3&$ q :i. 2 .B 8- 11/MO. ;C PI f/RR ' 'i 0(5023 3 3.30): .3&6 u g 2HU329; Control Valve. HPSI Aaad v #2 to RCS Loop 2A o..- Dw?.: 401120/B 4) Valvt Mfg.i Tt.*get Pock i,-2.
- 2(1 ~B1 2- i GL/H0- CL~ BT0/0P 115 0(S023.7-3.30) i-3&6 B .2 GL/M0' C PIT /RR. 0(5023-33.30)- 3&6
- 2HV9320,1 Control; Valve . hPSI Hecdor #1 to RCS Loop 2A
;y ' '(Dwg.:- 40ll20/A C) Valve Mfg.: Tarpt Rock.
2~ B -2; GL/MO C BT0/0P 15 0(S023 3-3.30) 3&6
-2 B -2 sGL/MO C^ FIT /RR 0(5023-3-3.30) 3&6 L
- 0 2HV9331,-- Control' Valve .- LPSI Header to RCS Loc;i 2B
'(Dwg.:'40ll2D/H 4) Valve Mfg.: Target Rock 2 B 8 GL/MO .C ' BT0/0P -16 0(5023 3 3.30) 3&6 2 .B- 8 GL/MO C -PIT /RR 0(S0233-3.31) 3&6 ,
ATTACHMENT 2 PAGE 35 0F S2 l o* . _
NUCLEAR ORGAN!2ATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 63 0F 208 ATTACHMENT 2 TCN _ L _1E_ un u 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M. Maintenance. 0 Operations T - Technical) Discussion of Cold Shutoown Intervals, See Next Att. 1 1 Valve Test Nc.es and See and- Type Test Valve a Code X1 Stre Aett,ator llorm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Titne (Procedure) Requests
- 2'!V4332, Control Valve hPSI Header #2 to RCS Leop 2B (Dwg.: 40112C/F4)ValveMfg.: Target Ror.k 2 B 2 GL/M0 C B10/0P 15 0(5023 3 3.30) 3&6 2 B 2 GL/MO C PIT /RR 0(5023 343.30) 3&6
'
- 2HV9333, Control' Valve HPS! Header #1 to RCS Loor 2B (Dwg.: 40ll2C/F 5) Valve Mfg.: largot Rock 2 B 2 GL/MO C BT0/0P 15 0(5023 3 3.30) 3&6 2 B 2 GL/MO C PIT /RR= 0(50L3 3+3.30) 3&6
- 2HV9334 Containment isolatitn - S1 Ta ik Dratr Header to RFWT 2T005 (Dwg.: 40ll4D/F 7) Valve Mfg.: WKM
,) 2 A 2 C AT/RR T5023V3.13) .)&l0 (V 2 A 2 GL/MO GL/MO C BTC/0P 13 0 5023 3 3.30) 3&l0 3&l0 2 A 2 GL/MO C PIT /RR 0 5023-3-3.30)
- 2HV9336, Isolation Valve. SDCS wo LPSI Pump Suction (Dwg.: 401120/C 7) Valvt N. : WKM 2 B 16 GA/MO OC BTC/0P 80 0 5023 3 3.30) f.
2 B 16 - GA/MO OC BT0/0P 80 0 5023 3 3.30) 6 2 B 16 GA/MO OC PIT /RR 0 5023 3 3.30) 6
- 2HV9337, Isolation Valve - SDCS to LPSI Pump Suction (Dwg.: 40ll2D/C 4) Valve Mfg.: WKM 1 A 16 GA/M0 OC AT/RR 0 5023 3-3.31.1) 5&6 1 A 16 GA/MO OC BTC/CS 103 0 5023-3 3.31) S&6
.1 A 16 GA/MO OC BT0/CS 103 0 S023 3 3.31) 5&6 1 A 16 GA/MO OC PIT /RR 0(5023-3-3.31) S&6
- 2HV9339, Isolation Valve. SDCS from RCS Loop 2 (Dwg.: 40112D/C-2) Valve Mfg.: WKM 1 A 16 GA/MO OC AT/RR 0(5023 3-3.31 1) 5&6 1 A 16 GA/MO OC BTC/CS 103 0 S023 3 3.31 5&6 l 1 A 16 GA/MO OC BT0/CS 103 0 S023-3 3.31 5&6 l 1 A .16 GA/MO OC PIT /RR 0 5023 3 3.31 S&6
- 2HV9340, Safety Injection Tank T008 Outlet Valve to RCS Loop 1A (Dwg.: 40ll3A/C-6) Valve Mfg.: WKM 12 O BT0/CS 35 0(5023 3-3.31) 5&6 I_)
C 1 1 B B- 12 GA/MO GA/MO O PIT /RR 0(5023 3-3.31) 5&6 AT1ACHMENT 2 PAGE 36 0F 52
1 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023.V 3.5 1 UNITS 2 AND 3 REVISION 7 PAGE 64 0F 208 ATTACHMENT 2 ' TCN 7-10_ LEIT .2 10/16/91 Inservice Testing Program for Valves i.a Onofre Nuclear Generating Station p (TestOrg's: M-Maintenance. 0 = Operations. T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and Se a, and Type Test Valvt ' Code :X1' Sire Actuator Norm and Str. Organization Re:11d Class Cat (in.) 'ype Pos, Mode Time (Procedure) Re%nsts T
- 2HV9345, Safety injection Tank T008 Vent Valve 1
i 2 (Dwg. B 40ll3A/G 1 %l/6)$0 Valve C Mfg.: Target BT0/CS 2 Rock3 3.31 0($023 5. t
? B 1 Gl/SO - C- FSTC/CS .0(502333.31 5 B- -C- PIT /RR 0(S023-3 3.31 5
! 1 GL/50 ,
i
* '2HV9347, Safety injection Recirc Return to RWST T005 Isolatten V 19e (INg.: 40114D/0.3) Valve Mfg.: WKM 2 'B: 4 fiA/MO O BTC/0P 32 0(5023 3 3.30) , 32 ,
2 b 4 -GA/MO O PIT /RR 0(502333.30) '4 6 ,
- _ 2HV9348, Safety Injection Recirc Return to RWST T005 1sn13t'.on V11ve (Dwg.: 40ll4D/D 4) Valve Mfg.: WKM .
2 8 4 GA/MO 0 BTC/0P 32 0(S023 3 3.30) 386
- 2. B 4 GA/M0 l0- PIT /RR 0(502333.30l 3&6
-* 2HV9350, Safety injection Tank 1009 Outlet Valve to _RCE Loop IB (Dwg.: 40ll3A/D 2).V4;ve Mfg.: WKM 1 8 12 -GA/MO. O BT0/CS 32 0(5023 3 3.31) 5t 3 1 B 12- GA/MO O PIT /RR 0(502333.311 SF6 , j
- 2HV9355. Safety injection Tank T007 Vent Valvu 'i' 2(Dwg.: -D 40ll3A/G 1 GL/50
- 2) ValveC Mfg.: Target BT0/CS 2 Rock0 S023 3 3.31) 5 2 8 1 =GL/SO C FSTC/CS 0 S025 3-3.31) 5
'2 B 1 GL/50 C PIT /RR 0 S023-3 3.31) 5
- 2HV9360 Safety injection Tank T009 Outlet Valve to R';*i Loop 2A '
(Dwg.: 40ll3B/C 6) Valve Mfg.: WKM 1 B 12 GA/M0 0 B10/C5 32 0(5023 3 J.31) S&6 . 1 B- 12 GA/MO O PIT /RF G(1023-33.31) 5L6
- 2HV9365, Safety Injection Tank T009 Vent Valvo (Dwg.:40ll3B/G6)ValveMfg.: Ttiget Rock .
2 B 1- GL/50 C, BYO/CS 2 0 5023 3 3.31 5 2 8 'l. GL/50 C FSTC/CS 0 5023 3 3.31 5 ' 2- B- 1. - GL/50 C PIT /RR 0 S023 3 3.31 5 ,l\ ATTACHA2NT 2 PAGE 37 0F 52 x ' V ! ).
,- .w, a. - ~ . , . - - , .-,.. _ , _
1 ( NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023 V 3.S UNITS 2 AND 3 REVISION 7 PAGE 65 0F 208 ATTArHMENT 2 TCN ,,_7 3 u
<(s .
1
' URLT_t 10/16/91 hservice Tosting Program for Valves
+ San Onofrt Huclear Generating Station (Test Org's: H Maintenance. 0 Operations. T = Technical)
Discussion ci Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- 2HV9370, Safety injection Tank T010 Outlet Valve to RCS 1.oop 2B (Dwg.: 40ll3B/D 2) Valve Hfg.: WKM 1 B 12 GA/MO O BT0/CS 35 0(502333.31) S&G 1 B 12 GA/MO O PIT /RR 0(5023 3 3.31) 566
*- 2HV3375 Safety injection Tank T009 Vent Yelve (Dwg.: 40ll3B/G-2) Valve Mfg.: Target Rock 1 B 1 GL/SO C BT0/CS 2 0 5023-3 3.31) 5 1 B 1 GL/SO C FSTC/CS 0 5023 3 3.31) 5
) B 1 EL/50 C PIT /RR 0 5023 3 3.31) 5
- 2HV9377. SDCS Bypass to LPSI Suction Isolstion Valve
( (Dwg.: 401120/B 4) Valve Mfg.: WKM
. (]s. 1 A 10 GA/MO OC AT/RR 0(S023 3 3.31.1) 5&6 1 A 10 GA/MO OC BTC/CS 240 0 5023-3 3.31) 5&6 1 A 10 GA/MO OC BT0/CS 240 0 S023 3-3.31) 5fi6 1 A 10 OA/MO OC PIT /RR 0 S023-3 3.31) $&6
- 2HV9378, SOCS Bypass to LPS! Suction Isolation Valve (Dwg.: 401120/D 3) Valve Mfg.: WKM
. 1 A 10 GA/MO OC AT/RR 0(50233-3.31.1) 5&G 1 A 10 GA/MO OC BTC/CS 240 0(5023 3 3.31 546 1 A 10 GA/M0 OC BT0/CS 240 0 S023-3 3.31 S&6 1 A 10 GA/MO OC PIT /RR 0 5023-3-3.31 5&6
- 2HV9379, SDCS Bypass to LPSI Suction Isolation Valve Seal (Dwg.: 40ll2D/B 7) Valve Mfg.: WKM 2 B 12 GA/MO OC BTC/0P 14 0 $023-3 3.30) 6
- 2 B 12 GA/MO OC BT0/0P 14 0 S023-3-3.30 6
- 2 8 12 GA/MO OC PIT /RR 0 $023 3-3.30 6
- 2HV9420, Control Valve HPSI Header #1 to RCS Loop 2 Hot leg (Dwg.: 40ll2C/G 3) Valve Mfg.: Target Rock 2 A 3 GL/MO C AT/RR T S023 V-3.13) 6&l0 2 A 3 GL/MO C 6T0/C5 11 050233-3.31) 6&l0 2 A 3 GL/MO C P!T/RR 0 S023 3 3.31; 6&lo 3
(v ATTACHMENT 2 PAGE 3B 0F 52
, t NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 t UN!75 2 AND 3 REVISION 7 PAGE 66 Of 206 :
ATTACHHENT 2 _( TCH 7-10_ UNIL2 l 10/16/91 inservice Testing Program for Velves San Onofre Nuclear Generating Station , (TastOrg%:MMaintenance.0= Operations.T=Technicai) Discussion of Cold Shutdown Intervals, See Next Att. l Valve Test Notes and See and Type Test Valve
, Code XI Size Actuator Norm and Str. Organization Relief :
ClassCat(in.) Type Pos. Mode Time (Procedure) Requests 2HYS434. Control Valve HPSI Header #2 to RCS Loop 1 Hot Leg ' (Dwg.2 40112C/E 3) Valve Mfg.: Target Rock 2 A 3 GL/MO C- AT/RR T $023 V 3.13 6&l0 2 A 3 GL/M0 .C BT0/CS 11 0 5023 3 3.31 6&l0 2 A - '3 GL/MO C Pll/RR 0 5023 3 3.31 6110
~* 2PSV9349, Shutdown Cooling System Relief Valve From RCS Loop No. 2 (Dwg.: 40ll20/C 5) Valve Mfg.: Crosby .
2 C 8 RV/SA C RVT/RR. M(5023 1 2.34) 15
- S21204MU001 (24 001 C 724), RW Tank 2T005 to Spray Pump 2P012 Suction Header (Dwg.: 40ll2A/D 8) Valve Mfg.: TRW/ Mission
/7) 2 C 24 SDCK/SA C CVP0/0P T S023 V 3.5.4) 1&l8 VRR 02 1&l8 VRR 02 2 C. 24 SDCK/SA C CVTC/RR M S023 1-6.20) 2 C 24 SDCK/SA C CVT0/RR M S023 1 6.20) 1&l8 VRR 02
- i
$21204MU002 (24 002-C-724), RW Tank 2T005 to Spray Pump 2P013 Suction Header (Dwg.: 40ll2A/D 7) Valve Mfg.: TRW/Hission 2, C 24 - SDCK/SA C- CVP0/0P T S023 V 3.5.4) 1&l8 VRR 02 2 C 24 SDCK/SA C CVTC/RR H S023 1-6.20 1&l8 VRR 02 ,
2 C 24 . SDCK/SA C. CVT0/RR M S023 1-6.20 1&l8 VRR 02 (24 003 C 724), Outlet Check Valve
- S21204MU003 Containment Emergency Sump (Dwg.: 40ll2A/A 6) Valve Mfg.: TRW/ Mission- ,
2 C 24 SDCK/SA C CVP0/RR T(Later) . 1,5&l8 VRR 03 2 C 24 SDCK/SA C CVT0/RR M(5023 1 6.20) 1,5&l8 VRR 03 S21204MU004 (24-004 C 724), Outlet Check Valve Containment Emergency Sump (Dwg.:40ll2A/B6)ValveMfg.: TRW/ Mission 2 C 24 SDCK/SA C CVP0/RR T(Later) 1,5&l8 VRR 03 i C 24 SDCK/SA C CVT0/RR M(5023 I 6.20) 1,5&l8 VRR 03 O q, ~ ATTACHMENT 2 PAGE 39 0F 52
- ,mu-,....-.--,1 5,u.-,-- ew-i. . . . . - , ,.n- -
---%--.- .e. ,, ,-n.. ,wm.-.-..,. .,, -- ,,, m. - - ,-
NUCLEAR ORGANIZAT!DN ENi31NEERING PROCEDURE 5023 V 3.5 REVISION 7 PAGE 67 Of 208 i UNITS 2 AND 3 ATTACHMENT 2 l
-) TCl4 7-in t an_2 1 i
10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station , (Test-Org's - M-Maintenance. 0 . Operations, T = Technical) j Discussion of Cold Shutdown Intervals, See Next Att. ! s Valve Test Notes and i Valve f Sec and Type Test Code XI Size Actuator Norm and- Str. Organization Relief ! ClassCat(in.) Type- Pos Mode Time (Procedure) Requests
- S21204MU006 (10 006 C 675), HPSI Pumps 2P017-and 2P018 Suction Check Valve :
(Dwg.: 40ll2A/G 7) Valve Mfg.: Aloyco ; 2- C 10 CK/SA C CVP0/0P T(5023V3.5.4 VRR.08 2 C- 10 CK/SA C- CVT0/RR 0(5023 3 2.8) ) VRR 08 ,
* $21204MU008_ (10008C675),HPSIPumps2P018and2PolgSuctionCheck .
Valve
-(Dwg.: 40ll2A/C 7) Valve Mfg.: Aloyco .
2 C 10 CK/SA C , CVP0/0P T(5023 V 3.5.4) VRR 08 y 2 C 10 CK/SA C CVT0/RR 0(502332.8) VRR 08
- S21204MU012 4 012 C 358) HPS! Pump 2P017 Discharge Check Valve l k'-/O - (Dwg.:40112 G 3) Valve Mfg.: Anchor / Darling
- 2. -C 4 SCK/SA C- CVT0/CS 0(5023 3 3.31.2) 5
.i S21204MU015 (4 015 C 358), HPSI Pump iP019 Discharge Check Valve 2(Dwg.: C 40112A/C 4 3) Valve SCK/SA: C Mfg.: Anchor / 0(50?333.31.2)
CVT0/CS Darling- 5
- S23204MU016 ('4 016 C 358).-HPSI Pump 2P018 Discharge Check Valve 2(Dwg.: C 40ll2A/E-3) 4 Valve Mfg.:CVT0/CS SCK/SA - C Anchor /Darlirg2333.31.2) 0(S 5- .
- S21204MU017~ .(4 017 C 553), HPSI Pumps 2P918 1 2P019 to #2 High
. Pressure Header 4 (Dwg.: .40112A/C-2) Valve Mfg.: Anchor /DarVing .
2- C 4 ' CK/SA C CVT0/CS ' 0(5023 3 3.31.2) 5
- S21204MU018 (3_018 A 551) HPSI Combined Header to RCS Loop 1A Check :
Valve (Dwg.: 40112C/D3)ValveMfg.: Anchor / Darling: - - 1- : AC 3 ~ CK/SA- C AT/RR 0 5023 3 3.31.1. 5 1- 1AC 3~ .CK/SA- C CVT0/CS 0 5023 3 3.31.2 5
- S21204MU019, (3 019 A 551), HPSI Combined Hender to HCS Loop 1B Check Valve-(Dwg.: 40ll2C/C 3) Valve Mfg.: Anchor / Darling U
O -1
' l-
-AC 3 AC ' 3 CK/SA C 'AT/RR 0(5023 3 3.31.1) 5 !
CK/SA C CVT0/CS 0(5023-33.31.2) 5 .i ATTACHMENT 2 PAGE 40 0F 52
. . . - . - . . . . .- - . ..- , - ~. a . . -
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023 V 3.0 UNITS 2 AND 3 REVISION 7 PAGE 68 0F 208 r ATTACHMENT 2 i Ov TCN 7 - 1 ft - t
% I..& ,
i 10/16/91 l inservice Tosting Program for Valves San Onofre Nuclear Generating Station : o (TestOrg's: M Maintenance. 0 Operations. T = Technical) l Discussion of Cold Shutdown Intervals. See Next Att. Valve Test Notes and ' See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief
- Clas* Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S21204MUO20 (3 020 A 551), HPS! Combined Header to RCS Loop 2A Check '
Valve 1(Dwg.: 401120/B3)ValveMfg.: AC--3 -CK/SA C -AT/RR Anchor 0(502333.31.1) / Darling 5 1 AC 3 CK/SA C CVT0/CS 0(5023 3 3.31.2) 5
* $21204MUO21 (3 021 A 551), HPS! Combined Hender to RCS Loop 2B Check Valve 1(Dwg.:
AC40ll2C/F 3 CK/SA
- 2) Valve C
Mfg.:
. AT/RRAnchor /0(5023 Darling3 3.31.1) 5
-1 AC 3 CK/SA C CVT0/CS 0(502333.31.2) 5 1
g
- S21204MUO24 (10 024 C 406), LPSI Pump 2P015 Discharge Stop Check Valve A -
2(Dwg.: 40ll28/G 2) Valve Mfg.: Anchor / Darling' C 10 SCK/SA C CVT0/CS 0(5023 3 3.31.2) 5 .;
- S21204MU025 (10 025 C 406), LPSI Pump 2 Pol 6 Discharge Stop Check Valve (Dwg.: 40ll28/G 3) Valve Mfg.: Anchor /Derling 2 C 10 SCK/SA C CVT0/CS 0(502333.31.2) 5
- S21204MUO27 (12 027-A 551), Safety Injection Headers to RCS Loop 1A (Dwg.: 40ll3A/C 5) Valve Mfg.: Anchor / Darling 1 AC 12 CK/SA C AT/RR 0(5023 3 3.31.1) 5 1 AC -12. CK/SA C CVT0/CS. 0(502333.31.2) 5
- S21204MUO29 (12 029 A 551), Safety injection Headers to RCS Loop IB
'l(Dwg.:AC- 40ll3A/C 12 4) ValveCMfg.:AT/RR CK/SA Anchar/ Darling 0(S023 3 3.31.1) ;
~
1 AC 12. .CK/SA CL CVT0/CS 0(502333.31.2) 5
* ~ 521204MUO31 (12 031 A 551), Safety injection Headers to RCS Loop 2A 1(Dwg.:-40ll3B/C AC 12 5) ValveC Mfg.: . Anchor / Darling CK/SA AT/RR 0(50.23 3 3.31.1). 5
[. . IL AC 12 CK/SA C CVT0/CS 0(5023 3 3.31.2) 5 . S21204MU033 (12 033 A 551), Safety injection Headers to RCS Loop 2B (Dwg,: 40ll3B/C-3) Valve Mfg.: Anchor / Darling- , 1 AC 12- CK/SA' C .AT/RR 0(5023 3 3.31.1) 5 1 AC 12 CK/SA C CVT0/CS 0(502333.31.2) 5 ATTACHMENT 2 PAGE 41 0F 52 e; , , , , n -..,...u..., , , ,
... .,,,- ev. v.,.e., r r
NUCLEAR ORGANIZATION ENGINEERiits PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 69 0F 208 ATTACHMENT 2 TCH , 7 _Lg_
]
v 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: H Haintenance. 0 = Operations, T = Technical) Discussion of Cold shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S21204MV034 (? 034 C-329) HPSI 2P017 Miniflow (Dwg.: 40112A/h 2) Valve Hfg.: Rockwell Edwards 2 C 2 SCK/SA C CVT0/0P T(5023 V 3.5.4)
- S21204HUO35 (2 035 C 329), HPSI 2P019 Miniflow (Dwg.: 40ll2A/D 3) Valve Mfg.: Rockwell Edwards 2 C 2 SCK/SA C CVT0/0P T(5023-V 3.5.4)
- S21204" N (2 036 C 329), HPSI 2P018 Train 'A' Hiniflow (Dwg.: A/F 3) Valve Hfg.: Rockwell Edwards 2 C ; SCK/SA C CVT0/0P T(5023-V 3.5.4)
(~'T
- S21204MUO37 (2 037 C 329) LPSI Pump 2P015 Miniflow Stop Check Valve V (Dwg.: 40ll2B/H 2) Valve Hfg.: Rockwell Edwards 2 C 2 SCK/SA C CVT0/0P T(5023 V 3.5.4)
S21204HUO40 (12 040 A 551), Safety injection Tank 1008 Outlet Check Valve (Dwg.: 40ll3A/D 6) Valve Hfg.: Anchor / Darling 1 AC 12 CK/SA C AT/RR 0 S023 3 3.31.1) 1,5&l8 VRR ll 1 AC 12 CK/SA C CVP0/CS 0 S023 3 3.31.2) 1,5&l8 VRR ll AC 12 H S023 1 6.160) 1,5&l8 VRR ll { 1 CK/SA C CVT0/RR
- S21204HUO41 (12 041 A 551) Safety injection Tank 1007 Outlet Check ,
Valve (Dwg.: 40113A/D 2) Valve Mfg.: Anchor / Darling 1 AC 12 CK/SA C AT/RR 0(5023 3 3.31.1) 1,5&l8 VRR 11 1 AC 12 CK/SA C CVP0/CS O(5023 3 3.31.2) 1,5&l8 VRR ll 1 AC 12 CK/SA C CVT0/RR M(S023 1 6.160) 1,5&l8 VRR ll
- S21204MUO42 (12 042 A 551), Safety injection Tank T009 Outlet Check Valve (Dwg.: 40ll3B/D 6) Valve Mfg.: Anchor / Darling
'4 1 AC 12 CK/SA C AT/RR 0 5023 3 3.31.1) 1,5&l8 VRR 11 1 AC 12 CK/SA C CVP0/CS 0 5023 3 3.31.2) 1,5&l8 VRR ll 1 AC 12 CK/SA C CVT0/RR H S023-1 6.160) 1,5&l8 VRR ll O
v ATTACHMENT 2 PAGE 42 0F 52
I l NUCLEAR ORGANIZATION ENGlHEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 70 Of 208
, ATTACHMENT 2 {
TCN 7-13 l (! i LEIL2 10/16/91 ! Inservice Testing Program for Valves San Onofre Nuclear Generating Station j (TestOrg's: H. Maintenance 0 Operations T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See ano Type Test Yalve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S21204MUO43 (12 043 A 551), safety Injection Tank T010 Outlet Check Valve (Dwg.: 40113B/D 2) Vaive Mfg.: Anchor / Darling 1 AC 12 CX/SA C AT/RR 0 5023 3 3.31.1) 1,5&l8 VRR ll 1 AC 12 CK/SA C CVP0/CS 0 5023 3 3.31.2) 1,5&l8 VRR ll 1 AC 12 CK/SA C CVT0/RR H S023 1 6.160) 1,5&l8 VRR ll
- S21204MUO63 (2 063 C 329), LPSI Pump 2P016 Miniflow Stop Check Valve (Dwg.: 40ll28/E 2) Valve Mfg.: Rockwell Edwards 2 C 2 SCK/SA C CVT0/0P T(5023 V 3.5.4) em
- S2'204MUO72 (8 072 A 552) LPSI Check Valve to RCS Loop 1A
(') 1 (lng.: 40ll2D/G 2) Valve Mfg.: Anchor / Darling AC 8 CK/SA C AT/RR 0(S023 3 3.31.1) 5 1 AC 8 CK/SA C CVT0/CS O(5023 3-3.31.2) 5
- F21204MUO73 (8 073 A 552), LPS! Check Valve to RCS Loop 10 (Dwg.: 40ll20/f 2) Valve Mfg.: Anchor / Darling 1 AC 8 CK/SA C AT/RR 0 S023 3 3.31.1 5 1 AC 8 CK/SA C CVT0/CS 0 5023 3 3.31.2 5
- C1204MUO74 (8 074 A 552), LPSI Check Valve to RCS Loop 2A (Dwg.: 40ll2D/f-2) Valve Mfg.: AnAor/ Darling 1 AC 8 CK/SA C AT/RR 0(5023 3 3.31.1) 5 1 AC 8 CK/SA C CVT0/CS 0(S02333.31.2) 5
- S21204HUO75 (8 075-A 552), LPSI Check Valve to RCS Loop 2B (Dwg.: 40ll2D/H 2) Valve Mfg.: Anchor / Darling 1 AC 8 CK/SA C AT/RR 0(502333.31.1) 5 1 AC 8 CK/SA C CVT0/CS 0(5023 3 3.31.2) 5
- S21204MUO77 ('6 077-C 645), LPSI Pump 2P016 Suction Header Check Valve (Dwg.: 40ll2A/D 7) Valve Mfg.: Anchor / Darling 1 VRR 12 2 C 16 CK/SA C CVP0/0P T(S023 V-3.5.4) 2 C 16 CK/SA C CVT0/RR 4 5023 SPT 8) 1 VRR-12
- S21204HU084 (16 084 C 645), LPSI Pump ;P015 Suction Check Valve
- i. (Dwg.: 40ll2A/G 8) Valve Mfg.: Anche / Darling l /, ,T 2 C 16 CK/SA C CVP0/0' T(S023 V 3.5.4) 1 VRR-12 V 2 C 16 CK/SA C CVT0/ A T(5023-SPT-8) 1 VRR-12 1
F ACHMENT 2 PAGE 43 0F 52 l
- ~ _ - - - - .- -- . --. -__ _.. --.__.~ --..- -
t' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 71 0F 208 (q g ATTACHMENT 2 TCN 7-in ; UNIT 2 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance, 0 = Operations. T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
- S21204MUO87 (16 087 C 675), Spray Pump 2P013 Suction Check Valve i (Dwg.: 40114A/G 6) Valve Mfg.: Anchor 'n=rling 2 C 16- CK/SA C CVT0/CS 9($023 3 3.31.2) 5
* $21204MU088 (16 088 C 675), Spray Pump 2P012 Suction Check Valve (Dwg.: 40114A/C 6) Valve Mfg.: Anchor / Darling 2 C 16 CK/SA C CVT0/CS 0(S0233-3.31.2) 5
- S21204MUO99 (2 099 C 334), Containment isolation, SI Tank to Drain Header to RFWT 2T005 (Dwg.: 40ll4D/F 6) Valve Mfg.: Kerotest 2 A 2 GL/M C AT/RR T(S023 V 3.13) 10 v * ' S21204MU104 (2-104 C 329), HPSI 2P018 Train '8" tiiniflow (Dwg.: 40ll2A/E 2) Valve Mfg.: Rockwell Edwards 2 C 2 SCK/SA .C CVT0/0P T(S023"'.5.4)
$21204Mul52 (3 152 A 551). To #2 HPSI Header
-(Dwg.: 40lllA/F-5) Valve Mfg.: Anchor / Darling
-1_ AC 3 CK/SA C AT/RR 0(5023 3-3.31.1) 1 AC 3 CK/SA C CVT0/CS 0(5023 3 3.31.2)
- S21204MU',55'(3 155 C-551), HPSI Header #1 to RCS Loop 2 Hot Leg (Dwg.: 49112C/F-7) Valve Mfg.: Anchor / Darling
- 2. C' 3 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5
- S212)4Mul56 (3 156 A 551), HPSI Header #1-to RCS Loop 2 Hot leg inlet Check Valve ,
(Dwg.:'401120/82) Valve Mfg.: Anchor / Darling-1 AL 3 CK/SA C AT/RR -0(S023 3 3.31.1) 5 1- #4 3 CK/SA C CVT0/CS O(5023 3 3.31.2) 5 S21204MU157-(3 157 A-550), HPSI Header #2 to RCS Loop 1 Hot Leg (Dwg.:- 40ll2C/E-2) Valve Mfg.: Anchor / Darling , 1 AC 3 CK/SA C AT/RR T(5023-V-3.13) S&l0 1 AC 3 CK/SA C -CVT0/CS 0(5023 3 3.31.2) S&l0
- 521204Mul58 (3 158 A 550), HPSI Header #1 to RCS Loop 2 Hot Leg L. (Dwg,: 40ll2C/G-2) Valve Mfg.: Anchor / Darling L- -
1- AC 3 CK/SA C AT/RR T(5023 V 3.13) 5&l0 1: AC 3 CK/SA C CVT0/CS O(5023-3-3.31.2) S&lo ATTACHMENT 2 PAGE 44 0F 52 l u- _ _ _ _ - -~_ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ - . . . __
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3- REVISION 7 PAGE 72 0F 208 X ATTACHMENT 2 7-16 G TCH UNIT 2 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M-Maintenance. 0 = Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and . Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief '
.ClassCat(in.) Type Pos Mode Time (Procedure) Requests
- S21204Mul99 (16-199 C 645), LPS! Pump 2P016 Suction Header Check Valve (Dwg.: 40112A/0 7) Valve Mfg.: Anchor / Darling 2 C- 16 CK/SA C CVP0/0P T S023 V 3.5.4) 1 VRR 12 2 C 16 CK/SA .C CVT0/RR T S023-SPT 8) 1 VRR 12 S21204MU201 (16 201 C-645) LPSI Pump 2P015 Suction Header Check Valve (Dwg.: 40ll2A/G 8) Valve Mfg.: Anchor / Darling 2 C 16 CK/SA C CVP0/0P _ T S023 V 3.5.4) 1 VRR 12 2 C- 16 CK/SA C CVT0/RR T S023 SPT 8) 1 VRR 12
** System: Salt Water Cool'ing
- 2HV6200, Salt Water Cooling System Pump 2P112 Discharge Valve N Valve Mfg.: Fisher 3: (Dwg.:
B 40126A/G 30- BTF 3)/A0-OC- BT0/0P 18 0 5023 3 3.30) 3- 30 BTF/A0 OC FST0/0P.- 0 5023-3 3.30) 3 8 B- ' 30 BTF/A0 DC PIT /RR 0S0233-3.30)
- 2HV6201, Salt Water Cooling System Pump _2Pll3 Discharge _ Valve (Dwg.: _40126A/0 3) Valve Mfg.:- Fisher 3 8 30- BTF/A0 OC' BT0/0P 18 0 5023 3 3.30 3 8 30 'BTF/A0 OC FST0/0P O S023 3 3.30 3 8 30 BTF/A0 0C- PIT /RR 0 S023 3 3.30
*12HV6202, Salt Water Cooling System Pump 2P307 Discharge Valve (Dwg.: 40126B/G 3) Valve Mfg.: Fisher 3 B' 30- BTF/A0 OC BT0/0P 18 0 5023 3 3.30 3 8 30, BTF/A0 OC FST0/0P 0 S023-3 3.30 3 B 30. BTF/A0 OC- PIT /RR 0 5023 3 3.30 2HV6203, Salt Water Cooling System Pump 2Pil4 Discharge Valve
'(Dwg.: 40126B/E-3) Valve Mfg.: Fisher 3 B - 30 BTF/A0 _OC BT0/0P 18- 0(5023 3-3.30)
- 3. B 30- BTF/A0- OC- FST0/0P 0(S023-3 3.30)_
3 8 30 BTF/AO. OC - -PIT /RR 0(5023 3 3.30)
- 2HV6494,'SWCS from CCW Heat Exchanger E002B to Overflow at Seawall
._ (Dwg.: 40127C/D 3) Valve Mfg.: Fisher 3 :D . 30 .BTF/MO- C BT0/0P- 0(5023 3-3.30) 6&7 L A()_./ x3 8 30 BTF/MO C PIT /RR 0(5023*3-3.30) 6&7 L
ATTACHMENT 2 PAGE 45 0F 52 o L
NUCLEAR ORGANIZATION -ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 73 0F 208 AliACHMENT 2 TCN 7 - 1 6_, f UNIT 2 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M. Maintenance. 0 Operations. T = Technical) ! Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests ,
- 2HV6495,. Salt Water from CCW Heat Exchanger E002B (Dwg.: 40127C/E 2) Valve Mfg.: Fisher 3 8 30 BTF/MO C BT0/0P 75 0(502333.30) 6 3 8 30 C PIT /RR 0(5023 3 3.30) 6 BTF/MO ,
- 2HV6496, SWCS from CCW Heat Exchanger E001A to Overflow at Seawall (Dwg.: 40127C/C3)ValveMfg.: Fisher
-3 8 30 BTF/MO C BT0/0P 0 $023 3 3.30 6&7 3 8 30 BTF/MO C PIT /RR 0 S023 3 3.30 6&7
- 2HV6497, Salt Water from CCW Heat Exchanger E001A :
(Dwg.: 40M7C/B 2) Valve Mfg.: Fisher 1~ 3 B ad BTF/MO C BT0/0P 75 0502333.30) 6 3: B 30 BTF/MO C PIT /RR 0 5023 3 3.30) 6
* . S21413MU009 (30 009 D 722), SWCS Pump 2P112 Discharge Check Valve (Dwg.: 40126A/G 4) Valve Mfg.: TRW/ Mission.- . . . . .
3 C 30 SDCK/SA OC CVTC/0P . T(5023 V 3.5.4) 3- C 30 SDCK/SA OC CVT0/0P T(5023V3.5.4)
- S21413MU010 (30 010 D 722), SWCS Pump 2Pll3 Discharge Check Valve (Dwg.: 40126A/D 4) Valve Mfg.: TRW/ Mission 3 C 30 SDCK/SA OC CVTC/0P T(S023-V3.5.4 3 C 30 SDCK/SA OC CVT0/0P T(5023 V-3.5.4
- S21413MUO11 (30 Oll D 722), SWCS Pump 2P307 Discharge Check Valve (Dwg.: 40126B/G 4) Valve Mfg.: TRW/ Mission 3 C 30 SDCK/SA OC CVTC/0P T 5023 V 3.5.4 3 C -30 SDCK/SA OC CVT0/0P T S023-V 3.5.4
- S21413MUO12 (30 012-D 722), SWCS Pump 2Pll4 Discharge Check Valve (Dwg.: 40126B/E 4) Valve Mfg.: TRW/ Mission 3 C 30 SDCK/SA OC CVTC/0P T S023 V 3.5.4 3 C 30 SDCK/SA OC CVT0/0P T 5023 V 3.5.4
- S21413MU013 (1013-D 691), SWC5 " ump 2Pil2 Recirculot. ion to Cyclona Separt. w (Dwg.: 40126A/F-4) Valve Mfg.: Contr Jmatics
(]n 3 C 1 CK/SA C CVT0/0P T(5023 V 3.5.4) ATTACHMENT 2 PAGE 46 0F 52
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 ' UNITS 2 AND 3 REVISION 7 PAGE 74 Of 208
, ATTACHMENT 2 TCH ,_7 - 16 untu 10/M/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance. 0 Operations. T = Technical) ,
Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief t ClassCat(in.) Type Pos. Mode Time (Procedure) Request.
- S21413MV016 (1016D691),SWCSPump2Pil3RecirculationtoCyclone Separator (Dwg.: 40126A/D 4) Valve Mfg.: Controlmatics r
.i 3 C 1 CK/SA C CVT0/0P T(5023 V 3.5.4)
*: 521413MV02) (1-021 D 691), SWCS Pump 2P307 Reci .;ulation to Cyclone Separator 3(Dwg.:
.C 401268/F 1
- 4) Valve CX/SA C Mfg.:
CVT0/0P ControlmaticsT(5023 V 3.5.4) .
- S21413MUO24 (1 024 D 691), SWCS Pump 2P114 Recirculation to Cyclone m Separator
.d
.# 3 (Dwg.: 40126B/D 4) Valve Mfgt: Contrnimatics C l~ CK/SA C CVT0/0P T(5023V-3.5.4)
-* S21413MV047' (1 047 D 691), Check Valve Service Water Supply to Salt Water Pump 2P112.. .
(Dwg.: 40126A/G 7) Valve Mfg.: 3 C 1- . CK/SA C CVTC/0P .T(5023 SPT-7)
* ' S21413MV048 (1 048 D 691), Check Valve Service Water Supply to Salt Water Pump 2Pll3 (Dwg.: 40126A/D-7) Valve Mfg.: i 3 C- 1 CK/SA C CVTC/0P T(5023SPT-7) ,
- S21413MUO49 (1 049 D 691), Check Valve Service Water Supply to Salt Water Pump 2P307
-(Dwg.: 40126B/G 7) Valve Mfg.:
3 C 1 CK/SA. C CVTC/0P T(5023 SPT-7)
- S21413MU050. (1049 D 691), Check Valve Service Water Supply to Salt Water Pump 2Pil4 (Dwg.: 40126B/D 7) Valve Mfg.:
3 at 1 CK/SA C CVTC/0P T(5023SPT7) n ATTACHMENT 2 PAGE 47 0F S2
- _ _ _ _ ,. _ _ _ _ ~ _ -.
,. . . . -- _ . _ . . . _ - . . . _ ~ - - . . . -
NUCLEAR ORGAN!ZATION ENGINEERING PROCE0VRE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 FAGE 75 0F 208 : ATTACHMENT 2 ( TCN _fy,fL s uniu
- 10/15/91 Inservice testing Frogram for Valves San Onofre Nuclear'denerating Station i (TestOrg'stMMaintenance.0= Operations.T= Technical)
Discussion of Cold Shutdown Intervals, See Next Att.
- Valve Test Hotes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organ nation Relief ,
ClassCat(in.) Type Pos. Mode Time (Procedere) Requests .
** System: Stean-
- 2HV4053 Blowdown Isolation Valve ' Steam Generator E089 '
-(Dwg.: 40141A/C 2) Valve Mfg.: Fisher 2 8 6 GL/A0 0 'BTC/0P 9 0 5023 3 3.30) 3 2 B 6 GL/A0 0 FSTC/0P O S023 3 3.30) S ,
2 .B 6 GL/A0 0- PIT /RR 0S02333.30) 3 , 4
- 2HV4054. Blowde m isolation Valve Steam Gener4 tor E080 2(Dwg.: 8 40141A/F 6 2) Valve
~GL/A0 0 Mfp.: Fisher BTC/0P 9 0 S023 3 3.30 3 4 2 B 6' -GL/A0 0 FSTC/0P O S023-3'3.30 3 , t 2 B _6 GL/A0 0 PIT /RR 0 S023r3 3..'LO 3
- 2HV4057. Sample Isolation Valve Steam Generator E089 (Dwg.: 40141A/B 2) Valve Mfg.: Fisher '
2-~ B 3/4 GL//.J 0 BTC/0P 5 0 S023-3 3.30 3 2 'B 3/4 GL/A0 0 FSTC/0P O S023 3 3.30 3 2 B. 3/4 GL/A0 _0 PIT /RR 0 5023 3 3.30 3
- 2HV4058, Sample Isolation' Valve Steam Generator E088 (Dwg.: 40141A/F-2) Valve Mfg.: Fisher 2 B 3/4 _GL/A0- 0- BTC/0P 5 0 S023 3 3.30 3 2 B 3/4 GL/A0 0 FSTC/0P O S023 3 3.30 3 2 _B- 3/4- GL/A0 0 PIT /RR 0 5023 3 3.30_ 3
* -2HV8200. Steam from Steam Generator E089 to AFW Pump 2P140 (Dwg.: 40141C/E 3) Valve Mfg.: Fisher 2 B: 4; GL/A0 OC BT0/0P 4 0 S023 3 3.30) 2 B 4> GL/A0 OC FST0/0P O S023 3 3.30) 2 8 -4 GL/A0 OC PIT /RR 0 S023 3 3.30)
- 2HV8201 Steam from Steam Generator E088 to AFW Pump 2P140
'(Dwg.: 401410/E-3)VsiveHfg.: Fisher 2_ B 4_ GL/A0 OC BT0/0P 4 0 S023 3 3.30) 2 B_ 4 GL/A0 OC FST0/0P 0S02333.30) 2 B 4 GL/A0 OC PIT /RR 0 S023 3 3.30) n
%J ATTACHMENT 2 PAGE a0 0F 52
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE SC23-V 3.5
' UNITS 2 AND 3 REVISION 7 PAGE 76 0F 208 ATTACHMENT 2 TCN 7-18 v
') ,
10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M Maintenance, 0 = Operations, T = lect,nical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- 2HV8204, Steam Cenerator E089 Main Steam Isolation ialve (Dwg.: 40141C/B 2) Valve Mfg.: WKM 2 8 40 GA/HY 0 BTC/CS 8 0(502-3-3,17) 3&9 2 B 40 0 BTPC/0P 0(502-3-3.17) 3&9 OA/HY 2 B 40 0 FSTC/CS 0(S02-3-?.17) 3&S GA/HY 2 B 40 0 PIT /RR 0(S02 3-3.17) 3&9 GA/HY
- 2HVB205, Steam Generator E088 Main Steam Isolatitir Valve (Dwg.: 40141D/B-3) Valve Mfg.: WKM 2 B .40 GA/HY 0 BTC/CS 8 0(S02 3 3.17) 3&9 2 B 40 GA/HY 0 BTPC/0P 0(S02-3-3.17) 3&9
-, 2 B 40 GA/HY 0 FSTC/CS 0(S02-3-3.17) 3&9 f 2 B 40 GA/HY 0 PIT /RR 0(502-3-3.17) 3&9 w)
- 2HVB419, Main Steam Dump to Atmosphere (Dwg.: 401410/E 6) Valve Mfg.: Contr Cono 1 2 8 8 AV/A0 C BTC/CS 15 0(S023-3-3.31) 3&ll VRR-25 2 B' 8 AV/A0 C BT0/CS 60 0(S0233-3.31) 3&ll VRR 25 2 B B AV/A0 C BTr0/oP 0(5023-3-2.18.1) 3&ll VRR-25 2 B 8 AV/A0 C FS"!rt 0(S023 3-3.31) 3&ll VRR-25 2 B. 8 AV/A0 C PIT /R.; 0(5023-3-3.31) 3&ll VRR 25
- 2HV8421, Main Steam Dump to Atmosphere (Dwg.: 40141C/F-6) Valve Mfg.: Contr Ccmp i 2 0 8 AV/A0 C BTC/CS 16 0(S023 3-3.31) 3&ll VRR-25 2 B B AV/A0 C BT0/CS 60 013023-3-3.31) 3&ll VRR-25 2 0 8 AV/A0 C BTP0/0P 0(5023-3-2.18.1) 3.ill VRR-25 2 B 8 AV/A0 C FSTC/CS- 0(5023-3-3.31) Sill VRR-25 2 8 8 AV/A0 C PIT /RR 0(S023-3-3.31) 3A11 VRR-25
- 2PSV8401, Main Steam Relief Valve (Dwg.: 401410/G-7) Valve Mfg.: Crosby 2 C 6 SV/SA C RVT/RR M(S023-1-2.5) 2
- 2PSV8401, Main Steam Relief Valve (Dwg.: 40141D/G-6) Valve Mfg.: Crosby 2 C 6 SV/SA C RVT/RR M(5023-I-2.5) 2
- 2PSV8403, Main Steam Relief Valve i
l
/^')
n/ (Dwg.: 40141D/G-6) Valve Mfg.: Crosby 2 C 6 SV/SA C RVT/RR M(S023-1-2.5) 2 L ATTACHMENT 2 PAGE 49 0F 52
~ . - . . . - . - - .. .. -. .-
'S NUCLEAR ORGANIZATION ENGINEERING PROCEDURE SC23-V-3.5 J E W ;. AND 3' '
REVISION 7 PAGE 77 0F 208
,$ ATTACHMENT 2 7-16
) 4 TCN W!iU_.2 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station-(Test Org's: M M:intenance,- 0 = Operations, T = Technical)-
Discussion of Cold Shutdown Intervals,:See Next Att. -
. Valve Test Notes and See and Type Test Valve Code XI -Size Actuator Norm and Str. Organitation. Relief Class ~ Cat (i_n.) Type Pos. Mode Time (Procerce) Requests
- 2PSV8404, Main Steam Relief Valve (Dwg.:-401410/05) : Valve Mfg.: R*
2 .C- 6? SV/SA :C RVT/RR M(5023-I-2.5) 2
- 2PSV8405,: Main Steam Relief Valve (Dwg;: 40141D/G-5) Valve Mfg.: Crosby 2 C 6- SV/SA C RVT/RR M(S023-I-2.5) 2
- _ 2PSV8406, Main Steam Relief Valve (Dwg.:-40141n/G-4)-Valve Mfg.- Crosby 2- .C 6 iSV/SA C 'RVT/RR M(S023-1-2.5) '2
!'3 'j/7~; * - 2PSV8407, Main; Steam Relief Valve
.(Dwg.: 40141D/F-4) Vih e Mfg.: Crosby
'2 C_ 6 SV/3A C RVT/RR M(5023-I-2.5) 2
- 2PSV8408, Main Steam Relief _ Valve , _ . . .
.(Owg.: 401410/F-5). Valve Mfg.: Crosby
-.2 CL 6 _SV/SA -C RVT/RR ... M(S023-1-2.5) 2
- 2PSV8409,: Main Steam Relief Valve (Dwg.: 40141D/G 3) Valve Mfg.: Crosby 2 C 6 SV/SA- LC RVT/RR- M(5023-I-2.5) 2
- 2PSV8410, Main Steam Relief-Valvec (Dwg.: 40141C/G-7) Valve Mfg.: Crosby
, -2 -C 6 SV/SA- C :RVT/RR- M(S023-I-2.5) 2
* : 2PSV8411,- Main Steam Relief Valve
- _(Dwg.:'40141C/G-6). Valve Mfg.: -Crosby 2: 'C 6 SV/SA' C: RVT/RR M(S023-I-2.5) 2
- L2PSV8412, Main Steam Relief Valve (Dwg.:'40141C/G-6) Valve Mfg.: Crosby
'2 -C- -6: SV/SA -C- RVT/RR M(S023-I-2.5) 2
* - 2PSV8413, Main Steam Relief Valve
. (Dwg.i 40141C/G-5) Valve Mfg.: Crosby
-2 C~ 6 SV/SA 'C RVT/RR M(S023-I-2.5) 2
-]-.
ATTACHMENT 2 PAGE 50 0F 52
NUCLEAR ORGANIZA110N ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 78 0F 208
-ATTACHMENT 2 ni n TCN 7-in UNIT 2
-10/16/91-
-Inservice Testing Program for Valves San Onofre Nuclear Generating Station '
(Test Org's:=M Maintenance, 0 Operations T = Technical) Discussion of Cold Shutdown' Intervals, See Next Att. Valve Test s tes and See and Type. Test Valve Code X1' Size- Actuator Norm and Str. Organization Relief Class Cat- (in.) Type Pos. Mode Time (Procedure) Requests
*' 2PSV8414, Main Steam Relief Valve (Dwg.: 40141C/G 5) Valve Mfg.: Crosby 2- C 6 .
SV/SA- C; RVT/RR M(S023-1-2.5) 2-
* -2PSV8415. Main. Steam Relief Valve (Dwg.: 40141C/G 4) Valve Mfg.: Crosby 2 C 6 C RVT/RR M(5023-1-2.5) 2
-SV/SA
'* 2PSV8416 Main Steam Relief Valve (Dwg.: 40141C/G-4) Valve Mfg.: Crosby 2- C 6 4SV/SA 3 C RVT/RR M(5023-1-2.5) 2 yy
-
- 2PSV8417,oMain Steam Relief Valve-(')' ' i (Dwg.:'40141C/G 3) Valve Mfg.: Crosby ,
2 C 6- ' SV/SA .C RVT/RR M(5023-1-2.5) 2 L*: 2PSV8418,' Main Steam Relief Valve _ ' (Dwg'.:-401410/G-3) Valve Mfg.: Crosby
- C- 6- ~SV/SA C RVT/RR .M(S023-1-2.5) 2
- S2130lMU003 :(4-003-D 620),ESteam Supply - S/G E088 to AFP Turbine K007 Check Valve?
(Dwg.': 3- C - 40141C/F 4- 1) Valve Mfg.: Anchor / Darling T(5023;V-3.5.4) l&l8 VRR-18 CK/SA C CVP0/0P 3 C 4- CK/SA C CVTC/RR M(5023-I-6.160)- 1&l8 VRR-18 3 C ~ .4 CK/SA C CVT0/CS T(S023-V-3.5.4) 1&l8 VRR-18
'* .S2130lMU005 T(4-005-D 620), Steam Supply - S/G E089 to AFP-Turbine-K007 Check Valve-
-(Dwg.: 3 40141C/E-2) Valve Mfg.: Anchor / Darling-3- C.- -4 .CK/SA C CVP0/0P T(S023-V-3.5.4) 1&l8 VRR-18
-3: -C 4 CK/SA C- CVTC/RR M(S023-I-6.160) 1&l8 VRR-18 13 C 4- CK/SA' C CVT0/CS T(S023-V-3.5.4) 1&l8 VRR-18 S2130lMUO27 :(3/4-027-P-635), Instrument Air Supply Check Valve for 2HV8419 (Dwg '. : 401410/D-6) Valve Mfg.: Anchor / Darling 2- AC '3/4 CK/SA C AT/RR 0(S023-3-2,18.1) 12
}
2 AC 3/4- CK/SA C CVTC/0P 0(S023-3-3.30) 12 ATTACHMENT 2 PAGE 51 0F 52 i
_ +. - ~ . .
? NUCLEAR ORGANIZATION' ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AN.0 3 REVISION 7 PAGE 79 0F 208
, ATTACHMENT 2 TCN _7_- 16 r[-c%}.-..
10/16/91
' Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance. 0 - Operations, T = Technical)_
Discussion of Cold Shutdown Intervals, See Next Att. Valve -Test Notes and - See and Type Test . Valve Code -XI Size Actuator Norm and Str. Organization Relief Class Cat (in.)' Type Pos.' Mode Time (Procedure) -Requests
- S21301MUO34 (3/4 034-P 636), I..strument Air Supply Chect 'llve for 2HV8421 (Dwg.:: 40141C/E-5) Valve Mfg.: Anchor / Darling 2 AC'3/4 CK/SA C AT/RR 0(S023-3-2,18.1) 12 2 AC 3/4 CK/SA C CVTC/0P 0(S023-3-3.30) 12
** System: Sumps and Drains
- 2Hu e03, Containment Sump to Radwaste Sump (Dwgf:' 40ll7A/E-2) . Valve Mfg.: WKM
- 2. A 3: GA/MO- -. 0 AT/r.R 'T S023-V-3.13) 3,5,6&l0 sf ~ .
2- A -3 GA/MO O BTC/0P 40 0 S023 3-3.30) 3,5,6&l0 lTtd
-l 2 A 3 GA/MO -0_ PIT /RR 0 S023-3-3.30) 3,5,6&l0
* - 2HV5804, Containment Semp to Radwaste Sump Isolation Valve (Dwg.: 40ll7A/E-2) Valve Mfg.: Fisher-2 A 13- GA/A0 0 AT/RR : T(S023-V-3.13 ) 3,5&l0
-2. A 3 GA/A01 0 BTC/0P _5 0(S023-3-3.30) 3,5&lo 2- A 3 GA/A0 0- FSTC/0P 0(S023-3-3.30)- 3,5&l0 2 A 3 -' _GA/A0 0 PIT /RR 0(S023-3-3.30) -3,5&l0 l . .. ,
i ATTACHMENT 2 PAGE 52 0F 52 L w _ _ .
\
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 80 0F 208 m ATTACHMENT 3
}
TCN 7-16 UNIT 2 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
** System: Auxiliary Feedwater
- S21305Mul21 (6-121 D 598), AFW Pump 2P140 Supply to Steam Generator E089 Exercismg this valve while the plant is at power would result in placing unnecessary thermal stresses on the feedwater piping, which could result in premature f ailure of this piping.
- S21305MU126 (6-126 D-598), AFW Pump 2P141 Discharge Check Valve Same as $21305MU121.
- S21305MU532 (6-532-0-598), AFW Pump 2P504 Discharge Check Valve Same as S2:305MU121.
- S21305MU547 (6 547-D-598), AFW Pump 2P140 Discharge Check Vi lve Same as 521305MU121.
** System: Boric Acid Hakeup
- 2HV9235, BAMU Tank T072 to Gravity Feed to Charoing Pump Suction
(, ,) Opening-this valve would result in injecting highly concentrated boric \> acid into the reactor coolant system, causing plant shutdown.
- 2HV9240, BAMU Tank T071 to Charging Pump Suction Header Control Valve Same as HV-9235.
- 2HV9247, BARU Pump to Charging Pump Suction Control Valve Same as HV-9235.
- S21218MUb33(3-033-D-675),BAMUPump2P175 Discharge'CheckValve Full stroke exercising of this valve during plant power operation would result in over-boration of the reactor coolant system and plant shutdown.
- S21218MUO35 (3-035-D-676), BAMU Pump 2Pl74 Discharge Check Valve Same as S21218MUO33.
** System: Chemical and Volume Control ,
2HV9200, Charging Pumps to Regenerative Heat Exchanger E063 Exercising while the plant is at power would isolate normal charging to the RCS. This would result in a non compliance with Technical Specification 3.1.2.c, which requires two flow paths for boration during power operation, 2HV9205, Regenerative Heat Exchanger to Letdown Heat Exchanger (m) Exercising this valve during power operation would result in w.) unnecessary thermal stress transients on the regenerative heat exchanger and reactor coolant system charging nozzles. ATTACHMENT 3 PAGE 1 0F 12 s
.. - . ~ . . - . _ . - --
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023.V-3.5 UNITS-2 AND 3~ REVISION 7 PAGE 81 0F 208 VN ATTACHMENT 3- __7 - 16
-Gh TCN L UNIT 2 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY--
- 2LV0227B, VCT Outlet Valve .
Closing this valve requires shifting charging pump suction and injecting highly concentrated bort:-acid into the RCS, causing plant shutdown. 2?V9267. Letdown Containment isolation Valve Same as HV49205.
'* S21208MUO15 (4 015 C-675), VCT to Charging Pump Suction Check Valve Same as LV-02278,'
* ..S21208MU082 (3-082-C-675), Gravity Feed - BAMU Tanks to Charging Pump 2P190 Suction Same as.HV9235,
* ~$21208MUO83-(3-083-C-675), BAMU Pumps to Charging Pumps Suction Header
.Same as-HV9235.-
-*- $21208MU130.
(2-130 C-334), Contmt Isol - Chg Pump Disch to Aux Spray (q
-e Regen HX Bypass
/ Exercising this valve would result in unnecessary thermal transients
- and stress on the pressurizer spray nozzle,
**-System: . Component' Cooling Water
- 2HV6211, Containment Isolation Valve - CCW Non Critical Loop Exercising this valve during operation would secure or direct cooling water flow .from RCP seals, which could result in seal damage and plant-
' shutdown.
* ~2HV6212, CCW from Heat Exchanger E001A to Non-Critical Loop Same as HV-6211.
- 2HV6213, Component: Cooling Discharge to Non-Critical Loop Same as HV-6211,
- 2HV6216, Containment isolation - CCW Non-Critical Loop Return Same as HV-6211',- --
2HV6218, Component _ Cooling Water Pump. Suction From Non-Critical Loop Same as HV-6211. E 2HV6219,0 Component Cooling Water Pump Suction From Non-Critical Loop Same.as HV-6211. p :* - 2HV6223, Containment Isolation - CCW .lon-Critical Loop Supply ij Same as HV-6211. ATTACHMENT 3 PAGE 2 0F 12
l
-NUCLEAR 0RGANIZATION ENGINEERIN
G. PROCEDURE
5023 V 3.5
- UNITS 2 AND 3: REVISION 7z PAGE 82 0F-208
, -ATTACHMENT IxI :TCN ,_ f_- g-v WIL 2 c -JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY.'
* ' 2HV6236', Containment Isolation- .CCW Non Critical' Loop Return ,
iSame as HV-6211.
- 2HV6500, Component Cooling Water from SDCS Heat Exchanger E003 1 Same as HV-6211.:
*- 2HV6501,' Component Cooling Water from SDCS fleat Exchanger E004
.Same as HV-6211.
- S21203MU101 (28 101-0 725),- CCW Pump' 2P024 Discharge Check Valve Full stroke exercising of-this valve during power operation would require diverting-CCW from the RCP seals, which could result in seal-Ldamage and plant shutdown.
* :S21203MU102 (28102-D 725), CCW Pump 2P026 Discharge Check Valve Same-as'S21203Mul01. ,
- * - 521203MU103'(28-103;D 725), CCW Pump-2P025 Discharge Check Valve Same:as-$21203MU101.
'*LS21203MU264l (li264 D-627), Nitrogen Supply to Component Cooling
- Water Surge Tank T003A-Stroke _ Test requires placing-the affected_ CCW loop out of service, g
- * -521203MU265 (1:265-D 627), Nitrogen Supply to Component Cooling Water Surge Tank:T003A Same:as:$21203MU264.
* -S21203MU266- 1(1-266-D-627), Nitrogen' Supply to Component Cooling Water Surge Tank T004B Same as S21203MU264.
'* SR1203MU267; (1-267-D 627), Nitrogen Supply to Component Cooling-L
. Water Surge Tank T004B
=Same-as-S21203MU264.
*- $21203MU268; (1-268 D 627), Nuclear Plant Service Water Supply' to CCW
- Loop A
- Same as-521203MU264;
- LS21203MU269-(1-269-0 627), Nuclear Plant. Service Water Supply to CCW Loop B Same as1S21203MU264/
1 l? , ATTACHMENT 3 PAGE 3 0F 12
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 83 0F 208 ATTACHMENT 3
) TCN t - 3, UNIT 2 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
** System: Condensate and Feedwater
- 2HV1105, Feedwater Bypass Valve for Steam Generator E023 This valve cannot be full stroke exorcised during power operation as this would disturb steam generator level control, which could result in plant shutdown.
- 2HV1106, Feedwater Bypass Valve for Steam Generator E088 Sa::le as HV-Il05.
- 2HV4047, Feedwater Block Valve - Steam Generator E088 Full stroke exercising this valve during power operation would result in loss of feedwater flow to the steam generator, which could result in a plant shutdown.
- 2HV4048, Feedwater Isolation Valve - Steam Generator E088 Same as HV-4047.
- 2HV4051, Feedwater Block Valve Steam Generator E089 X Same as HV-4047.
'd
- 2HV4052, Feedwater Isolation Valve - Steam Generator E089 Same as HV-4047.
- S21305MUO36 (20-036 C-609), Main Feed Check at Steam Generator E089 _
This valve cannot be stroked during any mode in which main feed must remain uninterrupted. It therefore can only be' stroked open when main feed is initiated following a plant shutdown.
- 1521305Mul24 (6124-C-599), AFW Check Valve at Steam Generator E089 Exercising this valve while the plant is at power would result in placing unnecessary thermal stresses on the feedwater piping, which could result in premature failure-of this piping.
- S21305Mul29 (20-129-C-609), Main Feed Check at Steam Generator E088 This valve cannot be stroked during a'iy mode in which main feed must-remain uninterrupted. It therefore can only be stroked open when main feed is initiated following a plant shutdown. -
- S21305MU448 (6-448-C-599), AFW Check Valve at Steam Generator E088 Same as S21305Mul24.
** System: Containment HVAC (Normal) 2HV9948, Containment Purge Supply See Valve Relief Request No. 19. This valve is passive except in
-(o) Modes 5 and 6, at which time it is tested, in addition, exercising this valve during plant power operation would result in non-compliance with the Technical Specifications. ATTACHMENT 3 PAGE 4 0F 12
., ~. - -- .
NUCLEAR ORGANIZATION = ENGINEERING PROCEDURE S023 V-3.5-UNITS 2 AND 3' REVISION 7 -PAGE 84 0F 208 1 ATTACHMpT3 ' TCN- *I6
}]7-v .
UNIT 2
- JUST!FICATION FOR VALVES NOT TESTED QUARTERLY
- 2HV9949, Containment-Purge Supp1y _
Same as HV 9948. :
- 2HV9950, Containment Purge Exhaust Same as,HV 9948.-
*< 2HV9951, Containment Purge Exhaust Same as HV-9948.
** System:' Containment Spray-
- 2HV8150,. Isolation' Valve - SDCS HX E004 to LPSI Header Applying power or opening.this valve while the plant is at power would result in non-compliance with the Technical Specifications. Opening this valve could= defeat both trains of LPSI.-
- 2HV8151 Isolatics Valve 'SDCS HX E003-to LPSI Header Same as HV-8150; rm *' S21206MU004' (8 004-C 406), Containment Isolation Stop Check Valve -
Spray. Header fl~ (V) Exercising this valve with flow during operation or cold shutdown would result in"a spraydown of the containment building.
'* S21206MU006 .;(8-006-C-406), Containment Isolation Stop Check Valve - .
Spray _ Header #2 Samefas $21206MU004.
-* H S21206MUO12 -(8-012 C-406)', Spray _ Pump 2P012 Discharge ,Stop Check' Valve Full stroke exercising of this check valve while the plant is at power would: require disabling both trains of LPSI.
S21206MU014 (8 014-C-406), Spray Pump 2P013- Discharge Stop Check Valve Same as 521206MUO12., .-
*S21206MUO29J (0-029 C-645), Spray Pump 2P012 Discharge Check Valve to SuCS HX E004 Same as 521206MUO12. -
.S21206MUO30 .'(8-030 C-645), Spray Pump 2P013 Discharge Check Valve to-SDCS-HX E003 Same as S21206MUO12.
** System: Fire Protection 2HV5686, Contmt. Isolation Valve, Outside - Fire Prot. System Water O1 d Exercising this valve during plant power operation will activate the Fire Protection System in the Unit 2 Containment building.
ATTACHMENT 3 PAGE 5 0F 12'
1 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 -REVISION 7 PAGE 85 0F 208
-ATTACHMENT 3 ?); TCN ; Q x/
UNIT 2 JUSTIFICATION FOR V*.LVES NOT TESTED QUARTERLY
** System:LFuel Stor. Pool & Refueling
- 2LV02270, RWST To Charging Pump Suction Opening this valve would result-in injecting highly concentrated boric acid into-the reactor coolant system, causing plant shutdown.
- S21219MU052-(6 052-C-675), RWFT T006 to Charging _ Pump Suction Header Same as LV-0227C.
** System: Reactor Coolant
- 2HV0296A, Reactor Head Vent .
This valve is part of the Reactor Coolant System Boundary, Isolation. Opening this valve while the Reactor Coolant System is pressurized would release Reactor Coolant to the vent system. Further, power is normally removed from the-solenoid.
- 2HV0296B, Reactor Her,d Vent This valve is part of the Reactor Coolant system Boundary isolation.
. , , Opening this valve while the Reactor Coolant _ Systen is pressurized would release Reactor Coolant to the vent system. Further, power is (O(
rormally removed from the solenoid.
~
- 2HV0297A,' Pressurizer Vent Valve This valve is part of the Reactor Coolant system Boundary isolation.
Opening this valve while the Reactor Coolant System is pressurized would release Reactor Coolant to the vent- system. Further, power is
'normally removed from the solenoid.
- 2HV02978, Pressurizer Vent Valvo This valve ~ is'part of the Reactor Coolant system Boundary isolation.
Opening this valve while the Reactor Coolant System is pressurized would' release Reactor Coolant to the vent system. .Further, power is , normally removed from the-solenoid.
- 2HV0298,. Vent to Contat from Reactor Head / Pressurizer This valve is not censidered accessible during power operation.
Further, power is normally removed from the solenoid._
* -2HV0299,' Quench' Tank' Inlet-from Reactor Head / Pressurizer Vent l This valve is normally inaccessible during power operation. Further, power is normally reaioved from the solenoid.
* -2HV9201,-Regenerative Heat Exchanger E063 to Auxiliary Spray l Exercising-would result in unnecessary thermal transients and stress on the pressurizer : pray nozzle.
l7 lA ATTACHMENT 3 PAGE 6 0F 12-l E
l IE
~ NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS.2 AND 3- REVISION 7 PAGE 86 0F 208
*A -ATTACHMENT 3
} TCN UNIT 7~1R JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
/ .
t
- 2HV9202, Regenerative Heat Exchanger E063 to RCS Loop 2A .
, his valve must remain open during power operation in order to ensure
' _ittency with' assumptions made regarding system' flow to the RCS
%d" legs in the accident analysis and to cotoply with the intent of LC0/3.5.2.
- 2HV9203, Regenerative Heat Exchanger E063 to RCS Loop 1A Same as HV 9202.
- 2HV9204,:RCS-Loop 28 Letdown to Regenerative Heat Exchanger Exercising this' valve during-power operation would result in unnecessary thermal stress transients on the regenerative heat exchanger _and reactor coolant _systae charging r,azzles.
- 2HV9217. Reactor Coolant System Bleed Off to Volume Control Tank
-Exercising this valve could result in Reactor Coolant Pump seal failure and subsequent reactor shutdown,-
.: 2HV9218. RCS Bleed Off to VCT ! solation Valve Inside Containment Sameas HV-9217.1 V
- 2TV0221.-Letdown Isolation Valve Same as HV-9204.
- _S21201MU019 (2-019-A 554), Acxiliary-Spray Check Valve.
-Same as HV-9201.-
52120lMU020 (2-020 A 554), Charging Line Check Valve to RCS Loop 2A This-valve cannot be tested without closing HV-9203 (discussed elsewhere in _this table). S'lt01MUO21:(2-021-A-554), i Charging Line Check Valve to_RCS Loop 1A This valve cannot be tested without-closing HV-9202 (discussed
- elsewhere in this table),
'.S2120lMU129 (2-129-A-554), Auxiliary Spray to RCS from Charging Pumps Same as HV-9201.
S2120lMU200. (14-200-C-645), Pump 2P016 Suction Check Valve
- This valve can only-be exercised when plant is on shutdown cooling.
* ~S21201MU202 (14-202-C-645), Pump 2P015 Suction Check Valve
.-Same as S21204MU200.
** System: Resp. & Service Air System ,
(d
- 2HV5388, Containment Isolation Valve - Instrument Air Exercising-this. valve during ple:it power operation isolates instrument air to the Containment and could result in a plant shutdown.
ATTACHMENT 3 PAGE 7 0F 12
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 87 0F 208 ATTACHMENT 3 fx TCH 7"16
~
UNIT 2 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY I
** System: _ Safety injection
- 2HV0396, Flow Control Valve LPSI Pumps to Shutdown Cooling System l Full stroke testing of this valve during power operation would result in non-compliance with Technical Specification 3/4.5.2, which requires this valve to be closed with power to the valve operator removed.
- 2HV8152, Isolation Valve - SDCS Heat Exchanger E004 Inlet Same as HV-0396.
* '2HV8153, Isolation Valve - SDCS Heat Exchanger E003 Inlet Same as HV 0396. -
- 2HV8160, Flow Control Valve - SDCS Heat Exchanger Bypass Full stroke exercising of this valve during power operation would .
result in non-compliance with Technical Specification 3/4.5.2, which requires this valve to be open with power removed.
- 2HV8161, Block Valve - SDCS Heat Exchanger Bypass to LPSI r~N Same as HV-8160.
~
- 2HV8162, LPSI Pump 2P015 Miniflow Block Valve Same as HV-8160.
- _2HV8163 LPSI Pump 2P016 Miniflow. Block Valve Same as HV-8160.
* '2HV9337, Isolation Valve - SDCS to LPSI Pump Suction This valve is required by Technical Specification 3/4.5.2 to be interlocked to prevent opening whenever reactor _ coolant system pressure exceeds 376 PSIA.
- 2HV9339, Isolation Valve - SDCS from RCS Loop 2 Same as HV-9337.
- 2HV9340, Safety injection Tank T008 Outlet Valve-to RCS Loop 1A Restoring power to this valve or opening this valve while the plant is at power would result-in-non-compliance with the Technical Specifications.
- 2HV9345, Safety injection Tink T008 Vent Valve During power cperation, Technical Specifications require power to be locked out'for this valve. This prevents inadvertent pressurization of the SIT.
r
- 2HV9350, Safety lujection Tank T009 Outlet Valve to RCS Loop 1B Same as HV-934'.
{5} ATTACHMFNT 3 PAGE 8 0F 12
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 88 0F 208 m ATTACHMENT 3 7-16 TCN m-
)
UNIT 2 JUSTIFICATION FOR VALVES NOT TESTED QUAP ERLY
- 2HV9355, Safety injection Tank T007 Vent Valve Same as HV-9345.
- 2HV9360, Safety injection Tank T009 Outlet Valve to RCS Loop 2A Same as HV 9340.
- 2HV9365, Safety injection Tank T009 Vent Valve Sawe as HV-9345.
- 2HV9370 Safety Injection Tank T010 Outlet Valve to RCS Loop 28 S.ame as HV-9340.
- 2HV9375, Safety injection Tank 1009 Vent Valve Same as HV-9345.
- 2HV9377, SDCS Bypass to LPSI Suction Isolation Valve This valve is required by Technical Specification 3/4.5.2 to be interlocked to prevent opening whenever reactor coolant system pressure exceeds 376 psia.
j
- 2HV9378, SDCS Bypass to LPSI Suction Isolation Valve Same as HV-9377,
- 2HV9420, Control Valve HPSI Header #1 to RCS Loop 2 Hot Leg Same as HV-0396. -
- 2HV9434,- Control Valve - PPSI Header #2 to RCS Loop 1 Hot Leg Same as HV-0396.
- S21204MUO12 (4-012-C-358), HPSI Pump 2P017 Discharge Check Valve This valve cannot be exercised while the plant is at power because the HPSI pump cannot overcome RCS Pressure. To exercise disc to fully spen position requires 200 GPM.
e S21204MUO15 (4-015-C-358), HPSI Pumt, 2P019 Discharge Check Valve Same as S21204MUO12.
- S21204MU016'f4-016-C-358), HPSI Pump 2P010 Discharge Check Valve
, Same as 521204HUO12.
,
- S21204MUO'17 (4-017-C-553), HPSI Pumps 2P018 & 2P019 to #2 High
~f Pressure Header Same as S21204MU012.
- S21204MUOl8 (3-018-A-S51), HPSI Combined Header to RCS Loop 1A Check n Valve l' Exercising this valve while the plant is at power would result in non-compliance with Technical Specification 3/4.5.2.
ATTACHMENT 3 PAGE 9 0F 12
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V 3.S UNITS 2 AND 3 REVISION 7- PAGE 89 0F 208 ATTACHMENT 3 fy TCN 7~1a
% )/
UNIT 2
- JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
* ~S21204MUOl9- (3 019 A-551), HPSI Combined Header to RCS Loop 1B Check Valve Same as $21204MU018.
*~ S21204MUO20 (3-020-A-551), HPSI Combined Header to RCS Loop 2A Check Valve Same as 521204MU018.
- S21204MUO21 (3 021-A-551), HPSI Combined Header to RCS Loop 2B Check
-Valve Same as 521204MU018.
* - S21204MUO24 (10-024-C-406), LPSI P'u mp 2P015 Discharge Stop Cher.n Valve '
While the plant is at power, LPSI pumps cannot overcome RCS pr,issure.
~
Additionally, aligning the system discharge to the _RWST would defeat both~ trains of LPSI.
- S21204HUO25-(10-025-C-406), LPSI Pump 2P016 01scharge Stop Check Valve Same as.S21204MUO24.-
t
!() * - S21204MUO27 (12-027-A-551), Safety Injection Headers to RCS-Loop 1A v During n wer operation there is no full flow path available to ' stroke
. test H F valve. LPSI or HPSI pumps cannc overcome the RCS pressure.
Requi m 2000 GPM fur full Stroke.
*= S21204MUO29 (12-029-A 551), Safety injection Headers to RCS Loop _18 ip : Same as: 521204MUO27.
'*o S21204MUO31-(12-031-A-55)), Safety Injection Headers to RCS Loop 2A i Same:as S21204MUO27.:
4
- S21204MUO33-(12-033-A-551), Safety injection Headers to RCS Loop 2B
.Same as S21204MUO27..
M . *; S21204MUO40 (12-040-A-551), Safety Injection Tank T008 Outlet Check J Valve Opening-this. valve during power operation is not.possible against normal .RCS- operating-pressure. 3- rattial strcke test is the only to possible during Cold shutdown '. " t o system configuration. See Valve Relief Request. Number 11.
- S21204MUO41 '
(12-041-A 551). Safety Injection Tank T007 Outlet Check
. Valve Same as S21204MUO40.
- S21204MUO42- (12-042-A-551), Safety injection Tank T009 Outlet Check C\ Valve L
V Same as S21204HUO40, i ATTACHMENT 3 PAGE 10 0F 12
, ~. . ... . . . - - . - - - . - . .~ .
f
.- NUCLEAR ORGANIZATION- ENGINEERING PROCtDU,G S023-V-3.5 .
- UNITS 2 AND'31 ' REVISION 7 PAGE 90 0F 208-4 ' ATTACHMENT 31 1 TCN 7 UNIT 2 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
*$S21204MUO43- -(12043-A551),Safetyinjection-Tank-T010 Outlet-Check .
- Valve
;Same as'.521204 MOO 40.-
- iS21204MUO724 (8' 072-A-552), LPSI Check Valve- to RCS Loop 1A '
'There .is not flow: path to exercise' this- valve during power operation. '
. LPSI' pumps cannot-overcome RCS Pressure while the-p1 ant is at power.
* . S21204MUO73 (8 073-A-552), LPSI Check Valve to RCS Loop lB
- Same as 521204MUO72.-
*~ tS21204MUO741(8 074-A-552), LPSI Check Valve to RCS Loop 2A Same as 521I04MUO72.
'*' S21204MUO75 (8 075-A-552), LPSI Check Valve to RCS Loop 2B
- Same' as~ SE1204MUO77..
2 1*i S21204MU087 (16 087-C 675), Spray Pump 2P013 Suction Check Valve , Same;as-521204MUO12. J* 'S21204MU088~(16-088 C-675),JSpray-Pump 2P012 Suction Check Valve o [QN Same as'S21204MUO12 .-
* .=S21204Mul52?(3-152-A551),xTo#2HPSIHeader
-Valve cannot:be--stroked at power.because the-HPSI pumps cannot iovercome RCS Pressure..o Additionally, opening the HPS! Header
? Isolation' valve during power operation would result ininon-compliance (with' Technical l Specification 13/4.5.2.
* --521204MU155 (3-155_C-551), HPS! Header #1 to RCS Loop':2 Hot leg '
Full _ or- partial, stroke exercising.of this_ valve while the plant is at . power would result!in-non compliance with Technical-Specification 3/4.5.2. In addition, while the plant is at' power,' HPSI pumps cannot.
'overcomefRCS pressure.
~
L *= S21204Mul56? (3-156-A-551), HPSI-Header #1 to RCS Loop-2. Hot Leg L .
> Inlet Check Valve:
?Same as-S21204MU155.-
4 m <* iS21204MU157.(3L157-A-550),-HPSI Header #2 to RCS_ Loop 1 Hot Leg Lc ;Same.as S21204MU155.
-* S21204Mul58-(3-158-A-550), HPSI-Header #1 to RCS Loop 2 Hot Leg
[_ Same'as S21204MU155.
'+ ~
j ATTACHMENT 3- PAGE 11 0F 12 L
e NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.S' UNITS 2 AND 3 REVISION 7 PAGE 91 0F 208
- ATTACHMENT 3
' _.s'; TCN 7-16 UNIT 2 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
** System: Steam
- 2HV8204, Steam Generator EM9 Main Steam Isolation Valve Full stroke exercising at full plant power would cause a loss of f 9 %
of cur heat removal frosn the nrimary coolant systsm, a reactor trip on assymetric powertin the core and actuation of the steam and prtssurfzer(primary) reliefs. e: ,
*' 2HV8205, Steam Generator E088 Mr.in Steam Isolation Valve Same as HP-8204.
- 2HV8419, Main Steam Dump to Atmosphere Full stroke exercising of tiiis vilve during power operation could result in a reactor plant transient due to energy released via the steam dump.
- 2HV0421, Main Steam Dump to Atmerhere s
Same as'HV-8419. g. D[N, r-N. ATTACHMENT 3 r\GE 12 0F 12
~
p pc
, v -s . - p1 me- ,
3};_i;l, m --
- w - .- - _ - _ . _ _
} (} ' 3 .{f.
- ';wQ s ..
$y 1 1
1 i, s .
! ENGINLERING PROCE0l'Rf I S023.V.3'.5 0 NUCl. EARL 0RGANIZAT10N .
- UNITS: 2 fjQl3 - , .
REVISION 7- - PAGE SE Oftt00' 1 l O ra i !, ATTACHMENT-4 _
, w(-c[. ,
TCH 7-16 F :lNDEX
.i g System e EM J 93 i ,
I.
?' Air Con'ditioning $ystem; . .,, ._. .. ... .............. .
l 4' ^ ~, ! AtixiU a ry Boif.er $ys tem . . . . . . . . . . . . . . . . . . . . . . . . . . . 93 94' c,' tA a Qiary Feed.tatert. . ... . . . ................... - 96
M' t ?g(Scric Aci'J andMakeup Volume ... . . . . .'. .. .. .. 1 . ... .. .. .. .. .. .. .. .. ... . . .. .. .. .. .. ..
97 Chemical Control 99
-Chilled Wateri.'. .1.c...-.-. . . .-. ... . . . . . . . . . .- . . . .
99 L Component 1'ooling Water '. ; . . . . . . . . . . . . . . . . . . . . . . . . A'%jh y 3 ondensate end-Feedwater . . . . . . . . . . . . . . . . . C W.#j ; Containment-HYAC-(Normal)-.;,- . 4 . . . . . . . . . . . . . .-. 106 107 ",. iContainment Spray ,,, . .,. . . . . . . . . . . ........ ... 108
..~................. 110.- 1 q Diesel _ Fuel Oil System' .-h s. . ..
...... 111
- 6py ' Dieser Diesel Generator Air Start .. . . .. ...........
Generator System". . .=.' . . . . . . . 113 NT A n. Fire Protection . . .-. . . . . .-. . . . . . . , , .
. . . . . . . . . . 113 <
gy. Fuer stor. Pool & RefJelh g'. . .:. . . . . . . . . . .. . ....,
. .. 'll! l Gas Radwaste . .-_.-. ., . .. . . .. . . . . . , .
~
. . 114
-- Liquid:RadwasteL. .:... c . . . . ..... ........ ,..., 114- ,
VMitrogenSas:.-.,;.L..-
~
115 m ' 116' *
- p. JNuclear Samplingi : L. '. .. .. ... ......... .........
119 c Nucl e ar~ Se rv i ce Wat e r . . . . . . . . . . . . . , . . , . . . . . . . , lf;, H- l Reacto n Cool ant . . . a . J .. . . . . . . . . . . . . . . . . . . . . . . , . 120 Resp. &'.ServiceTAir System . . . . . ...........-......,. .123 Safety Injection -... . ... . , . . . , ,_ , .-. . ... . . ._. . . . . 123 g Salt Water.Cooli_ngs.e. . , , . . .. ..a . ..,......... . . . . 136 y.j
- v;L g $ team j .7.c... ,-.c.-. . ._. . . ,-_. ._... , ,., , , ,_, ., ,;,_._, , , _ 139 ,
g_ y' Sumpsiar.d Drains,-.: .. . .-. . ... .
. , , 443
. :: w 0 .,
-{i .
. : n,
.a +a i
II f.- F M. y a
.h e
lI
.I
(
-ATTACHMENT 4 PAGE 1 0F 52
, -yy
. . . . lm - -- , . - -
-NOCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AO 3' REVISION 7 PAGE 93 0F 208
- - ATTACHMENT 4
)- TCH ..._7 -1h l!t0La 10/16/91 Inservice Testing Program for Valves 1 1 San Onofre Noclent Generating Station (Test'0.T ;: HsMaintenance, 0 - Operations T - Technical)
Discussion of f. aid Shutdwn Intervals, See Next Att. Valve Test Notes and See and Type Test Yalve Code XI Size Actuator Nonn and Str. Organization Relief Class Cat (in.) Type Pos. Hode Time (Procedure) Reque:ts
** System: Air Ccnditioning System
- 3HCV9918, Hydrogen Purge Exhaust Control Valve
-(Dwg.: 40172BS03/G-2) Valve Kfg.: Fisher 2 A 6 BTF/tl C AT/RR T'S023-V-3.13) 10 .c
- 3HCV9945, Hydrogan Perge Unit A 080 Olscharge (Ng,; 40172B503/G-5) Valve Mfg.: Fisher 2 A- 6 BTF/H C AT/RR T(S023.V-3.13) 16
'* 3HV9917, Containment Hydrogen Purge Outlet (Dwg.: 401720503/G-3) Valve Mfg.: Fisher
~~} . 6&lo j 2 A 6 BTF/MO C AT/RR T(5023-V-3.13)
- 3HV9946, Containment Hydrogen Purge Inlet (Dwg.: 40272BS03/G 4) Valve Mfg.: Fishat 2 A 6 BTF/NO C. AT/RR - T(S023-V 3.13) M10
*' 531500MUO38 (3/4 03S C-306), ILRT Pressuritation Connection (Dwg.: 40171BS03/C-2) Valve Nfg.: Kerotest 2 A~ 3/4 GL/M C' AT/RR T{S023-V.3,13) 10
- S31 MOMUO39 (3/4-039-C 396 , ILRT Pressurization Connection
('swg.: 401710503/0 1) Valva) Mfg.: Kerotert 2 A 3/4 GL/H C- AT/RR T(S023-V-3.13) 10
** System: Auxiliary Boiler Systeen S31312HUO37. (2-037-C-307), Auxiliary Steam Inside Containrant Isolution Valve (Dwg.: 40169CS03/D 4) Valve Mfs.: Vogt 2 :A 2 GA/M .C AT/RR T(5023-V-3.13) 10 S31312MUO38 (2-038-C-337), Auxiliary Steam Outside Containment 1501ation Val de (Dwg.: 40169CS03/E-4) Valve Hfg.: Vogt 2 A 2 GA/M C AT/RR T(5023-V-3.13) 10 7
i
}
/
ATTACHMENT 4 PAGE 2 0F 52
- NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 'S023 V-3.5-UNITS 2 AND 3 REVISION 7 PAGE 94 0F 208 i
;M ATTACHMENT 4 TCN 7~1n UNIT 3
> 10/16/91 Inservice Testing Program for Valves '
San Onofre Nuclear Generating Station (Test'Org's: M-Maintenance, 0 = Operations. T - Technical)
> Discussion of Cold Shutdown Intervalr., See Next Att.
w Notes and-Valve Test See and Type Test Valve ,
-Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type - Pos Mode Time (Procedure) Requests
-** System:. Auxiliary feedwater h *; 3HV4705, S/G E088 Auxiliary Feedwater Contral Valve
-(Dwg;: 40160AS03/E 3) Valve Mfg.: WKM
.. 1 3,4&6 3= B 6 GL/M0 C BTC/0P 33.5 0(5023 3-3.30 3 B :6 C BT0/0P 35 0(S023-3-3.30 3,4&6
' GL/MO .
3 61 PIT /RR 0(5023-3-3 30 3,4&6 .
-B~ -GL/M0' C
~
r G
- 3HV4706 S/G-E089 Auxiliary feedwater Contro1~ Valve- -
(Dwg.: 40160AS03/D-3) Valve Mfg.:- WKM . 3 iB 6 C- BTC/0P 33.5 0(S023-3-3.30) 3,4&6
.GL/MO 3,4&6
% -3 :B 6- GL/MO C BT0/0? 35 0(S023 3-3.30) yk):- 3. B' 6- GL/MO - C PIT /RR- 0(S023-3 3.30) 3.4&6
* -:3HV4712, Auxiliary Feedwater Pump 3P504 Discharge to Steam Generators "
- -(Dwg.: 40160AS03/G 3) Valve Mfg.: WKM -
- ' 3- B.-4 _ GL/MO - C- BTC/0P 36. 0(S023 3 3.30)_ 3&6.
- ' _B; 14
- -C- BT0/0P 36- 0(S023-3-3.30) 3&6
!3 GL/MO 3 8. 4i 'GL/MO C PIT /RR 0(50233-3.30) 3&6 .
- D3HV4713,LAuxiliary Feedwater Pump 3P141-Discharge to Steam Generators J(Dwgi: 40160AS03/B-3) Valve.Nfg.:- WKM e
U
- 3 ' ' S: 4 -GL/MO -C
.C:
BTC/0P.36 0(5023-3-3.30) ~3&6 0(S023-3 3.30)
- b 3~
3
.B B
4 4_ GL/A0 GL/M04 z C-BT0/0P- 36 FIT /RR 0(50233-3.30)-
.3&6 3&6
* -3HV4714,' Isolation Valve - Auxiliary Feedwater to S/G E0881
'(Dwg.: 40160AS03/F-1) Valve Mfg.:. Fisher 2 B 6 GL/EH C _BTC/0P. 10 0(S023 3-3.30) 3
. 2 ~. "B= 6 LGL/EH C- BT0/0P 10 0(5023-3-3.30) -3 92' -B 6 :GL/EH -C FSTC/0P 0(S023-3-3.30) 3 2; 6 3 B -GL/EH _C- -PIT /RR 0(5023a3-3.30)
- 3HV4715,: Isolation Valve - Auxiliary feedwater.to S/G E089
- a. (Dwg.: 40160AS03/D 2) Valve Mfg.: WKM
- 2. 'B- 6 BTC/0P .10; 3,4&6 GL/MO C 0(S023-3-3.30) 2 B 6 ,GL/MO- C BT0/0P 10 0(5023-3-3.30) 3,4&6 gg 12 B - -6 GL/MO C- PIT /RR 0(5023-3-3.30) 3.4&6 Li L ATTACHMENT 4 PAGE 3 0F 52 1 .
I m,m ,, , , ., __ _ _ _ _ ._ . _ . - _ . . _ _
t l- ' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023 V-3.5 UNITS 2 AND-3 -REVISION PAGE 95 0F 208
- ATTACHMENT 4 7-18 (v)_ TCN Mli]
10/16/91
-Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M '4aintenance, 0 Operations, T = Technical)
Discussio'n of Cold Shutdown Intervals, See Next Att. Valve Test' Notes and ; See and Type _ Test Valve _ Code __XI Size Actuator Norm and Str. Organization Relief ClassCat(in.)_ Type- Pos Mode Time (Procedu e) Requests
- 3HV4716 -~ Auxiliary Feedwater Pump Turbine Trip and Throttle Valve (Dwg.: 40160BS03/E-3) Valve Mfg.: Gimpel Inc.
3 B 4 GA/MO C -BT0/0P 13.5 0(S023 3 3.30) 3,4&6
~3 B .4 GA/M0_ C PIT /RR 0(S0233-3.30) 3,4&6
- 3HV4730, Isolation-Valve - Auxiliary Feedwater to S/G E088
'~
(Dwg.:- 40160AS03/F-2) Valve Mfg.: WKM 2 ;B: _6 GL/MO C BTC/0P 10 0 S023-3-3.30) 3,4&6 2 -B '6 GL/MO C -BT0/0P-10 0 S023-3-3.30 3,4&6 2 B -6 GL/MO _C PIT /RR 0 5023-3-3.30 3,4&6
*- 3HV4'/31, Isolation Valve - Auxiliary Feedwater to S/G E089 y]m (Dwg.: 40160AS03/D-1) Valve Mfg.: ' Fisher 2 B 6 GL/EH- C -BTC/0P 10 0(S023-3-3.30) 3 2 B 6- GL/EH C BT0/0P _10 0(S023-3-3.30) 3 2- B 6 GL/EH C FSTC/0P O S023-3-3.30 3 2 B -6 _GL/EH C PIT /RR .0 S023-3-3.30 3
- 3HVA'62, Bypass Valve-for 3HV4712
-(Dwg.: 40160AS03/F-3) Valve Mfg.: Control-Components 3 LB- 4- GL/EH C BTC/0P _40 0(S023-3-3.30) 3 3 B- 4 GL/EH C FSTC/0P 0(S023-3-3.30) l3 .B 4 GL/EH C PIT /RR 0(S023-3-3.30)
- 3HV4763, Bypass Valve for 3HV4713 .
- (Dwg.:: 40160A503/C-3) Valve Mfg. :- Control Components 3 B 4' GL/EH; C BTC/0P 40 0(5023-3-3.30) 3 3- B' 4 GL/EH' C FSTC/0P 0(S023-3 3.30) 3 B- .4- C- PIT /RR 0(S023 3-3.30)
GL/_EH ,
* -S31305MU121 (6-121-D-598), AFP 3P140 Supply to S/G E089 (Dwg.: 40160AS03/0-3) Valve Mfg.: Anchor / Darling 3 - C -- 6 .CK/SA -C CVT0/CS O(5023-3-3.31.2) 5 S31305MU126-(6-126-0-598), AFP 3P141 Discharge Check Valve
' (Dwg. :' 40160A503/B-5) Valve Mfg. : Anchor / Darling 3 C. -6 CK/SA C CVT0/CS 0(S023-3-3.31.2) 5 (O
V S31305MU532 (6-532-D-598), AFP 3P504 Discharge Check Valve (Dwg.: 40160AS03/G-4) Valve Mfg.: Ancnor/ Darling 3 C 6 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5 ATTACHMENT 4 PAGE 4 0F 52
/
_ . , . . . ~ --_ _ _ 4 .. __ - __ _
-NUCLEAR ORGANIZATION . ENGINEERING PROCEDURE S023 V.3.5
' UNITS 2 AND 3 REVIS10N'7 PAGE 96 0F 20B ATTACHMENT 4
- f3 TCN 7 4jx 10/16/91 hservice Testing Program for Valves St. Onofre Nuclear Generating Station
'(Test Org's: M-Maintenance, 0 Operations, T Technical)
Discussion of Cold Shutdown Intervals, See Next Att. , Valve Test Notes and ' Sec and Type -Test Valve Code XI Size Actuator' Norm and . Str. Organization Relief ClassCat-(in.) Type Pos. Mode Time (Procedure)-- Requests
- S31305MU547 (6 547-D 598), AFP 3P140 Discharge Check Valve (Dwg.: 40160AS03/E 3) Valve _ Mfg.: Anchor / Darling 3 C- 6 C CVT0/CS O(5023-33.31.2) 5 <
CK/SA
** System: Boric Acid Makeup
* ~3FV9253, Makeup Water to VCT (Dwg.: 40125BS03/G-2)-Valve Mfg.: ITT 3 8 3- GL/A0 C BTC/0P 2 0(S023 3-3.30 3 -- B ~ 3- GL/A0 C FSTC/0P. 0(5023-3 3.30 3 B- '3 'GL/A0 C; PIT /RR 0(S023 3-3.30 b-V
- 3HV9231. Boric' Acid' Makeup' Pump'3Pl75 Recirculation to Tank T072 (Dwg.:-40125AS03/D-8) Valve Mfg.: ITT t
3 B GL/A0 -C~ BTC/0P - 2-_ 0 S023 3-3,30 L 3 .B: 2 GL/A0 C' FSTC/0P 0 5023-3-3.30
+_ 3 'B 2- - GL/A0 C . PIT /RR' 0 5023-3-3.30
*' 3HV9235 BAMU Tank T072.to Gravity Feed to Charging. Pump Suction
-(Dwg.:--40125AS03/B 5) Valve Mfg.: Target Rock 3- B 3: GA/MO C- BT0/CS ~12 0(5023-3-3.31) S&6 1 13 B. 3 GA/M0 C PIT /RR ,0(5023 3-3.31) 5&6
, *n 3HV9236, BAMU Pumpi 3P174 Recirculation to Tank T071
'(Dwg.: 40125AS03/D-1) Valve Mfg.: ITT-3- B 2 -GL/A0 C BTC/0P 12 0(S023-3-3,30) 3 8 2 GL/A0 C~ FSTC/0P , 0(S023-3-3.30).
3 B: 2~ GL/AO - C PIT /RR 0(5023-33.30) 3HV9240, BAMU Tank T071 to Charging Suction Header Control Valve (Dwg.: 40125A503/B 4) Valve Mfg,: Target Rock 3_ -B~ 3 GA/M0' -C BT0/CSL-12 0(S023-3-3.31) S&6 3 B 3 GA/MO C PIT /RR 0(S023-3-3.31) S&6
* ~ 3HV9247, BAMU Pump to Charging Pump Sucticn Control Valve (Dwg.: 40125BS03/E-5) Valve Mfg.: Target Rock
'3- B. 3' -GA/MG C BT0/CS 12 0(S023-3-3.31) 5&6
-3 8 3 g
y GA/MO C- PIT /RR 0(5023-3-3.31) 5&6 ATTACHMENT 4 PAGE 5 0F 52
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 97 0F 20B
' ATTACHMENT 4 TCH 7-10 UNIT 3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M-Maintenance. 0 Operations, T = Technical)
Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests S3121BMUO33 (3-033-D-675), Boric Acid Hakeup Pump 3Pl75 Discharge Check Valve (Dwg.: 40125BS03/B-5) Valve Mfg.: Aloyco/Walworth . 3 C 3 CK/SA C CVT0/CS 0(S023-3-3.31.2)
- S3121BMUO35 (3-035 D 675), Boric Acid Hakeup Pump 3Pl74 Discharge Check Valve (Dwg.: 40125BS03/C-5) Valve Mfg.: Aloyco/Walworth 3- C 3 CK/SA C CVT0/CS 0(5023-3-3.31.2)
- S31218MUO46 (3-046-Y-675), Demin Water to Boric Acid Mixing Tee (Dwg.: 40125BS03/G 3) Valve Mfg.: Aloyco/Walworth 2 C 3 CK/SA C CVTC/0P T(5023-V-3.5.4)
** System: Chemical and Volume Control
- 3HV9200, Charging Pumps.to Regenerative Heat Exchanger E063 (Dwg.: -40123AS03/D-3) Valve Mfg.: Fisher 2 A 2 GL/A0 0 AT/RR T(S023-V-3.13) 5&l0 2 A 2 GL/A0 0 BTC/CS 8 0(5023-3-3.31) 5&l0 2 A 2 GL/A0 0 BT0/CS 25 0(S023 3-3.31) S&l0 2 A 2 GL/A0 0 FST0/CS O(5023-3-3.31) 5&l0 2 A 2 GL/A0 0 PIT /RR 0(5023-3-3.31) 5&l0 3HV9205, Regenerative Heat Exchanger E063 to Letdown Heat Exchanger (Dwg.: 40123AS03/F-3) Valve Mfg.: Fisher 2 A 2 GL/A0 0 AT/RR T(S023-V-3.13) 3,5&l0 2 A 2 GL/A0 0 BTC/CS 4 0(S023-3-3.31) 3,5110 2 A 2 GL/A0 0 FSTC/CS 0(S023-3-3.31) 3,5&l0 2 A 2 GL/A0 0 PIT /RR 0(S023-3-3.31) 3,5&l0 3LV02278. VCT Outiet Valve (Dwg.: 40124AS03/B-5) Valve Mfg.: Target Rock 2 B -4 GA/MO O BTC/CS 11 0(S023-3-3.31) 5&6 2 B 4 GA/M0 0 PIT /RR 0(5023-3-3.31) 5&6
- 3TV9267, Letdown Containment Isolation Valve (Dwg.: 40123A503/F 3) Valve Mfg.: Westinghouse, Inc.
-9 2 2
A A 2 2 GA/MO GA/M0 O 0 AT/RR BTC/CS 13 T(S023-V-3.13) 0(5023-3-3.31) 3,5,6&l0 3,5,6&l0 2 A 2 GA/M0 0 PIT /RR 0(S023-3-3.31) 3,5,6&l0 ATTACHMENT 4 PAGE 6 0F 52
d NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 98 0F 20B
- ATTACHMfNT 4
-( m .%y TCH 7-16 UNIT 3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station xll1
* (TestOrg's: H Maintenance. 0 = Operations, T Technical)
Discussion of Cold Shutdown Intervals, See Next Att. V lve- Test Notes and See and Type Test Valve Code XI Size Actuator Norm and S*r. Organization Relief Class Cat (in.) Type Pos. Mode- Time (Procedure)- Requests
- S31208MUO15 (4 015 C-675), VCT to Charging Pump Suction Check Velve ,
(Dwg.: 40124AS03/B-4)ValveMfg.: Aloyco/Walworth 2' C 4 CK/SA 0 CVTC/CS 0(H23 3-3.31.2)
- S31208MU017 (2-017-C 554), Charging Pump 3P192 Discharge Check Valve (Dwg.': 40124B503/C-3) Valve Mfg.: Kerotest 2- C 2 CK/SA C CVT0/0P ?(S023-V-3.5.4)
=
- S31208MUO67 (2 067-C 554), Charging Pump 3P190 Discharge Check Valve
'(Dwg.: 40124BS03/G-2) Valve Mfg.: Kerotest 2= C 2 CK/SA C CVT0/0P T(5023-V-3.5.4)
- S31208MUO69 (2-069 C 554), Charging Pump 3P191 Discharge Check Valve d (Dwg.: 40124BS03/D 2) Valve Mfg.: Kerotest 2 -C- 2 CK/SA C- CVT0/0P T(S023-V-3.5.4)
"
- LS31208MU082 (3 082-C-675), Gray Feed - BAMU Tanks to Charging Pump ,
3P190 Suction (Dwg.:= 40124B503/H-5) Valve Mfg.:- Aloyco/Walworth 2- C3 CK/SA C '. CVT0/CS 0(S023-3-3.31.2) -5
- S31208HUO83 (3 083-C-675), BAMU Pumps to Charging Pumps Suction Header (Dwg.: 40124B503/F-7) Valve Mfg.: Aloyco/Walworth-2 C. 3 -CK/SA =C CVT0/CS .0(S023-3-3.31.2) 5
* . S31208MU122 (2-122-C 554), Charging Pumps to Regen HX E063 Check Valve
'(Dwg.: 40123A503/D 4) Valve Mfg.: Kerotest 2 AC 2_ CK/SA- C AT/RR T(5023-V 3.13) 10 VRR-14 2- AC- 2 -CK/SA C CVTC/RR T(S023-V-3.13) 10 VRR-14 2- AC 2- -CK/SA -C CVT0/0P . T(S023-V-3.5.4) 10 VRR-14
- S31208MU130- f2-130 f 334), Contmt Isol. - Chg Pump Disch to Aux.
skay Regen HX. Bypass
- (Dwg.: 2 40123AS03/B 2)' Valve Mfg.:- Kerotest
'2- A 2 CL/M C AT/RR- T(S023-V-3.13) 7&lo 12- A 2 GL/M C BTC/CS 0(S023-3-3.31) 7&l0 2 A 2 GL/M C BT0/CS O(5023-3-3.31) 7&l0 2 A 2 GL/M C PIT /RR 0(S023-3-3.31) 7&l0 b
ATTACHMENT 4 PAGE 7 0F 52
' NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3- REVISION 7 PAGE 99 0F 208 ATTACHMENT 4
['N TCN 7-16 s%lr' 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station
-(Test Org's: H Maintenance. 0 Operations, T - Technical)
Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size- Actuator Norm and Str. Organization Relief Ciass Cat (in.) Type Pos. Mode Time (Procedure) Requests <
** System: Chilled Water
- 3HV9900. Containment Isolation Valve - Cooling Supply, Penet # 45 (Dwg.: 40170AS03/G 4). Valve Mfg.: Fisher 2 A 8 BTF/MO O AT/RR T(S023-V-3.13 3,6&l0 2- A 8 BTF/MO O BTC/0P 14 0(50233-3.30 3,6&l0 '
2- A 8 BTF/M0 0 PIT /RR - 0(S023-3-3.30 3,6&l0
* - 3HV9920,- Containment Isolation-Valve - Cooling Supply (Dwg;: 40170A503/G-2) Valve Mfg.: Fisher 2 A' 8 BTF/A0 0 AT/RR T(S023-V-3.13) 3&l0 2 A .8 BTF/A0 0 -BTC/0P 12 0(S023-3-3.30) 3&l0
(] t/
'2 2
A A 8 8 BTF/A0 BTF/A0 0-0 FSTC/0P PIT /RR 0(S023-3-3.30) 0(S023 3 3.30) 3&l0 3&l0
* - 3HV9921, Containment Isolation Valve - Cooling Return (Dwg.: 40170AS03/F-2) Valve Mfg.: Fisher .
2- A 8 BTF/A0 0: AT/RR :T(S023-V-3.13) 3&lo 2- A 8 BTF/A0 0 BTC/0P 26 0(5023-3-3.30) 3&l0 2 A 8 BTF/A0 0 FSTC/0P - 0(S023-3-3.30) 3&l0 21 A '8 BTF/A0 0 PIT /RR 0(S023 343.30) 3&l0
- 3HV9971, Containment Isolation Valve - Cooling Return Pen # 46 (Dwg.: 40170AS03/F-4) Valve Mfg.: Fisher 2 A 8' BTF/MO O AT/RR T(S025-V 3.13)- 3,6&l0
- 2 .A 8 BTF/MO- 0 BTC/0P 13 0(S023 3-3.30) 3,6&l0 22~ _A 8 BTF/MO O PIT /RR 0(S023-3-3.30) 3,6&l0.
-** System: Component Cooling Water
* -3HCV6537, CCW Pump 3P024 Miniflow Block Valve (Dwg.: 40127A503/F-2) Valve Mfg.: Fisher 3- B- 10 BTF/A0 BTC/0P S 0(S023-3-3.30) 3 _B -10 BTF/A0 0- FSTC/0P 0(S023-3-3.30) 13 B- 10 BTF/AO' 0- PIT /RR 0(5023-3-3.30)
- 3HCV6538, CCW Pump 3P025 Miniflow Block Valve
~ (Dwg.: 40127AS03/E-2) Valve Mfg.: Fisher 3- B 10 :BTF/A0 0 BTC/0P 5 0(S023-3-3.30)
O(~) :3 3 B 10 10 BTF/A0 0 0
'FSTC/0P 0(S023-3-3.30)
B BTF/A0 PIT /RR 0(S023-3-3.30) ATTACHMENT 4 PAGE 8 0F 52-I
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 100 0F 208 s ATTACHMENT 4
') TCN 7-1s UHlI_l 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M Maintenance. 0 - Operations, T = Technical)
Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
- 3HCV6539, CCW Pump 3P026 Miniflow Block Valve (Dwg.: 40127AS03/B 2) Valve Mfg.: Fisher 3 8 10 BTF/A0 0 BTC/0P 5 0(5023-3-3.30) 3 B 10 BTF/A0 0 FSTC/0P 0(S023-3-3.30) 3, B 10 BTF/A0 0 PIT /RR 0(5023-3-3.30)
- 3HV6211, CCW Non-Critical Loop to Containment Isolation Valve (Dwg.: 40127FS03/G-3) Valve Mfg.: Fisher 2 A 10 BTF/MO O AT/RR T(S023 V-3.13) 3,5,6&l0 2 A 10 BTF/M0 0 BTC/CS 15 0(S023-3-3.S1) 3,5,6&l0 2 A 10 BTF/MO O PIT /RR 0(5023-3-3.31) 3,5,6&l0 j
- 3HV6212, CCW From Heat Exchanger E001A to Non-Critical Loop
- (Dwg.: 40127DS03/E 7) Valve Mfg.: Fisher 3 8 28 BTF/A0 0 BTC/CS 13 0(S023-3-3.31) 14 3 8 28 BTF/A0 C FSTC/CS 0($023-3-3.SI) 14 3 B 28 BTF/A0 0 PIT /RR- 0(S023 3-3.31) 14
- 3HV6213, Component tooling Water Discharge to Non-Critical Loop (Dws.: 40127DS03/D-7) Valve Mfg.: Fisher 3 B -28 PTF/A0 0 BTC/CS 14 0(SOS s-3.31) 14 3 B 28 61f/ A0 0 FSTC/CS 0(S0c.-3-3.31) 14 3 B 28 BTF/A0 0 PIT /RR 0(5023-3-3.31) 14
- 3HV6216, Isolatior Valve - CCW Non-Critical Loop From Containment (Dwg.: 40127FS03/C-5) Valve Mfg.: Fisher 2' A- 10 BTF/MO O AT/RR T(5023-V-3.13) 3.5,6&l0 2 A 10 BTF/M0 0 BTC/CS 15 0(5023 2-3.31) 3,5,6&l0 2 A 10 BTF/MO O PIT /RR 0(S023-3-3.31) 3,5,6&l0
- 3HV6218, CCW Pump Suction from Non-Critical loop (Dwg.: 40127AS03/E-7) Valve Mfg.: Fisher
'3 8 28 BTF/A0 0 BTC/CS 16 0(S023-3-3.31) 5&l4 3- B 28 BTF/A0 0 FSTC/CS 0(5023-3-3.31) S&)4 3 8 28 BTF/A0 0 PIT /RR 0(5023-3-3.31) 5&i4 3HV6219, CCW Pump Suction from Non-Critical Loop 'm (Dwg.: 40127AS03/D-7) Valve Mfg.: Fisher N
3 B 28 BTF/A0 0 BTC/CS 16 0(S023-3-3.31) 5&l4
-) 3 B 28 BTF/A0 0 FSTC/CS 0(5023-3-3.31) 5&l4 3 8 28 BTF/A0 0 PIT /RR 0(S023-3-3.31) 5&l4 ATTACHMENT 4 PAGE 9 0F 52
r NUCLEAR ORGANIZATION kNGINEERINGPROCEDURE S023-V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 101 0F 208 q ATTACHMENT 4
-i ,<n TCN 7*16 q
N ..
. 10/16/91 Inservice Testing Prograhn for Valves San Onofre Nuclear Generating Station-(Test-Org's: M Maintehance. 0 Operations, T = Technical)
Discussion of Cold Shutdown' Intervals, See Next Att. Valve Test Notes and See and Type Test Valve
-Code XI~ Size Actuator Norm and Str. Organization Relief Requests
. Class cat (in.) Type Pos. Mode Time (Procedure)
- 3HV6223, Isolation ~ Valve - CCW Non-Critical Loop Containment inlet (Dwg.: 40127FS03/G 4) Valve Mfg.: Fisher 2 A 10 BTF/MO 0 -- AT/RR T(0023-V-3.13 3,5,6&l0-2 A- 10- BTF/MO O BTC/CS 15 0(5023-3-3.31 3,5,6&l0 2 .A _10 , BTF/MO O PIT /RR 0(5023-3-3.31 3,5,6&l0
* ' 3HV6236, Containment ' Isolation - CCW No'n Critical Loop Return (Dwg._ : 40127FS03/C-6) Valve Mfg.: Fisher 2 A 10 BTF/MO- 0 AT/RR T(S023-V 3.13) 3,5,6&l0 2 -A- _BTF/MO O BTC/CS 15 0(5023 3-3.31) 3,5,6&l0-2 A 10 BTF/MO O PIT /RR 0(S023-3-3.31) 3,5,6&l0
- ,m
- 3HV6366 Component Cooling Wacer to Emergency Cooling Unit E-401-('") -- (Dwg.: 40172BS03/C-7) Valve Mfg.,: WKM 2 A. 10 - -GA/M0 0 AT/RR T S023-V-3.13 3,6&lo 2 A 10 GA/MO- 0 BTC/0P 12 0 S023-3 3.30 3,6&l0 2 A 10 GA/MO O BT0/0P 12 0 5023 3-3.30 3,6&l0 2- A 10 GA/MO O _ PIT /RR 0(S023-3-3.30 3,6&l0
- 3HV6367 Component Cooling Water. from Emergency Cooling Unit E-401 (Dwg.:~ 40172B503/D-7) Valve Mfg.: WKM .
2- A '10-GA/MO_ C AT/RR T(S023-V-3.13)- 3,6&l0-2 A 10 - GA/M0 - C .BTC/0P 12 0(S023-33.30) 3,6&lo 2 A -10_ GA/MO C BT0/0P 12 0(5023-3-3.30)- 3,6&lo 2 A 10 GA/MO C PIT /RR 0(5023-3-3.30) 3,6&l0
- 3HV6368[ Component Cooling Water to Emergency Cooling. Unit E-400 2(Dwg.:
~
-A 40h.!BS03/E-7)
'l GA/M0 Valv-0 Mfg.
AT/RR
- WKM T(S023-V-3.13) 3,6&l0 4 2 A 10 GA/MO O BTC/0P 12 -0(5023-3-3.30) 3,6&l0 2 -A- 10 GUM 0 0 BT0/0P - 12 0(5023-3-3.30) 3,6&l0 2 A 10 GA/M0 0 PIT /RR- 0(S023-3-3.30) 3,6&l0
- 3HVr.469, Component Cooling Water from Emergency Cooling Unit E-400 (D%. : 40172BS03/F-7) Valve Mfg. : .WKM- l 2 - A- 10 GA/M0 C AT/RR T(5023-V-3.13) 3,6&l0 2 A 10 -GA/MO C BTC/0P 12 0(S023 3-3.30) 3,6&l0
_q 2 'A 10' GA/MO C BTC.'0P 12 0(S023-3-3.30) 3,6&l0 Q 2 ~~ A -10 GA/MO C PIT /RR 0(S023-3-3.30) 3,6&l0 ATTACHMENT 4 PAGE 10 0F 52
.. a
NUCLEAR ORGANIZATI0fl ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 102 0F 208 m ATTACHMENT 4
~
I UNIT 3 ; 10/16/91 Inservice Test % Program for Valves . San Onofre Nuck ar Generating Station l (Test Org's: M. Maintenance, 0 - Operations, T - Tocht.ical) Discussion of Cold Shutdown Intervals, See Next Att. valve Test Notes and See and Type Test Valve Relief Code XI Size Actuator Norm and Str. Organization ClassCat(in.) Type Pos. Mode Time (Procedure) Raquests
- 3HV6370, Component Cooling Water to Emergency Cooling Unit E-399 (Dwg.: 40172BS03/D-2) Valve Mfg.: WKM 2 A 10 GA/MO O AT/RR T(5023-V-3.13) 3,6&l0 2 A 10 GA/MO. O BIC/0P 12 0(S023-3-3.30) 3,6&l0 2 A 10- GA/MO O BT0/0P 12 0(S023-3-3.30) 3,6&l0 2 A 10 GA/MO O PIT /RR 0(5023-3-3.30) 3,6&l0
- 3HV6371, Component Cooling Water from Emergency Cooling Unit E-399 (Dwg.: 40172B503/C-2) Valve Mfg.: WKM 2 A 10 GA/M0 C AT/RR T(5023-V-3.13) 3,6&l0 2 A 10 GA/MO C BTC/0P 12 0(S023-3-3.30) 3,6&l0 m 2 A 10 GA/M0 C BT0/0P 12 0(5023 3-3.30) 3,5&l0 2 A 10 C PIT /RR 0(5023-3-3.30) 3,6&l0
) GA/MO
- 3HV6372, Component Cooling Water to Emergene.y Cooling Unit E-402 (Dwg.: 401/28503/F-2) Valve Mfg.: WKM 2 A 10 .GA/MO. O AT/RR T(5023-V-3.13). 3,6&l0 2 ~A 10 GA/MO O BTC/0P 12 0(S023-3-3.30) 3,6&l0 2 A 10 GA/M0 0 BT0/0P 12 0(5023-3-3.30) 3,6&l0 2 A 10 GA/M0 0 PIT /RR 0(S023-3-3.30) 3,6&l0
- 3HV6373, Component Cooling Water from Emergency Cooling Unit E-402 (Dwg.: 40172BS03/E-2) Valve Mfg.: WKM 2 A 10 GA/MO C AT/RR T(S023-V-3.13) 3,6&l0 2 A 10 GA/M0 C BTC/0P 12 0(S023-3-3.30) 3,6&l0 2 A 10 GA/M0 C BT0/0P 12 0(S023-3-3.30) 3,6&l0 2 A 10 GA/MO C PIT /RR 0(5023-3 3.30) 3,6&l0 3HV6500, Component Cooling Water from SDCS Heat Exchanger E003 (Dwg.: 40127ES03/F 4) Valve Mfg.: Fisher .
3 B 18 BTF/A0 C BT0/CS 8 0(S023-3-3.31) 3&5 3 B 18 BTF/A0 C FST0/CS 0(S023-3-3.31) MS 3 8 18 BTF/A0 C PIT /RR 0(5023 3-3.31) 3&5 3HV6501, Component Cooling Water from SDCS Heat Exchanger E004 (Dwg.: 40127ES03/C-4) Valve Mfg.: Fisher 3 8 18 BTF/A0 C BT0/CS 8 0(S023-3-3.31) 3&S _ 3 8 18 BTF/A0 C FST0/CS 0(S023-3-3.31) 3&5 / 3 8 18 BTF/A0 C 0(5023-3-3.31)
) PIT /RR 3&S ATTACHMENT 4 PAGE 11 0F 52
Tr ] NUCLEAR ORGANIZATION. ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 LAND 3 REVISION 7 PAGE 103 0F 208 ; f(}l
-R fu^ "k"- $6 UNIT 3 10/16/91 Inservice-Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M-Maintenance. 0 = Operations T = Technical)
Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and Sec. and Type Test Valve Code XI Size Actuator Norm and Stt . Organization Relief ClassCat(in.) Type Pos. Mode- -Time (Procedure) Requests
- 3PSV6356, CCW' Surge Tank T003 Relief Valve (Dwg.: 40127BS03/H 5) Valve Mfg.: Crosby 3 C. 1 SV/SA .C RVT/RR- M(S023-I-8.88) 2
* - 3PSV6359,- CCW Surge Tank T004 Relief Valve (Dwg.: 40127BS03/D S) Valve Mfg.: Crosby-3 C 1 SV/SA C RVT/RR M(S023-1-8.88) 2
- S31203MR229 Drain Valve, CCW Pump P026 Drain Line - 1
- (Dwg. : -.40127AS03/B-5) Valve Mfg.: -Vogt 3 B 1 GATE /M- C BT0/0P 0(i.ater) 7 b -
- S31203MR232, Drain Valve, CCW Pump P025 Drain Line (Dwg.: 40127AS03/D 6) Valve Mfg.: Vogt 3 _B l1 GATE /M C BT0/0P - 0(Later) 7
-* S31203MR233, Drain. Valve, CCW Pump P024 Drain.Line (Dwg.: 40127A503/G-5). Valve Mfg.: Vogt 3- -B .1 GATE /M C. BT0/0P 0(Later) 7
>* S31203MU1011(28-101-D-725),Cv- Pump 3P024 Discharge Check' Valve (Dwg;: .40127AS03/G-4)--' Valve Mfg.: TRW/ Mission 3 C - : 28- SDCK/SA OC- - CVP0/0P T(S023-V-3.5.4) 3- .C -28 SDCK/SA OC CVTC/CS 0 S023 3 3.31.2) 3 C 28 -SDCK/SA-OC CVT0/CS 0 S023-3-3.31.2)
- S31203Mul02 (28-102-D 725), CCW Pump 3P026 Discharge Check Valve (Dwg.: 40127AS03/B-4) Valve Mfg.: TRW/ Mission _ .
3 .C 28' SDCK/SA OC CVP0/0P .T(S023-V-3.5.4) C -28 SDCK/SA OC - CVTC/CS -0(S023-3-3.31.2) 3 C- 28' SDCK/SA OC CVT0/CS 0(50233-3.31.2) v ATTACHMENT 4 PAGE 12 0F 52
.. - . , - . . . ..~....--..-...-....-.-.-.....-.-...--.-.----...-.-.-.w.
-4 NUCLEAR ORGANIZATION- - ENGINEERING PROCEDURE $023.V 3.5 l UNITS 2 AND 3- REVISION 7 PAGE 104 0F 208 !
A ATTACHMENT 4 i
- IY TCN _7 - 1) ;
L/ : , i b THIS PAGE LEFT . P f BLANK , i l O: INTENTIONALLY ., s n r i r i e I T O .
< ATTACHMENT 4 PAGE 13 0F 52 + y ', .e e-+-ev.-.r --
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t NUCLEAR ORGANIZATION ENGINECRING PROCEDURE $023<V 3.5 REVISION 7 PAGE 105 0F 208 i UNITS 2 AND 3 ATTACHMENT 4 h a MIL) TCH 7*16 . 10/16/01 Inservice Testing Program for ' .1ves
- sfrc Nuclear Generating Station (Test _ Orc f* :intenance. 0 Oper4tions. T Technical)
Disc s sn . Cold Shutdown Intervals, see Next Att. Valve Test Notes and
- See and lype Test Valve
. Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type. .
Pos. Mode Time (Procedure) Requests
- S31203Mul03 (28 103 D 725). CCW Pump 3P025 Discharse Check Valve (Dwg.: 40127A503/D 4) Valve Mfg.: TRW/ Mission
-3 C 28 SDCK/SA OC CVP0/0P TS023V3.5.4) 3 C 28 SDtK/SA OC CVTC/CS 0502333.31.2) 3 -C 28 SDCK/SA'DC CVIO/CS 0 5023 3 3.31.2) ,
* -S31203MU2(4 (1 264 0 627), Nitrogen Supply to Component Cooling Water Surge Tank T003A
. (Dwg.: 40127bS03/H 5) Valve Mfg.: Kerotest - 3 AC 1. CK/SA C AT/RR T(S023 SPT 2) 13 3 AC 1 CK/SA C CVTC/RR T(5023 SPT 2) 13
* -531203MU265 (1 265 D 627), Nitrogen Supply to Component Cooling J Water Surge Tank 1003A (Dwg.: 401278503/G 5) Valve Mfg.: Kerotest 3 AC 1 CK/SA C AT/RR T(5023 SPT 2) 13 3 . AC 1 CK/.SA C.: CVTC/RR T(S023SPT2) 13
- S31203MU266 .(1 266 D 627), Nitrogen Supply to Component Cooling Water Surge Tank T0048 (Dwg.:'40127S503/D 5) Valve Mfg.: Kerotest 3 AC 1 CK/SA C~ AT/RR T(S023 SPT 2) 13 3- AC 1 CK/SA- C CVTC/RR T(5023 SPT 2) 13
* $31203MU267 '(1+267 D 627), Nitrogen Supply to component Cooling Water Surge Tank T004B
'(Dwg.: 40107B503/D 5) Valve Mfg.: Xerotest 3 . AC 1 CK/SA C. AT/R'l T(5023 SPT 2 13 2 AC ) CK/SA C CVIC/RR T(5023 SPT-2 13
- S31203MU268 (1268 D 627), Nuclear Plant Service Water Supply to CCW Loop A (Dwg". : 40127BS03/0 3) Valve Mfg.: Ancher Darling
-3 AC 1 CK/ SA 6 AT/RR T(S023-SPT 2) 3 AC 1 CK/SA C- CVTC/RR T(S023SPT-2) ,
S31203HU269 (1269 D 627), Nuclear Plant Servico Water Supply to CCW Loop B (Dwg.: 40127BS03/B 3)- Valve Mfg.: Anchor Darling Os -
-3 .AC 1 CK/SA C AT/RR T(5023-SPT 2) 3 AC - 1 CK/SA C CVTC/RR T(5023-SPT2)
ATTACHMENT 4 PAGE 14 0F S2 n, m , <.-,.-c.w.,, _ - - - , - - - i. e r e g 3-- w .,,-r -g. 1 -r y 1 y
NUCLEAR ORGAN!ZATION ENGlHEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 106 0' .,o ATTACHMENT 4 (m,)- TCN 7 - LQ,, v LWlu 10/16/91 Inservice Tetting Program for Valves San Onofre Nuclear Generating Station (ht,tOrg's: M. Maintenance. 0 = Operations, T = Technical) Discussion of Cold Shutdow'i intervals, see Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
** System: Condensate end Feedwater
- 3HV1105, S/G E089 Feedwater Bypass Valve (Dwg.: 40!568503/B 6) Valve Mfg.: Copes Vulcan, Inc.
B 6 -GA/A0 C B1C/CS 10 0 S023 3-3.31 3
+ B 6 GA/A0 C FSTC/CS 0 S023 3 3.31 3
- B 6 GA/A0 C PIT /RR 0 5023 3 3.31 3
- 3HV1106, S/G E0BB Feedwater Bypass Valve (Dwg.: 40156BS03/E 6) Valve Mfg.: Copes Vulcan, Inc.
- B 6 GA/A0 C B1C/CS 10 0 S023 3 3.31 3 B 6- Gs,/A0 C FSTC/CS 0 5023 3-3.31 3
, {q j
- B 6 GA/A0 C PIT /RR 0 5023 3-3.31 3
- 3HV4047, Feedwater Block Valve Steam Generator E088 (Dwg.: 40156B503/F 4) Valve Mfy.: WKM
- B 20 GA/EH 0 BTC/CS 10 , 0(5023 3-3.31) 3&5.
B 20- GA/EH 0 plt /RR 0(5023-3 1.31) 3&S
- 3HV4048, Feedwater Isolation Valve Steam Generator E088 (Dwg.: 40156BS03/F-2) Valve Mfg.: WKM 2 B 20 GA/EH 0 BTC/CS 10 0(5023-3 3.31 3&5 2 B 20 GA/EH 0 FSTC/CS _0(S023 3 3.31 315 2 B 20 GA/EH 0 PIT /RR 0(5023 3 3.31 3&5
- 3HV4051, Feedwater Block Valve Steam Generator E089 (Dwg.: 40156BS03/B 4) Valve Mfg.: WKM
- B 20 GA/EH 0 BTC/CS 10 0(5023 93.31) 3&S
- B 20 GA/EH 0 PIT /RR 0(5023 3-3.31) 3&5
- 3HV4052, Feedwater Isolation Valve - Steam Generator E089 (Dwg.: 401568503/B 2) Valve Mfg.: WKM 2 B 20- GA/EH 0 B1C/CS 10 0 5023 3 3.31) 3&S 2 B 20 GA/EH 0 FSTC/CS 0 S023 3-3.31) 3&5 2 8 20 GA/EH 0 PIT /RR 0 S023 3 3.31) 3&S
$31305MUO36 (20-036-C 609), Main feed Check Valve at Steam Generator -s E089
( ) (Dwg.: 40141AS03/C-7) Valve Mfg.: Anchor / Darling V 2 C 20 CK/SA 0 CVTC/RR M(5023 1-6.160) 1&lB VRR-20 2 C 20 CK/SA 0 CVT0/CS O(Later) 1&lB VRR-20 ATTACHMENT 4 PAGE 15 0F 52
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V 3.5 UN!15 2 AND 3 REVISION 7 PAGE 107 0F 208 ATTACHMEN1 4 ry ( j TCN 7 - I fL UNIT 3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M Maintenance. 0
- Operations. T = Technical)
Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S3130bHU124 (6 124 C 599), AFW Check Valve at Steam Generator E089 (Dwg.: 40141AS03/B 7) Valve Mfg.: Anchor / Darling 2 C 6 CK/SA C CVT0/CS 0(5023 3 3.31.2) 5
- S31305Mul29 (20 129 C 609), Main Feed Check Valve at Steam Generator E088 (Dwg.: 40141AS03/F 7) Valve Mfg.: Anchor / Darling 2 C 20 CK/SA 0 CVTC/RR M(5023 1 6.160) 1&l8 VRR 20 2 C 20 C/,/SA 0 CVT0/CS O(Later) 1&l8 VRR 20
- S31305MU448 (6 448 C 599), AFW Check Valve at Steam Generator E088 o (Dwg.: 40141A503/F-7) Valve Mfg.: Anchor / Darling Q 2 C 6 CK/SA C CVT0/CS 0(5023 3 3.31.2) 5
** System: ContainmentHVAC(Normal)
- 3HV9821, Isolation Valve Containment Minipurge Supply .
(Dwg.: 40171AS03/B 5) Valve Mfg.: Fisher 2 A 8 BTF/A0 0 AT/0P T(S023V3.13) 3&l0
? A 8 BTF/A0 0 BTC/0P 5 0 S023 3 3.30) 3&l0 2 A 8 BTF/A0 0 FSTC/0P O S023 3-3.30 3&l0 2 A 8 BTF/A0 0 PIT /RR 0 S023-3-3.30 3&l0
- 3HV9823, Isolation Valve - Containment MMipurge Supply (Owg.: 40171AS03/B-4) Valve Mfg.: Fisher 2 A 8 BTF/A0 0 AT/0P T(5023 V 3.13) 3&lo 2 A 8 BTF/A0 0 BTC/0P 5 0 S023 3 3.30 3&l0 2 A 8 BTF/A0 0 FS1C/0P 0 5023 3 3.30 3&l0 2 A 8 BTF/A0 0 PIT /RR 0 S023 3 3.30 3110
- 3HV9824, Isolation Valve - Containment Minipurge Exhaust (Dwg.: 40171AS03/D 3) Valve Mfg.: Fisher 2 A 8 BTF/A0 0 AT/0P T S023 V 3.13) 3&l0 2 A 8 BTF/A0 0 BTC/0P 5 0 S023 3 3.30) 3&l0 2 A 8 BTF/A0 0 FSTC/0P O S023 3 3.30' 3&lo 2 A 8 BTF/A0 0 PIT /RR 0 S023 3 3.30) 3&l0 ATTACHMENT 4 PAGE 16 0F 52 L
l l l NUCLEAR ORGANIZMION ENGINEERING PROCEDURE 5023 V 3.5 l UNITS 2 AND 3 REVISION 7 PAGE 108 0F 208 m ATTACHMENT 4 TCN ___7 - 1 g MIL 1 l 10/16/91 Inservice Testing Program for Valves l San Onofre Nuclear Generating Station ! (Test Org's: M Maintenance. 0 = Operations T = inchnical) i Discussion of Cold Shutdown Intervals, See Next Att. l Valve Test Notes and l i See and Type Test Valve Code X1 Size Actuator Norm and Str. Organization Relief I ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
- 3HV9825, Isolation Valve Containment Minipurge Exhaust (Dwg.: 40171AS03/0 7) Valve Mfg.: Fisher 2 A 8 BTF/A0 0 AT/0P T S023 V 3.13 3&l0 2 A 8 BTF/A0 0 BTC/0P 5 0 5023 3 3.30 3&l0 2 A 8 BTF/A0 0 FSTC/0P 0 5023 3 3.30 3&l0 2 A 8 BTF/A0 0 PIT /RR 0 S023 3 3.30 3&l0
- 3HV9948, containment Purge Supply (Dwg.: 40171AS03/B 6) Valve Mfg.: Fishu 2 A 42 BTF/A0 C AT/0P T(5023 V 3.13) 3&l0 2 A 42 BTF/A0 C BTC/CS 12 0(5023 3-3.31) 3&l0 3&l0
') 42 0(5023 3 3.31) ^ 2 A BTF/A0 C FSTC/CS
-(
- 3HV9949 Containment Purge Supply (Dwg.: 40171A503/0 4) Valve Mfg.: Fisher 2 A 42 BTF/MO C AT/0P T(5023 V 3.13) 3,6&l0 2 A 42 BTF/MO C BTC/CS 12 0(50233-3.31). 3,6&lo .
- 3HV9950, Containment Purge Exhaust (Dwg.: 40171AS03/C 3) Valve Mfg.: Fisher 2 A 42 BTF/MO C AT/0P T(5023-V-3.13) 3,6&l0 2 A 42 BTF/M0 C BTC/CS 12 0(S023-3 3.31) 3,6&l0
- 3HV9951, Containment Purge Exhaust (Dwg.: 40171AS03/C 6) Valve Mfg.: Fisher 2 A 42 BTF/A0 C AT/0P T S023 V-3.13) 3&lo 2 A 42 BTF/A0 C BTC/CS 12 0 5023 3 3.31) 3&l0 2 A 42 BTF/A0 C FSTC/CS 0 S023 3 3.31) 3&l0
** System: Containment Spray
- 3HV8150, Isolation Valve 30C5 Heat Exchanger E004 to LPSI Header (Dwg.: 40ll4BS03/E 5) Valve Mfg.: Walworth ,
2 B 10 GL/MO C BTC/CS 90 0(S023 3-3.31) 6 2 B 10 GL/MO C BT0/CS 90 0(5023 3 5.31) 6 2 B 10 GL/M0 C PIT /RR 0(5023-33.31) 6 ATTACHMENT 4 PAGE 17 0F S2 i
_ . - .- . . . ~ -. - _ -. . .- .- . -.- . . - - i
-NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 PAGE 109 0F 208 l
- UNilS 2 AND 3 P.EVISION 7 ATTACHMENT 4 TCN 7-ja UNIT 3 10/16/91 Inservice Testing Prograin for Valves San Onofre Nuclear Generating Station i
-(TestOrg's: M. Maintenance. 0 = Operations. T = Technical)
Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and ' See and Type Test Valve ' Code XI Size Actuator Norm and Str. Organization Relief Class-Cat (in.) Type Pos. Mode Time (Procedure) Requests
*' 3HV8151, Isolation Valve SOCS Heat Exchanger E003 to LPS! Header (Dwg.: 40114BS03/F-5) Valve Mfg.: . Walworth 2 B 10 GL/MO C -BTC/CS 90 0 S023 3 3.31 6 2 B 10. GL/MO C BT0/CS 90 0 5023 3 3.31 6 '
2 B 10 GL/MO C PIT /RR 0 5023 3-3.31 6
- 3HV9367, Containment Isolation MOV Spray Header #1 ,
-(Dwg.: 40114B503/C4)ValveMfg.: Target Rock
'2 ' A 8- GA/MO C AT/RR T S023 V 3.13 3,6&l0 2 A_ 8 - GA/M0 C BT0/0P 12 0 S023-3-3.30 3,6&lo 2 'A 8 GA/M0 C PIT /RR 0 5023 3-3.30 3,6&l0
- 3HV9368, Containment isolation MOV Spray _ Header #2 V- (Dwg.:-40ll4BS03/G-4) Valve Mfg.:- Target Rock 2 A_6 GA/MO C AT/RR T S023-V 3.13 3,6&l0 2 ~A- 8 GA/MO C BT0/0P_-12 0 5023 3 3.30 3,6&l0 2 :A-8 - GA/MO- - C- -PIT /RR 0 5023 3 3.30 3,6&l0 ,
- S31206MU004 - (8 004 C-406), Spray Header #1 Containment Isolation Stop-Check-Valve-l(Dwg.: 40114BS03/C 3) Valve Mfg.: Anchor / Darling _
2 AC 8- SCK/SA C- AT/RR- T(5023-V-3.13): 1,5,8,10&l8 .
- VRR-13 j
- 2 AC'.8 SCK/SA C CVP0/RR T(M.O.). 1,5,8,10&l8 :
VRR 13 2 AC 8 - SCK/SA C CVT0/RR M(RMO)- 1,5,8,10&l8 VRR
- S31206MU006 (8 006 C 406), Spray Header #2 Containment Isolation '
.Stop Check Valve - .
-(Dwg.: 40ll4BS03/G 3) Valve Mfg.:' Anchor / Darling 2 AC 8 SCK/SA C- _AT/RR- T(S023 V 3.13)- - 1,5,8,10&l8 VRR-13 2_ AC. 8 SCK/SA C- CVP0/RR T(M.O.) 1,5,8,10&l8 VRR-13 2 -AC 8 SCK/SA C 'CVT0/RR M(RMO) 1,5,8,10&l8 VRR 13 c.
~
ATTACHMENT 4 PAGE 18 0F 52
+w,' , > , , ~ - .. re, .,,,~,%..-...,,,,,,..,....-,e- .,m- r,----r-,_ ry .-..c- -
.# .m-.. ..,,,,,,e .- , -,.. -
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UltiTS 2 AND 3 REVISION 7 PAGE 110 0F 200 ATTACHMENT 4
~
() TCN 7=1a_ \v' PKlL1 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Haintenance 0 Operations T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in,j Type Pos Mode Time (Procedure) Requests
- S31206MU0 0 (2 010 C 329), Containment Spray Pump 3P012 Miniflow Stop Check Valve (Dwg.: 40ll4AS03/D 3) Valve Mfg.: Rockwell Edwards 2 C 2 SCK/SA C CVT0/0P T(5023V3.5.4)
- S3120SMU0ll (2 Oll-C 329), Coctainment Spray Pump 3P013 Miniflow Stop Check Valve (Dwg.: 40ll4AS03/H 3) Valve Mfg.: Rockwell Edwards 2 C 2 SCK/SA C CVT0/0P T(5023 V 3.5.4)
- S31206Mb012 (8 012 C-406), Spray Pump 3P012 Discharge Stop Check Valve (Dwg.: 40ll4A503/C-3) Valve Mfg.: Anchor / Darling
(] 2 C- 8 SCK/SA C CVTC/C9 0 5023 3 3.31.2 5 V- 2 C 8 SCK/SA C CVT0/C5 0 5023 3 3.31.2 5
- S31206MU014 (8 014-C 406), Spray Pump 3P013 Discharge Stop Check Valve (Dwg.: 40ll4AS03/G 3) Valve Mfg.: Anchor / Darling 2 C 8 SCK/SA C CVTC/CS 0 5023 3 3.31.2) 5 2 C 8 SCK/SA C CVT0/CS 0 5023 3 3.31.2) 5
* (8 029 C-645), Spray Pump 3P012 Discharge to SDCS HV S31206MUO29 E004 Check Valve (Dwg.: 40ll4AS03/C-2) Valve Mfg.: Anchor / Darling 2 C 8 CK/SA C CVTC/RR 0(5023 3 3.31.2) 5 2 C 8 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5
- S31kJ6MUO30 (8 030 C 645), spray 1p 3P012 Discharge to SDCS HV E003 Check Valve (Dwg.: 40ll4AS03/G 3) Valve Mfg.: Ancho' Oarling 2 C 8 CK/SA C CVTC/RR 0(S023-3-3.31.2) 5 2 C 8 CK/SA C CVT0/CS O(5023-3 3.31.2) 5
** System: Diesel Fuel 011
*- S32421MUO39 (2 039 D 627), Diesel Fuel Oil Transfer Pump 3P096 Discharge Check Valve (Dwg.: 40ll6A503/C 6) Valve Mfg.: Kerotest 3 C 2 CK/SA C CVT0/0P T(5023-V3.5.4) r q -
ATTACHMENT 4 PAGE 19 0F 52
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 111 0F 208 , ATTACHMENT 4 '
, ,\ TCH 7-16
( ) ~ LEll ) 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M. Maintenance. 0 Operations. T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organizatlon Relief ClassCat(in.) Type Pos. Mode Time (Proceduie) Requests
- S32421MUO48 (2 048 D 627), Diesel fuel Oil Transfer Pump 3P093 Discharge Check Valve (Dwg.: 40116AS03/D7)ValveMfg.: Kerotest 3 C 2 CK/SA C . CVT0/0P 1(5023 V 3.5.4)
- S32421MUO54 (2 054 D 627), Diesel Fuel Oil Transfer Pump 3P095 Discharge Check Valve (Dwg.: 40116A503/C 3) Valvin Hfg.: Kerotest 3 C 2 CK/SA C CVT0/0P T(5023 V 3.5.4)
S32421MUO63 (2 063-D 627), Diesel Fuel Transfer Pump 3P094 Discharge Check Valve
\ (Dwg.: 40ll6AS03/D 4) Valve Mfg.: Kerotest (d 3 C 2 CK/SA C CVT0/0P T(5023 V 3.5.4)
**-System: Diesel Generator Air Start
- 3HV5931A. Diesel Generator 3G002, 20 Cyl., Air Start Relay Valve
-(Dwg.: 40110AS03/E-1) Valve Mfg.:. Later 3 B GL/A0 C BT0/0P 10 -0(5023-3 3.23) 17
- 3HV59318, Diesel Generator 3G002,16 Cyl., Air Start Reisy Valve (Dwg.: 40110BS03/E-2) Valve Mfg.: Later 3 B GL/A0 C BT0/0P 10 0(5023-3 3.23) 17
- 3HV59310. Diesel Generator 3G002, 20 Cy)., Air Start Relay Valve (Dwg.: 40110AS03/E 2) Valve Mfg.: Later 3 B GL/A0 C BT0/0P 10 0(S023-3 3.23) 17
- 3HV59310, Diesel Generator.3G002, 16 Cyl., Air Start Relay Valve (Dwg.: 40110BS03/E-1) Valve Mfg.: Later 3 8 GL/A0 C BT0/0P 10 0(S023 t 3.23) 17
- 3HV5931E, Diesel Genera, tor 3G003, 20 Cyl., Air Start Reley Valve (Dwg.: 40110CS03/E-1) Valve Mfg.: Later 3 8 GL/A0 C BT0/0P 10 0(3023 3-3.23) 17
- 3HV5931F, Diesel Generator 3G003,16 Cyl., Air Start Relay Valve
/ (Dwg.: 40110DS03/E 2) Valve Mfg.: Later
, . V) 3 B GL/A0- C BT0/0P 10 0(S023-3-3.23) 17 ATTACHMENT 4 PAGE 20 0F 52
NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023 V 3.5 i UNITS 2 AND 3 REVISION 7 PAGE 112 0F 208 , l ATTACHMENT 4 Tr.N 7-16, l Lt(11.3 - ! 10/16/91 Inservice Testing Program for Valves l San Onofre Nuclear Generating Station (Test Org's: M. Maintenance. 0 = Operations, 1 Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and ' See and Type Test Valve Code XI Size Attuator Norm and Str. Organization Relief- ! Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- 3HV5931G, Diesel Generator 3G003, 20 Cyl., Air Start Relay Valve (Dwg.: 40110CS03/E 2) Valve Mfg.: Later 3 -B C BT0/0P 10 0($023 3 3.23) 17
.GL/A0
* -3HV5931H, Diesel Generator 3G003, 16 cyl., Air Start Relay Valve :
(Dwg.:-40110D503/E 1) Valve Mfg.: later 3 -B GL/A0 C BT0/0P 10 0(5023 3 3.23) 17 !
- 3HY5955Al', Air Start Sol. Diesel Generator 30002, 20 Cyl., Right Bank
-(Dwg.: 40110AS03/E 1) Valve Mfg.: MKW '
NA B. 3 Way/SO.C BT0/0P 10- 0(5023 3-3.23) 47 [
'V
- 3HYS955Bl. Air Start 501. Diesel Generator 3G002,16 Cyl., Left Bank '
(Dwg.: 40110BS03/E-2) Valve Mfg.: MKW NA. B- 3 Way/50 C BT0/0P' 10 - 0(5023-3-3.23) 17
- 3HY5955C1, Air Stirt 501. Diesel Generator 3G002, 20 Cyl., Left Bank .
(Dwg.: 40110A503/E 2)~ Valve Mfg.: MKW NA B 3 Wsy/SO C' BT0/0P 10 0($0233-3.23) 17 , 3HY5955Dl / Air Start Sol. . Diesel Generator 3G002,16 Cyl., Right Bank (Dwg.: 40110BS03/E 1) Valve Mfg.:- MKW NA- B 3 Way/50 C BT0/0P 10 0(S023-33.23) 17
- 3HYS955E2, Air Start Sol. - Diesel Generator 3G003, 20 Cyl., Right Bank (Dwg.': 40110CS03/E 1)-Valve Mfg.:- MKW
'NA B 3 Way/50 C BT0/0P 10 0(50233-3.23) 17 1 '*
3HYS955F2, Air Start Sol. -- Diesel Generator 3G003,16 Cyl., left Bank l (nwg.: 40110DS03/E 2) Valve Mfg.-: MKW - !
.NA B 3.Way/SO C BT0/0P 10 0(5023-3 3.23) 17 l- -:* 3HY5955G2, Air Start 501. .
Diesel Generator 30003, 20 Cy1., Left Bank l (Dwg.: 40110C503/E 2) Valve Mfg.: MKW L NAs B 3 Way/$0 C BT0/0P 10 0(S023-3-3.23) 17 3HY5955H2, Air Start 501. - Diesel Generator 3G003,16 Cyl., Right Bank ' i .N Y a S bf0P 0 0(S023 3-3.23) 17 1 ATTACHMENT 4 PAGE 21 0F 52 ,
. , ~ _ - - - L _- - . . . _ . - . - , - . - - _ - - - -
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISICN 7 PAGE 113 0F 208 ATTACHMENT 4 c TCN 7.i_g AllC 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance, 0 Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Orp nization Relief Class Cat (in.) Type .Pos. Mode Time (Procedute) Requescs
** System: Diesel Generator System .
- 532420MU135 (1 1/2 135 D *), Diesel Air Receiver T-277 Air Inlet Check Valve (Dwg.: 40110CS03/G 3) Valve Mfg.: Later C 1 1/2 CK/SA C CVTC/0P 0(502333.30)
* $32420Mul46 (11/2146 D *), Diesel Air Receiver T 274 Air Inlet Check Valve (Dwg.: 40110A503/H 1) Valve Mfg.: Later C 1 1/2 CP/SA C CV(C/0P 0(S023-3 3.30)
- S32420MU160 (1 1/2-160 0 *), Diesel Air Receiver T 275 Air inlet (d' Check Valve (Dwg.: 40110AS03/G 3) Valve Mfg.: Later C 11/2 Cr/SA C CVTC/0P 0(5023-3 3.30) +
- S32420Mul68 (1 1/2168 D *), Diesel Air Receiver T-276 Air inlet Check Valve (Dwg ., : 40110CS03/H 1) Valve Hfg.: Latsr C 1 1/2 CK/SA C CVYC/0P 0(5023-3-3.30) ,
** System: Fire Protection
- 3HV5686, Containment Isol. Fire Protection (Outside Containment)
(Dwg.: 401890503/D 3) Valve' Mfg.: WKM 2 A 4 GA/MO C AT/RR T(5023 V 3.13) 3&lo 2 A 4 GA/MO C BTC/CS 33 0(5023 3 3.31) 3&l0 2 A- 4 GA/MO . C PIT /RR 0(S023 3 3.31) 3&lo
- SA230lMUO95, Containment 1 sol. Fire Protection (Inside Containment)
(Dwg.: 40189B502/D 4) Valve Mfg.: Anchor / Darling.
? AC 4 CK/SA C AT/RR T(5023 V 3.13) 10
** System: Fuel Stor. Pool & Refueling
- 3LV02270, RWST to Charging Pump Suction
, (Owg.: 40124BS03/A-7) Valve Mfg.: Target Rock Il V
2 B 4 4 GA/MO C BIO /CS 11 0(5023 3-3.31) S&6 2 B GA/MO C PIT /RR 0(S023-3-3.31) S&6 ATTACHMENT 4 PAGE 22 0F 52
t
.NUCl. EAR ORGANIZATION ENGINEERING PROCEDURE $023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 114 0F 208 ATTACHMENT 4 .(
TCN .7 16 UNIT.3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M. Maintenance. 0 = Operations T = Technical) Discussion of Cold Shutdown Intervals, see Next Att. , Valve Test- Notes and See and Type Test Yalve Code XI Size Actuator Norm and Str. Org/whation Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
* $31219MU052(6052C675),RWST1006toChargingPumpSuctionHeader 2(Dwg.: C 40124B503/87)ValveMfg.:
6 CK/SA C -CVT0/CS Aloyco/Walworth 0(502333.31.2) 5
- S31219HU100 (10100.C rT2), Refueling Pool Outlet inside Containment *
(Dwg.: 40122A503/G4)ValveMfg.: Walworth 2 A 10 C AT/RR T(5023V3.13) 10 GA/M
- S31219MU101 (10 101 C 212), Refueling Pool Outlet Outside Containment to Pump 2P014-(Dwg.: 40122A503/G4)ValveMfg.: Walworth +
2 AL 10 GA/M- C AT/RR T(5023 V 3.13) 10 A(v) ** System: Gas Radwaste
- 3HV7258. Containment Isolation Waste Gas from Contmt'to surge Tank
=(Dwg.: 4J31A503/F 3) Valve Mfg.: WKM 2 A. 4 GA/MO O AT/RR .
T($023 V 3.13 -3,6&l0 < 2 A .3 GA/MO- 0 BTC/0P 31 0(5023 3-3.30 3,6&l0 2 A 3- GA/MO O PIT /RR 0(5023 3 3.30 3,6&l0
* :3HV7259, (trtainment Isolation Safety injection Tank Vent' Header .
-(Dwg.: 40131AS03/F-2) Valw Mfg.: Fisher 2 A' :3 GA/AO- 0. AT/RR T(5023 V 3.13 3&l0
-2 .A 3- GA/A0 0 BTC/0P 5 0(5023-3 3.30 3110
-2 A .3 GA/A0 0 FSTC/0P 0(S023 3 3.30 3&lo 2 A '3 GA/A0 0 PIT /RR 0(502333.30) 3&lo
- ** System: Liquid'Radwaste
~
- L3HV7512, RCDT' Pump Discharge From Containment to Rsd Waste (Dwg.: = 40131AS03/B 3) Valve Mfg.: .WKM 2 A3 GL/M0 C AT/RR T S023 V 3.13) 3,6&l0 L 21 A. 3 GL/MO C BTC/0P 17 0 5023-3 3.30) 3,6&l0 L 2 A~ 3 GL/MO C PIT /RR 0 5023 3 3.30) 3,6&l0 i
ATTACHMENT 4 PAGE 23 0F 52 L
._. - _ _ _ . _ ~ _ . . _ _ . . _ _ _ _ __ __m _ _...__ _ . _
r .
~-
4 NUCLEARORGANYZATION LHdlNEEFJNG PROCEDURE 5023 V 3.5 UNITS 2 AND 3 - RWISION 7 PAGE !!S OF 208
' ATTACHMENT 4 !
TCN 7
- M.
mu 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating $tation : (Test Org's: H Maintenance. 0 - Operations T = 19chnical) ; Df stussion of Cold Shutdown Intervals, See Nut Att. t Valve Test Notes and ! Scc . and Typo Test Valve Code XI Stre Acuator Nor:a and Str. Organization Relief i Requests j
.ClassCat(in.). Type Pos. Mode Time (Procedure)
- 3HV7513, Containment Isolation RCS Drain to Radwaste !
(Dwg.: 40131ASM/B-2) Valve Mfg.: Fisher 2 A 3 GL/A0 C AT/RR T S023 V 3.13 3&10: ' 2 A 3- GL/A0' C BTC/0P 7 0 5023 3 3.30 3&l0 2 -A 3 GL/A0 C- FSTC/0P 0 5023 3 3.30 3&l0 F 2 A 3 C PIT /RR 0 5023 3 3.30 3110
. GL/A0 '
- S31901MU321 (2 321.C 376), Isolation Yalve Coolant Polishir; Demin to Quench Tank (Dwg.: 40lllCS03/G 6) Valve Mfg.: Kerotest 2- A 2 GL/M C AT/RR T(5023-V3.13) 10
- S3190lMU573 (2 573 C 611),-- Check Valve Cint Pol Demin to Quench Tank i O'.
(Dwg.: 40111CS03/G5)ValveMfg.: Kerotest- . 2 AC 2 CK/SA C AT/RR' T(5023 V 3.13) 10
** Systa: ' Nitrogen Gas
- 3HV5434, Nitrogen to Safety injection Tanks 2(Dwg.:-40192CS03/D6)ValveMfg.:-Fisher A 2. GL/A0-. C AT/RR T S023 V-3.13 3&lo
-2 A 2 Gl/A0 -C BTC/0P 4 0 S023 3-3.30 3&10l
- 2 'A,-2 OL/A0 C FSTC/0P O S023 3 3.30 3&lo 2- 1A 2 - GL/AO: C- PIT /RR 0 5023 3 3.30 3110
'* 3HV51.*7, Nitrogen-Supply to Containment
-(Dwg.: 40192CS03/F5)ValveMfg.: Fisher '
2 A 3/4 GL/A0- 0 AT/RR. T S023 V-3.13 3&lo L 2. A 3/4 GL/A0 0 BTC/0P 2 0 5023 3 3.30 3&l0 L - 2 _. A 3/4; GL/AO- 0 FSTC/0P O S023 3 3.30 3&l0 ' L '2' A 3/4 GL/AO~ 0 PIT /RR 0 5023-3 3.30 3&lo l
.. ' ' S32418MU002 (3/4 002-C 611), Nitrogen Supply to Containment
-(Dwg.: 40192CS03/E5}:ValveMfg.: Kerotest
;2 ACE 3/4 CK/SA C- -AT/RR T(S023-V3.13) 10
- S32418MU108 :(2-108 C-627), Nitrogen Supply to Safety injection Tanks L Check Valve l- (Dwg.: 40192CS03/C-6)ValveMfg.: Kerotest
! 2 ' AC 2 'CK/SA C- 'AT/RR T(S023 V 3.13) 10 i ATTACHMENT 4 PAGE 24 0F 52 H
.. ._,...L...Ja.._.-...,-,m, . . - . . .
-_.-.__-___.-,,.m..[..t__,.-,,,-.__=
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 REVISION 7 PAGE 116 0F 208 UNITS 2 AND 3 ATTACHMENT 4 TCN 7-in. -{o } unu 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: H. Maintenance. 0 = Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Test Notes and Yalve and Type Test . Valve See Str. Organization Relief Code XI Size Actuator Norm and Requests Class Cat (in.) Type Pos. Mode Time (Procedure)
** System: Nuclear Sampling
- 3HV0500. Post LOCA Hydrogen Monitor (Dwg.: 40172AS03/C 3) Valve Mfg.: Target Rock 2 A 1 GA/SO C AT/RR T(S023 y 3.13) 10
- 3HV0501, Post Loca Hydrogen Monitor (Dwg.: 40172AS03/D 2) Valve Mfg.: Target Rock T(5023 V 3.13) 10 2 A 1 GA/SO C AT/RR
- 3HV0502, Post Loca Hydrogen Monito'
) Valve M Taiget (Dwg.{4072ASO/
- 3HV0503 Post-Loca Hydrogen Monitor (Dwg.: 40172A503/B 2) Valve Mfg.: Target Rock 2 A 1 GA/SO C. AT/RR T(5023-V 3.13) 10
- 3HV0508 RCS Hot Leg Sample Containment Isolation Valve (Dwg.: 40134AS03/T 7) Valve Mfg.: WKM 2 A 3/4 GL/MO C AT/RR T(S023 V-3.13 3,6&l0 2 A 3/4 GL/MO C BTC/0P 33 0(5023 3 3.30 3,6&l0 2 A 3/4 GL/M0 C PIT /RR 0(5023 3 3.30 3,6&l0
- 3HV0509 RCS Hot Leg Sample Containment Isolation Valve (Dwg.: 40134AS03/F 5) Valve Mfg.: Fisher 2 A 3/4 GL/A0 C AT/RR T(5023 V 3.13) 3&l0 2 A 3/4 GL/A0 C BTC/0P 4 Of5023 3 3,30) 3&l0 2 A 3/4 GL/A0 C FSTC/0P 0(S023-3-3.30) 3&l0 2 A 3/4 GL/A0 C. PIT /RR 0(5023-3-3.30) 3&l0 .
- 3HY0510, Pressurizer Yapor Sample Containment Isolation Valve '
(Dwg.: 40134AS03/E 7) Valve Mfg.: WKM
? A 3/4 GL/MO C AT/RR T(5023 V 3.13) 3,6&l0 2 A 3/4 GL/MO C BTC/0P 24 0(5023 3-3.30 3,6&l0 2 A 3/4 GL/MO C PIT /RR 0(5023 3-3.30 3,6&l0 0
ATTACHMENT 4 PAGE 25 0F 52 1 1
1 NUCLLAR ORGANIZATION' ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVIS!(,N 7 PAGE 117 0F 208 y NT 4 Q ATTACHM(e~16 (CLi Unll.1 10/16/91 Inservice Testing Program for Valves San Onofra Nuclear Generating Station . (TestOrg's: M' Maintenance, 0 = Operations, T = Technical) Discussion of Cold $hutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
- 3HV0511. Pressurizer Vapor Sample Containr.3nt Isolation Valve
., (Dwg.: 40134AS03/E 5) Valve Mfg.: Fisher
.2- A 3/4- GL/A0 C- AT/RR 3&lo 2 A 3/4 GL/A0 .C BTC/0P 5 Tq(S023V3.13 0 5023 3 3.30 3&lo 2 m 3/4- GL/AO' C FSTC/0P 0(5023-3 3.30 3&l0 2 A 3/4 GL/A0 C PIT /RR 0(S023 3 3.30 3&lo
- 3HV0512, Pressuriter Surge Line Sample Containment Isolation Val m (Dwg.:-40134AS03/C7)ValveMfg.: WKM 2 A l3/4- GL/MO C AT/RR T S023 V 3.13 3,6&l0 2 A 3/4 GL/MO C BTC/0P 31 0 5023-3 3.30 3,6810 0 A 3/4 GL/MG C PIT /RR 0 5023 3 3.30 3,6&l0
- 3HV0513, Pressurizer Surge Line Sample Containment Isolation Valve (Dwg.: 40134AS03/C 6) Valve Mfg.: Fisher 2 A 3/4 GL/A0 C AT/RR .T S0 3 V 3'.13 3&lo 2 A 3/4 GL/A0 C LTC/FP 5 0 5023-3 3.30 3&l0 2- A 3/4 GL/A0 C FSTC/0P 0 $023-3 3.30 3&lo o o '2 A 3/4- GL/A0 C PIT /RR 0 5023 3 3.30) 3&lo
- 3HV0514,-Isolation Valve Quench-Tank to Waste Gas System (Dwg.: 40lllCS03/F 3) Valve Mfg.: WKM 2 A 3/4 GL/MO- 0 AT/RR T(5023 V "1.13 3,6&l0 2 A 3/4' GL/MO O BTC/0P 31 0 S023 3 3.30 3,6&l0 A 3/4- GL/MO 0 PIT /RR 0 5023 b 3.30 3,6&l0
* -3HV0515, Isolation Valve Quench Tank /RCOT to Waste Gas Sampling Syst (Dwg.:. 40lllCS03/G 2) Valve Mfg.:- Fisher
-2. A 3/4 GL/AO- C- AT/RR -T 5023 V 3.13) 3&lo 2 A 3/4: GL/A0 .C BTC/0P 2 0 S023 3-3.30 3&l0 2 A' 3/4. GL/A0 C FSTC/0P_ 0 5023-3 3.30 3&lo 2 A 3/4 GL/A0 C PIT /RR 0 S023 3 3.30 3&l0
* -3HV0516, Isolation Valve RCDT to Waste Gas Sampling System (Dwg.: 40111CS03/G 3) Valve Mfg.: WKM
'2 A- 3/4 GL/MO O AT/RR T(S023 V 3.13) 3,6&l0 2 A 3/4 GL/MO O- BTC/0P 25 0(S023 3 3.30) 3,6&l0 p -2 A 3/4 GL/M0 0 PIT /RR 0(5023 3 3.30) 3,6&l0 pd u
ATTACHMENT 4 PAGE 26 CT 52 L _
e NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023.V 3.5 UNITS 2 AND 3 REVISION 7 PAGE !!8 0F 208 c (q ATTACHMENT 4 TCH 7 .- 1 s_ UNIT 3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generatihg S% tion (TestOrg's: M Maintenance. 0 Oper.tions, 7 . Technical) Discussion of Cold Shutdown 13tervals, See Next Att. Valve = Test Notes and
-i-See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief C1hss Cat (in.) Type Pos. Mode Time (Procedure) Requests 1
* #2 Sample Isolation Valve
-(Dwg.:
3HiO511, RCS Hot Lef Valve Mfg.: 40134A503/G.7 WKM 3,6&l0
'2 A 3/4 GL/MO C AT/RR TS023V-3.13}_
0 S023 3 3.30, 3,6110 2 'A' 3/4 GL/MO C BTC/0P 29 PIT /RR 0 5023 3 3.3,) 3,6&lo 2 .A~ 3/4- GL/MO C
- 3HV7800. Containment Airborna Rad Monitor Train "M ! sol (Pen 308)
(Dwg.: 40170AS03/E-3).ValveMfg.: Target Rock . 2 A 3/4 GA/SO O AT/RR T S023 V 3.13) 3&l0 -
; 2 A 3/4 GA/S0 0 BTC/0P 1 0 5023-3 3.30 3&lo ,- 2 ,A 3/4 GA/SO -0 FSTC/0P- 0 S023 3 3.30 3&l0 2 A -
3/4 GA/50 0 PIT /RR 0 5023 3-3.30 3&l0 a V. A
*- 3HV7801. Containment- Airborne Rad Monitor Train "A* 1s01 (Pen 308)
. (Dwg.: 40170A503/E-4) Valve Mfg.:-. Target Rock 2 A 3/4i GA/50 1 AT/RR T S023-V 3.13 3&l0-2 A 3/4- GA/SO O BTC/0P 1 0 S023 3-3.30 3&lo 2 A 3/4- GA/SO O FSTC/0P 0 S023-3 3.30 3110 2' E. A -3/4 GA/50 0 1 PIT /RR- -0 5073 3 3.30 - 3&lo
~
T
- 3HV7802. Containment Airborne Rad Wonitor Train "A" Isol (Pen 30A)
(Dwg.: 40170AS03/D-4) Valve Ufg.: ' it.rget Rock 2 -A 3/4 GA/30- 0 AT/RR T S023-V 3.13 3&lo 2 A 3/4 GA/SO O BTC/0P 1 0 5023-3 3.30 3&l0 2 A 3/4 .GA/50 0 FSTC/0P O S023-3 3.30 3&l0 ,
*2- _A 3/4 GA/50- 0 PIT /RR 0 5023-3-3.30 3&l0 3HV7303, Containment-Airborne Rad Monitor Train "B" Isol-(Pen 3A) -
-j* (Dwg.: 40170AS03/D-3) Valve _ Mfg.:- Target Rock 2- A 3/4 GA/50 0 AT/RR T(5023V-3.13) 3&l0
- 2 A. 3/4- GA/SO O BTC/0P 1 0(5023-3 3.30) 3&l0 2 A- 3/4 GA/50- 0- rFSTC/0P 0(S023 3-3.30) 3&l0 2 A 3/4 GA/50 s' ~ PIT /RR- 0(S023-3-3.30) 3&l0
*: 3HV7805, Containment Airborne Radiation Monitor Train "B" ^
(Dwg.: 40170AS03/C 4) Valvo Mfg.: Target Rock 2 A 3/4 GA/SO- 0 AT/RR T S023-V 3.13 3&l0 A 2 A 3/4: GA/SO O BTC/0P 1 0 5023-3 3.30 3&lo h 2 :' 2 A A; 3/4 3/4 GA/50-GA/SO
-0 O
FSTC/0P-PIT /RR
'0 S023 3 3.30 0(5023-3-3.30 3110 3&lo ATTACHMENT 4 PAGE 27 0F 52
_ - ._. _ _ 2. ._ ._ , _ _ _ _ _ - _
qp NUCLEAR OhGAy!IATION. ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AFD 3 REVISION 7 PAGE 119 0F 208 ATTACHHENT 4 Ov TCH , 7710 WIL) 10/16/91 Inservice Testing Program for Valves
!an Onofre Nuclear' Generating Station (TestOrg's: M.Haintenance. 0 = Operations. T = Technical)
Discussion of Cold Shutdown Intervals See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Acturoor Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- 3HV7806, Containment Airborne Raritation Monitor Train 'B'
.; IJrget Rock 2 (Dwg.:
A 40170AS03/C 3/4 GA/50 4)0 Valve Ai Hfg/RR T $023 V-3.13 3&l0 2 A 3/4 GA/50 0 BTC/0P 1 0 5023 3 3.30 3&l0 i 2 A 3/4 GA/SO O FSTC/0P O S023 3-3.30 3&l0 2 A 3/4 GA/SO O PIT /RR 0 5023 3 3.30 3&l0 3HV7810. Containment Airborno Rad Monitor Train "B" (Pen 160) (Dwg.: a0170A503/C 3) Valve Mfg.: Target Rock 2 A 3/4 GA/SO O AT/RR T(S023 V-3.13) 3&l0 2 A 3/4 GA/SO O BTC/0P 1 0(5023 3 3.30 3&l0 2 A 3/4 GA/SO O FSTC/0P 0(5023 t-3.30 3&lo 2 A 3/4 GA/50 0 PIT /RR 0(5023-3-3.30 3&l0 (V-)
- 3HV7811 Containment Airborne Rad Monitor Train *B' (Pen 270)
(Dwg.: 40170AS03/C 3) Valve Hfg.: Target Rock 2 A 3/4 GA/50 .O AT/RR T 5023 V 3.13) 3&lo
? e 3/4 _GA/SO O BTC/0P 1 0 S023 3 3.30) 3&l0
? .
3/4- GA/$0 0- FSTC/0P O S023 3 3.30) 3&l0 1 A 3/4 GA/50 0 PIT /RR 0(5023 3-3.30) 3&l0
- W 416. Containment Airborne Radiation Monitor Emergency Sample (Dwg.: 40170AS03/E-3) Valve Mfg.: Target Rock 2 A 3/4 GA/SO O AT/RR T S023 V 3.13 3&lo 2 A 3/4 GA/SO O BTC/0P 1 0 5023 3 3.30 M10 2 A. 3/4 GA/SO O FSTC/0P _0 5023-3 3.30 3&lo l 2 A 3/4- GA/SO O PIT /RR 0 5023 3 3.30 3&l0
** System: Nuclear Service Water
- 3HV7911, Containment Isolation Nuclear Service Water
, (Dwge: 40140BS03/F-b) Valve Mfg.: Fisher 2 A 3 GA/AO- 0 AT/RR T S023 V ?.13 3&lo 2 A 3 GA/A0 0 BTC/0P 7 0 5023-3 3.30 3&l0 i 2 A .3- GA/A0 0 FSTC/0P O S023 3 3.30 3&l0 L 2 A 3 GA/A0 0 PIT /RR 0 5023 3 3.30 3&l0
,
- S31415MU236 (3 236 C 675), Nuclear Servico Water Containment
/}
. (/
! solation Check Valve (twg.: 40140BS03/G 5) Valve Mfg.: Aloyco/Walworth q 2- AC 3 CK/SA C .AT/RR T(5023 V-3.13) 10 ATTACHMENT 4 PAGE 28 0F 52 '
l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023 V 3.5 [ ' UNITS 2 ANO 3 REVISION 7 PAGE 120 0F 200 ATTACHMENT 4 TCN 7-18, Ell _1 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M. Maintenance. 0 . Operations. T = Technical) Discussion of Cold Shutdown Intervals. See Next Att. Valve Test Notes and See and Type Test Valve l Code XI Site Actuator Norm and Str. Organization -Relief ClassCat(in.) Type. Pos. Mode Time (Procedure) Requests i
** System: Reactor Coolant
- 3HV0296A, Reactor Head Vent (Dwg.: 40lllCS03/F 6) Valve Mfg.: Target Rock 0 B 1 GL/SO C BTC/CS 5 0 5023 3 3.48 2 8 1 GL/50 C BT0/CS S 0 5023 3 3.48 '
2 8 1 GL/SO C FSTC/CS 0 S023 3 3.48 2 B 1 GL/SO C PIT /RR 0_S023 3 3.48 , 3HV02968. Reactor Head Vent (Dwg.! 40111CS03/F 6) Valve Mfg.: Target Rock 2 B 1 GL/50 C BTC/CS 5 0 5023 3 3.48 . () 2 B' 1 GL/SO C BT0/CS 5 0 S023 3 3.48 0 S023 3 3.48 (_/ 2 B. 1 GL/SO C FSTC/CS 2 B 1- GL/50- C- PIT /RR 0 S023 3 3.48 ,
* -3HV0297A, Pressurizer Vent Valve ;
r 2(Dwg,: B 40lllCS03/Ee6) 1 GL/$0 Valve C Mfg.: Tariet Rock BTC/CS 5 0 5023 3 3.48 2 B 1: ~GL/SO. C BT0/CS 5 0 S023 3 3.48 1 2 8 1: GL/SO- C FSTC/CS 0 S023 3 3.48 -
-2 B- 1 GL/SO- C PIT /RR 0 S023 3 3.48 :
* .3HV0297B, Pressurizer Vent Valve 2(Dwg.: 40111CS03/E6)ValveMfg.: GL/50 Target Rock . -
0 5023 3 3.48 B 1 C BTC/CS S 2 B 1 GL/50 C BT0/CS 5- 0 S023 3 3.48 2 B 1 GL/SO C FSTC/CS- 0 5023 3 3.48 2- B '1 GL/50 C PIT /RR 0(5023 3 3.48
. 3HV0298. Vent to'Contmt from Reactor Head / Pressurizer (Dwg. :< 49111CS03/E S). Valve Mfg.: Target Rock =
2- -B. 1 GL/SO .C BTC/CS 0 5023 3 3.48
'2 B -
'l .GL/SO^ C- BT0/CS 5 0 S023 3 3.48 2- -B 1 GL/SO C FSTC/CS- 0 S023 3 3.48 2 B 1 GL/50 C PIT /RR- 0 S023 3-3.48) uO ATTACHMENT 4 PAGE 29 0F 52'
, - - , - . . . ~ , . - - - . _ . , , , , - -_,%-- % --,, , . . _ , - , , . _ , -
_+- -
i NUCLEAR ORGANIZATION ENGINEERING PRDCIDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 121 0F 208 m AITACWLENT 4 l I TCH 7-10 v - LEll_2 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: H Maintenance. 0 Operations,1 Technical)
,1 Discussion of Cold Shutdown Intervals, See Next Att.
Valve Test Notes and See and Type Test Valve Cade XI Size Actuator Norm and Str. Organirauon Relief C' lass Cat (in.) Type Pos. Ho6e Time (Procedure) Requestr
- 3HV0299, Quench Tank Inlet from Reactor Head / Pressurizer Vent (Dwg. 401110503/E 4) Va'ive Hfg.: Target Rock 2 B 1 GL/$0 C BTC/CS 5 0 5023 3 3.48 2 B 1 GL/50 C BT0/CS 5 0 5023 3 3.48 2 B 1 GL/50 C FSTC/CS 0 S023 3-3.48 2 B 1 GL/SO C PIT /RR 0 5023 3 3.48
- 3HV9201, Regenerative Heat Exchanger E063 to Auxiliary Spray (Dwg.: 4012.tA503/C-6)ValveMfg.: WKM 3 B ? GA/MO C BTC/CS 17 0 5023-3-3.31 51.6 1 B 2 GA/MO C BT0/CS 17 0 5023 3 3.31 5&6 (q l B 2 GA/MO C PIT /RP 0 5023 3 3.31 516
- 3HV9202, Regenerative Heat Exchanger E063 to RCS Loop 2A (Dwg.: 40123AS03/E 6) Valve Hfg.: WKM 1 B 2 GA/MO O BTC/CS 23 05023-3-3.31) 6 1 B 2 GA/M0 0 B10/CS 22 0 S023 3 3.31) 6
'l B 2 GA/MO O PIT /RR 0 5023+3 3.31) 6
* -3HV9203, Regenerative Heat Exchanger E063 to RCS Loop 1A (Dwg.t 40123A503/E4) Valve Mfg.: WKH 1 8 2 GA/MO O BTC/CS 20 0 5023 3 3.31) 5 1 0 2 GA/MO O BT0/CS 20 0 5023 3 3.31) 6 1 0 2 GA/MO O PIT /RR 0 S023-3-3.31) 6
*- 3HV9204, RCS Loop 2B to Regenerative Heat Exchanger E063 (Dwg.: 40123AS03/F 6) Valve Mfg.: Fisher 1 B 2 GA/A0 0 BTC/CS 4 0(5023 3 3.31 5 1 B 2 GA/A0 0- FSTC/CS 0(S023-3 3.31 5
) B 2 GA/A0 0 PIT /RR 0(5023 3 3.31 5
- 3HV9217. RCS Bleed Off to Vclume Control Tank (Dwg.: 40124AS03/G 2) Valve Mfg.: WM 2 A- 3/4 GL/MO 0- AT/RR T S023-V 3.13 3,5,6&l0 2 A 3/4 Gl./MO O BTC/CS 15 0 S023 3 3.31 3,5,6&l0 ,
2 A 3/4 GL/MO O PIT /RR 0 S023 3-3.31 3.5,6110 ! (~) l V ATTACHMENT 4 PAGE 30 0F 52-I . _ -
y , J g
.NUCLLAR ORGANIZATION ENGINEERING PROCEDURE S023.V 3.5 UNITS 2 AND 3 REVISION 1 PAGE 122 0F 208
-,a ATTACHMENT 4
< TCH _ 7 - I n,
! )
LE1L2 10/16/91 Inservice Testing Program %r Valves San Onofre Nuclear Generating Station (TestOrg's: M. Maintenance. 0 = Operations, T = Technical) Discussion of Cold Shutdown Intervals See Next Att. Valve Test Notes and See and Type Test Yalve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- 3HV9218, RCS Bleed Off to VCT isolation Valve inside Containment (Dwg.: 40124AS03/F 3) 'lalve Mfg.: Fisher 0 AT/RR T S023 V 3.131 3,5&l0 2 A 3/4 GL/A0 3,5&lo 2 A 3/4 GL/A0 0 BTC/CS 5 0 5023-3 3.31' 2 A 0 FSTC/CS 0 5023 3 3.31 3,5&l0 3/4 GL/A0 3,5&lo 2 -A 3/4 GL/A0 0 PIT /RR 0 5023-3 3.31
- 3PSV0200 Pressurizer Safety Valve (Dwg.: 401118503/G 7) Valve Hfg.: Dresser 6 RVT/RR M(5023 1 2.1) 2 1 C SV/SA C
- 3PSV0201, Pressurizer Safety Valve (o) 1 (Dwg.: 40lllB503/G 5) Valve Mfg.: Dresser C 6 SV/SA C RVT/RR M(5023 I-2.1) 2 3TV0221 Letdown isolation Valve (Dwg.: 40123A503/F 6) Valve Mfg.: ITT 1 B U GL/A0 0 BTC/CS 4 0 5023 3 3.31) 5 1 B 2 GL/A0 0 FSIC/CS 0 5023-3 3.31 S 1 B 2 GL/A0 0 PIT /RR 0 5023 3 3.31 5
- S3120lHU019 (2 019 A 554), Auxiliary Spray Check Valve (Dwg.: 40123AS03/C 7) Valve Mfg.: Kerotest 1 C 2 CK/SA C CVT0/CS 0(50233-3.31.2) S
- S3120lHUO20 (2 020 A 554), Charging Line Check Valve to RCS L op 2A (Dwg.: 40123A503/E 7) Valve Mfg.: Kerotest 1 C 2. CK/SA= C CV10/CS 0(5023 3 3.31.2)
- S3120lMUO21 (2-021 A 554), Charging Line Check Valve to RL5 Loop 1A (Dwg.: 40123AS03/D 7) Valve Hfg.: Kerotest 1 C 2 CK/SA C CVT0/CS O(5023 3 3.31.2)
- S3120lHU129 (2-129 A 554), Auxiliary Spray to RCS From Charging Pumps (Dwg.: 40123AS03/B 3) Velve Mfg.: Kerotest 1 AC 2 CK/SA C AT/RR T(5023 V 3.13) 10 1 AC 2 CK/SA C CVT0/CS 0(5023-3 3.31.2) 10 b(
ATTACHMENT 4 PAGE 31 0F 52
t i NUCLEAR ORGANXZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3' REVISION 7 PAGE 123 Of 208 i ATTACHMENT 4 O TCN 7
- 1 fL I 1811.1 !
i 10/16/91 inservice Testing Program for Valves t San Onofre Nuclear Generating Stt. tion . (TestOrg's: M Maintenance. 0 = Operations T Technical) Discussion of Cold Shutdown Intervals, Sen Next Att. j
~!
Valve Test Notu and See and' Type Test Valve Code XI Size Actuator th .ti anri Str.; Organization Relief ;
~
ClassCat(in.)-Type Pos Mode Time (Procedure) Requests
* $3120lMU200 (14 200 C 645), Pump 3P016 Suction Check Valve (Dwg.: 40ll28503/F6)ValveMfg.: Anchor / Darling ;
2 C 14 CK/SA C~ CVTC/CS 0(502333.31.2) > 2' C 14- CK/SA C CVT0/CS 0(502333.31.2)
* ' $3120lMU202 (14 202 C 645), LPSI Pump Suction Check Valve y (Dwg.t40ll2BS03/G5)ValveMfg.: Anchor / Darling :
2 C 14 CK/SA C- CVTC/CS 0($02333.31.2) ! 2' C 14 CK/SA C CVT0/CS 0(502333.31.2)
** System: Resp. & Service Air System :
'3HV5388. Containment Isolation Valve for Instrument Air
.: Fisher 2-(Dwg.t.
A 40191GS03/G 1 1/2 GL/A0 '06) Valve A Mfp'/RR T 5023 V 3.13 3&l0 2' A 1-1/2GL/A0 0 BTC/CS 2- 0 5023 3 3.31 3&l0 t ~ A- 1 1/2 GL/A0- 0 FSTC/CS 0 5023 3 3.31 3&l0 - 2 A 1 1/2 GL/A0 0 Pil/RR 0 5023 3 3.31 3&lo
* $32417MU016- (1-1/2016C627),' Instrument.AirIsolationCheckValve
. Inside containment' ,
(Dwg.: 40191GS03/G 6) Valve Mfg.: Kerotest 2 AC. 1 1/2 CK/SA C AT/RR T(5023V3.13) 10 S32423MU017-(2 017 C 627) - Service Air Containment Isolathn Valve
.: Kerotest >
2-(Dwg.:-40191ES03/C-4)_ Valve Mfg /RR. . AC 2- CK/SA; C AT T(S023-V3.13) 10
'* S3242360055 (2 055 C 387),l Containment Isolation Valve -Service Air (Dwg.:L40191E503/C 5) Valve Mfg.: Vogt A 2 . GL/M C AT/RR~ -T(5023 V 3.13) 10
** -Systems. Safety injection
- 3HV0396,' Flow Control-Valve - LPSI Pumps to: Shutdown. Cooling System 2(Dwg.: 8: 40ll2B503/C 10 -GL/MO 3)-Valve C Mfg.:
BT0/CS 80 Borg Warner 0 5023 3 3.31 6 > 2 'B- 10 GL/MO C: Pil/RR 0 S023 3 3.31 6 ATTACHMENT 4 PAGE 32 0F-52
-..._.1 .
-y,, - , , . . . , _ m - - . . . - - . . . . , . _ . . . - . _ . . . - . . . --,a..--._u..- _ , - , -
NUCLEAN ORGANIZATION ENGINEERING PROCEDVRE 5023 V 3.5 llNITS 2 AND 3 REVISION 7 PAGE 124 0F 208 73 ATTACHMENT 4 Q TCN 7 - LfL UltiL)
")/16/91 Inservice Testir,g Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M. Maintenance. 0 = Operations. T = Technical)
Discussion of Cold ShuNown Intervals, See Next Att. Valve Test Notes and and lype Test Valve Sec Code XI Site Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
- 3HV8152, Isolation Valve SDCS Heat Exchanger E004 Inlet (Dwg.: 40112BS03/F 2) Valve Mfo.: Walworth 6
2 B -12 GA/MO C BTC/CS 100 0(5023 3 3.31) 6 2 B 12 GA/MO C BT0/CS 100 0(502333.31) 0(S0233-3.31) 6 2 B 12 bA/MO C P!T/RR
- 3HV8153, Isolation Valve SDCS Heat Exchanger E003 Inlet (Dwg.: 40112BS03/G 2) Valve Mfg.: Walworth 2 B 12 C BTC/CS 100 0 5023 3 3.31) 6 GA/MO 2 B 12 C BT0/CS 100 0 5023 3 3.31) 6 GA/MO 2 B 12 C PIT /RR 0 5023-3 3.31) 6 CA/MO V
- 3HV8160. Flow Control Valve - SDCS Heat Exchanger Bypass (Dwg.: 40ll2BS03/C 2) Valve Mfg.: Fisher 2 B 10 GL/MO O BTC/CS 40 0 5023 3 3.31 6 2 8 10 GL/MO O PIT /RR 0 S023 3-3.31 6
- 3HV8161, Block Valve - LPS! to SDCS Heat Exchanger Bypass (Dwg.: 40112B503/C 2) Valve Mfg.: Walworth 2 B 14 GA/MO O BTC/CS 105 0(S023 3-3.31) 6 2 B 14 GA/MO O PIT /RR 0(5023 3 3.31) 6
- 3HV8162 Block Valve LPSI Pump 3P015 Miniflow (Dwg.: 40112BS03/G 2) Valve Mfg.: Westinghouse, Inc.
2 B 2 GA/MO O BTC/CS 12 0(S0233-3.31) 6 2 B 2 GA/MO O PIT /RR 0(50233-3.31) 6
- 3HV8163, Block Valve LPSI Pump 3P016 Miniflow (Dwg.: 40ll2B503/D 3) Valve Mfg.: Westinghouse, Inc.
2 B 2 .GA/MO O BTC/CS 12 0(S023 3-3.31) 6 2 B 2 GA/MO O PIT /RR 0(50233-3.31) 6 ,
- 3HV9302, Control Valve Con +ainment Emerg Sump to Spray Pump 3P013 (Dwg.: 40ll2AS03/B 6) Valve Mfg.: Fisher 2 B 24 BTF/MO C BT0/0P 39.5 0(S023 3-3.30) 3&6 2 B 24 BTF/MO C PIT /RR 0(5023 3 3.30) 3&6
- 3HV9303, Control Valve Containment Emerg Sump to Spray Pump 3P012 (N (Dwg.: 40ll2AS03/B 6) Valve Mfg.: Fisher
! () 2 B 24 BTF/M0 C- BT0/0P 39.5 0(S023 3 3.30) 3&6 l l 2 B 24 BTF/MO C PIT /RR 0(S023 3 3.30) 3&6 L l ATTACHMENT 4 PAGE 33 0F $2
. . _ _ . _ . . - _ _ _ _ _ . _ _ _ . _ - _ ~ _ . _ _ _ . _ _
l NUCLEAR ORGAN!ZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGF 125 0F 208 , p ATTACHMENT 4 ) 7*16 Q TCN UNIT 3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: H Maintenance. 0 = Operations. T = Technical) Discussion of Cold Shutdown Intervals, see Next Att. Valve Test Notes and , See and Type Test Valve i Code XI Size Actuator Norm and Str. Organization Relief !
<ClassCat(in.) Type a,s Mode Time (Procedure) Requests ;
I 3HV9304.-Control Valve Containment Emergency Sump Outlet (Dwg.: 40ll2AS03/B 3) Valve Mfg.: Fisher - 2 B_ 24 BTF/MO O BT0/0P 39.5 0(S023 3 3.30) 6 21 8 24 BTF/MO O PIT /RR- 0(S02333.30) 6
*' 3HV9305, Control Valve Contair. ment- Emergency Sump Outlet !
(Dwg.: 40ll2A503/B 3) Valve Mfg.: Fisher ' 2 8 24 BTF/MO_ 0- BT0/0P 39.5 0(S023 3 3.30) 6 2 B 24 BTF/MO O PIT /RR 0(S02333.30) 6
*- 3HV9306, Isolation Valve SI Recire Return to.RWST 1005 q (Dwg.: 40114D503/D3)ValveMfg.: WKM
~B 4 tj
'~
2 GA/MO O BTC/0P 30 0(S023 3 3.30) 3&6 '
. 2_ B 4 GA/MO O PIT /RR 0(502333.30) 3&6
- 3HV9307, Isolation Valve St Recire Return to RWST T005 (Dwg.: 40114D503/B4)V41veMfg.: WKH- . f 2 B :4- GA/MO .O BTC/0P 30 0(S023 3 3.30) 3&6 .
- 2 B 4- GA/MO O- PIT /RR 0(5023 3 3.30) 3&6 .j 3HV9322 Control Valve' LPSI Header to RCS_ Loop 1A (Dwg.: 401120503/G 4) Valve Mfg.: Target Rock 2 .B 8 GL/MO C BT0/0P 16 0(5023 3 3.30) 3&6
.2 - B 8 GL/MO C- PIT /RR 0(S02333.30) 3&6
- 3HV9323, Control Valve - HPSI Header #2 to RCS Loop 1A m '(Dwg.: 40112C503/D 4) Valve Mfg.: Target Rock .
.B- 2 GL/MO C BT0/0P 15 0(S023 3 3.30) 3&6 -
2 B 2 _GL/MO C PIT /RR 0(S023-33.30) 3&6
* .'3HV9324, Control-. Valve -
.HPS! Header #1 to RCS Loop 1A ,
- (Dwg.: '40ll2CS03/D 5), Valve _ Mfg.: Target' Rock -
2 -- B' 2 GL/MO- C BT0/0P-15 0(5023 3 3.30) 3&6 - 2; B 2. GL/MO C PIT /RR 0(5023 3-3,10) 3&6 :
- 3HV9325 Control Valve LPSI Header to RCS Loop' 1B (Dwg.: 40ll2DSC3/F-4) Valve Mfg.: Tar 0et Rock 2 B 8 GL/MO C 'BT0/0P 16 0(5023 3 3.30) 3&6 O 2 8 8 GL/MO C PIT /RR_ 0(50233-3.30) 3&6 ATTACHMENT 4 PAGE 34 0F 52 i
-- ~ _ _ . .. .. .. . _ _ - , _ , _ . _ _ _ . _ . . . _ _ _ . - _ _ .__
i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V,3.5 UNITS 2 AND 3 REVISION 7 PAGE 126 0F 208 1 p ATTACHMENT 4 t] TCN 7-in_ 1 mu ' 10/16/91 Inservice Testing Program for Valves : San Onofre Nuclear Generating Station (TestOrg's: M Maintenance, 0 Operations. T = Technical) i Discussion of Cold Shutdown Intervals, See Next Att. , Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Tf:'a(Procedure) Requests *
- HPSI Header #2 to RCS Loop 1B ,
3HV9326. Control Valve '
-(Dwg.: 40112CS03/C 4) Valve Mfg.: Target Rock '
2 8 2 GL/MO C BT0/0P 15 0(5023 3 3.30) 3&6 2 B 2 GL/MO C PIT /RR 0(502333.30) 3&6
- 3HV9327, Control Valve HPSI Header #1 to RCS Loop 1B (Dwg.: 40112C503/B 5) Valve Mfg.: Target Rock
-2 B 2 GL/MO C. B10/0P 15 0 5023 3 3.30) 3&6 -1 2 B 2 GL/M'., .C PIT /RR 0 5023 3 3.30) 3&6
- 3HV9328 Control Valve LPSI Header to RCS Loop 2A G (Dwg.: 40ll2DS03/F-4) Valve Mfg.: Target Rock ,
L (") 2 2
~B-B 8
8 GL/MO GL/MO C C BT0/0P 16 0(5023-3-3.30) PIT /RR 0(5023 3 3,30) 316 3&6
'* 3HV9329, Control Valve HPSI Header #2 to RCS Loop 2A (Dwg.:-40112C503/B-4)ValveMfg.: Target Rock
.2- B- 2 GL/MO .C BT0/0P 15 0(5023 3 3.30) 3&6 2 B 2 - GL/MO -C P!T/RR 0(5023-3 3.30) 3&6 ,
- 3HV9330, Control. Valve - HPSI Header #1 to RCS Loop 2A 2(Dwg.:B 40112CS03/A 2 GL/MO
- 5) CValveBT0/0P Mfg.:- 15 Target0 Rock 5023 3 3.30 S&6 2 0 2 GL/MO C PIT /RR 0 S023 3-3.30 3&6 i
- 3HV9331-Control-Valve LPSI Header to RCS Loop 2B
, (Dwg.: 401120503/H 4) Valve Mfg.:- Target Rock
- l. 2 B- 8 GL/MO C BT0/0P 16 0(5023 3-3.30) 3&6 L J2 S 8 GL/MO C PIT /RR 0(S023-33.31) 3&6
- 3HV9332, Control Valve HPSI Header #2 to RCS Loop 2B 2(Dwg.: 40ll2CS03/F 2- 4) Valve Mfg.: Target Rock BT0/0P .15 B GL/MO C 0(5023 3 3.30) 3&6 2 B. 2 GL/MO C- PIT /RR 0(502333.30) 3&6-3HV9333 Control Valve HPS7 !.eader #1 to RCS-Loop 2B (Dwg.: Target Rock B ~40112CS03/F 2
5)C Valve BT40P Mfg.' 15 2 0(5023 3 3.30) 3&6 GL/MO L 2' B 2- GL/M0 C PIT /RR 0(5023-33.30) 3&6 g L ATTACHMENT 4 PAGE 35 0F 52
<-y-4,--,,, , .--~c m.w. , .- , -,.-m+
v +w- h- , - - , ., ,,,,,-v , p%,- .+7-4 7
f NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 : UNITS 2 AND 3 REVISION 7 PAGE 127 0F 208 l'
- ATTACHMENT 4 TCN 7-16 ,
I UNIT 3 i 10/16/91 inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance. 0 = Operations, T = Technical) 1 Discussion of Cold Shutdown Intervals, See Next Att. ! Valve Test Notes and See and- Type Test Valve Code XI~ Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- 3HV9334, Containment Isolation MOV 51 Tank Drain HDR to RFWT 2T005 i
.: WKM 2 (Dwg.: A- 40ll4DS03/F7)ValveMfg/RR 2 GL/MO C AT T S023 V 3.13 3&l0 2 A 2 GL/MO C BTC/0P !! O S023 3 3.30 3110 2 A 2 GL/MO C PIT /RR 0 5023 3 3.30 3610
- 3HV9336, Isolation Valve SDCS to LPSI Pump Suction (Dwg.: 401120503/C-7) Valve Mfg.: WKM !
2 B 16 GA/MO OC BTC/0P 80 0(S023 3 3.30 6 , .. 2 B 16 GA/MO OC BT0/0P 80 0(5023 3 3.30 6 2 B 16- GA/MO OC PIT /RR 0(502333.30 6
- 3HV9337, Isolation Valve SDCS to LPSI Pump Suction (Dwg.: 40ll2D503/C 4) Valve Mfg.: WKM 1 A 16 GA/MO 0C AT/RR 0 5023 2 1.31 1) S&6 1 A 16 GA/MG OC BTC/CS 103 0 5023 4 3.31 S&6 1 A 16 GA/M0 OC- BT0/CS 103 0 5023-3 3.31 S&6 1 A 16 3A/M0 OC PIT /RR 0 502',-2-3.31 S&6
- 3HV9339, Isolation Valve - Shutdown Cooling System from RCS Loop 2
. (Dwg.: 40112DS03/C 2) Valve Mfg.: WKM i 1 A 16 GA/MO OC AT/RR 0 5023-3-3.31 1) S&6 BTC/CS 103 0 S023 3-3.31 516 1 ~A GA/MO OC 1 A 16 GA/MO OC BT0/CS 103 0 5023 3 3.31 S&6 1 A 16 GA/MO OC PIT /RR 0 5023 3 3.31 S&6
- 3HV9340. Safety Injection Tank T008 Outlet Valve to RCS Loop 1A (Dwg.: 40113AS03/D 6) Valve Mfg.: WKM-1 B 12. .GA/M0' 0 BT0/CS 35 0(5023 3-3.31) S&6 1 B 12' GA/MO O PIT /RR 0(50233-3.31) S&6
*i 3HV9345. Safety injection Tank T008 Vent (Dwg.: 40ll3AS03/G 6)- Valve Mfg.: Target Rock 2 8 1 ..GL/SO C. BT0/CS 2 0S02333.31) 5 2 B 1 GL/SO. C FSTC/CS 0 S023 3 3.31) 5 2 B 1 .GL/50- C PIT /RR 0 S023 3 3.31) 5
- 3HV0347, Isolation Valve Safety injection Recirculation to RWST T005 ,
s -(Dwg.: 40114DS03/D 3) Valve Mfg.: WKM 2 B 4 GA/MO O BTC/0P 32 0 S023-3-3.30 3&6 2 B 4 GA/MO O PIT /RR 0 5023-3-3.30 3&6 ATTACHMENT 4 PAGE 36 0F 52
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UN!15 2 AND 3 REVISION 7 PAGE 128 0F 20B
^
rN ATTACHM[NT 4 TCN 7~16 () LEll.] 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: M Maintenance. 0 Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time.(Procedure) Requests
- 3HV9340, Isolation Valve, Safety injection Recirculation to RWST T005 (Dwg.: 401140503/D 4) Valve Mfg.: WKM 2 B 4 O BTC/0P 32 0(5023 3 3.30) 3&6 GA/MO 2 B 4 O PIT /RR 0(502333.30) 386 GA/MO
- 3Hv9350. Safety Injection Tank T009 Outlet Valve to RCS Loop IB (Dwg.: 40ll3AS03/D 2) Valve Mfg.: WKM 1 B 12 GA/MO O BT0/CS 32 0 5023 3-3.31 S&6 1 B 12 GA/MO O PIT /RR 0 5023 3 3.31 S&6
- 3HV9355, safety injection Tank T007 Vent Valve (3 (Dwg : 40ll3AS03/G-2) Valve Mfg.: Target Rock
( ,/ 2 B 1 GL/50 C BT0/CS 2 0 S023 3 3.31 5 2 B 1 GL/SO C FSTC/CS 0 5023 3 3.31 5 2 B 1 GL/SO C PIT /RR 0 5023 3-3.31 5
- 3HV9360, Safety injection Tank T009 Outlet Valve to RCS Loop 2A (Dwg.: 40ll3B503/D 6) Valve Mfg.: WKM 1 -B 12 GA/MO O BT0/CS 32 0 5023 3-3.31 5&6 1 B 12 GA/MO O PIT /RR 0 S023-3 3.31 S&6
- 3HV9365, Safety injection Tank T009 Vent Valve (Dwg.: 40ll3BS03/G 6) Valve Mfg.: Target Rock 2 B 1 GL/SO C BT0/CS 2 0(5023 3 3.31 5 2 B' 1 GL/50 C FSTC/CS 0(5023-3 3.31 5 2 B 1 GL/50 C PIT /RR 0(5023 3 3.31 5
- 3HV9370, Safety injection Tank T010 Outlet Valve to RCS Loop 2B l (Dwg.: 40113B503/D 2) Valve Mfg.: WKM 1 B 12 GA/M0 O BT0/CS 35 0(5023-3-3.31) 5&6 1 B 12 GA/MO , O PIT /RR 0(5023 3 3.31) 5&6
- 3HV9375, safety Injection Tank T009 Vent Valve (Dwg.: 40ll3BS03/G-2) Valve Mfg.: Target Rock 1 B 1 GL/50 C BT0/CS 2 0(5023-3 3.31) 5 1 B 1 GL/50 C FSTC/CS 0(502333.31) 5 1 B 1 _GL/SO C PIT /RR 0(5023 3-3.31) 5 v
l ATTACHMENT 4 PAGE 37 0F 52
l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 129 0F 20B
,m ATTACHMENT 4 TCH ,_7 - I n (a)
~
10/16,'91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M. Maintenance. 0 = Operations T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Pelief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- 3HV9377, Isolation Yalve SDC5 Bypass to LPSI Suction (Dwg.: 40ll20S03/B 4) Valve Mfg.: WKH 1 A 10 GA/MO OC AT/RR 5023 3 3.3).1) 5&6 [
l BTC/CS 340 0 5&6 1 A A 10 10 GA/MO GA/MO OC OC BT0/CS 240 0(L502333.31)1 S&6 1 A 10 GA/MO OC PIT /RR 0((S023-33.310 5023-3 3.31) S&6
- 3HV9378, Isolation Valve SDCS Bypass to LPSI Suction 1(Dwg.: A 401120503/B 10 GA/MO 3)OC Valve Mfg.: WrJi 0 5023 3 3.31.1)
AT/RR S&6 1 A 10 GA/MO OC BTC/CS 240 0 5023 3 3.31) S&6 gm 1 A 10 GA/MO OC BT0/CS 240 0 5023 3 3.31 j 5&6 (j 1 A 10 GA/MO OC PIT /RR 0 S023-3-3.31) 5&6
- 3HV9379, Isolation Valve SOCS Bypass to LPSI Suction - Seal (Dwg.: 401120503/B 7) Valve Mfg.: WKM ,
2 B 12 GA/MO OC BTC/0P 14 0 5023 3-3.30) 6 2 B 12 GA/MO OC BT0/0P 14 0 5023 3 3.30) 6 2 B 12 GA/MO OC PIT /RR 0 S023 3-3.31) 6
- 3HV9420, Control Valve - HPSI Heeder #1 to RCS Loop 2 Hot leg (Dwg.: 40112CS03/G 3) Valve Mfg.: Target Rock 2 A 3 GL/M0 C AT/RR T S023 V 3.13 6&l0 2 A 3 GL/MO C BT0/CS 11 0 S023-3 3.31 6&lo 2 A 3 GL/MO C PIT /RR 0 S023-3 3.31 6&l0
- 3HV9434, Control Valve - HPSI Header #2 to RCS Loop 1 Hot Leg (Dwg.: 40112CS03/E 3) Valve Mfg.: Target Rock 2 A 3 GL/M0 C AT/RR T(5023-V-3.13) 6&l0 2 A 3 GL/MO C BT0/CS 11 0(5023 3 3.31 6&lo 2 A 3 GL/MO C PIT /RR 0(5023 3 3.31 6&l0
- 3PSV9349, SDCS Relief Valve from RCS Loop 2 (Dwg.: 40ll20503/C-5) Valve Mfg.: Crosby 2 C 8 RV/SA C RVT/RR M(5023-1 2.34) 15 o
j ATTACHMENT 4 PAGE 3B 0F 52
ENGINEERING PROCEDURE PAGE 130 Of 208S023 V 3.5 HUCLEAR ORGANIZATION REVIS10N 7 UNITS 2 AND 3 ATT ACHMENT 4 TCN 7-30 O utill_1 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear GeneratingOperations,Station T = Technical) (Test Org's: M Haintenance, 0 Discussion of Cold Shutdown Intervals, see Next Att. Notes and Valve Test Valve Type Test Relief See and Str. Organization Requests Code XI Site Actuator Norm and Pos. Mode Time (Procedure) Class Cat (in.) Type (24 001 C 724), RW Tank 3T005 to Spray Pump 3P012
* $31204MU001 Suction Header Valve Mfg.: TRW/ Mission I&l8 VRR 02 (Dwg.: 40ll2AS03/D 8) A C CVP0/0P 1 S023- 6 3.5.4) 1&l8 VRR 02 2 C 24 SDCK/S CVTC/RR H S023-I 6.20) 1&l8 VRR-02 2 C 24 SDCK/SA C H $023 1 6.20)
SDCK/SA C CVT,0/RR 2 C 24 , (24 002 C 724), RW Tank 3T006 to CS Pump 3P013 Suctio S31*04MU002 Header TRW/ Mission 1&l8 VRR 02 (Dwg.: 40112AS03/D 7) Valve Mfg.: CVP0/0P T 5023 V 3.5.4) 1&l8 VRR 02 2 C 24 SDCK/SA C H S023 1 6.20) SDCK/SA C CVTC/RR 1&l8 VRR 02 2 C 24 CVT0/RR H S023 1 6.20) 0
- 2 C S31204MU003 24 SDCK/SA C (24 003-C-724), Outlet Check Valve Containment
, Emergency Sump Valve Mfg.: TRW/ Mission 1,5&l8 VRR 03 (Dwg.: 40ll2AS03/A 7) A C CVP0/RR 1,5&l8 VRR 03 2 C 24 SDCK/S CVT0/RR T(Later)
M(5023 1- 6.20) 2 C 24 SDCK/SA C Containment (24 004 C 724), Outlet. Check Valve S31204MU004 Emergency Sump Valve Mfg.: TRW/ Mission 1,5&l8 VRR 03 (Dwg.: 40ll2AS03/B-7) A C CVP0/RR 1,5&l8 VRR 03 2 C 24 SOCK /S CVT0/RR T(Later) M(50231- 6.20) 2 C 24 SOCK /SA C
- S31204HU006 (10-006 C 675), HPSI Pumps 3P017 and 3P018 Suction Check Valve (Dwg.: 40ll2A503/G 7) Valve Mfg.: Aloyco VRR-08 C CVP0/0P T(S023 V 3.5.4) VRR-08 10 CK/SA 2 C CK/SA C CV10/RR 0(502332.8) 2 C 10 (10 008 C 675), HPSI Pumps 3P018 and 3P019 Suction Check S31204MU008 Valve (Dwg.:
40112A503/C-7) Valve Mfg.: Aloyco VRR 08 C CVP0/0P T(SO23-V 3.5.4) VRR 08 C 10 CK/SA 2 C CVT0/RR 0(S023-3-2.8) 2 C 10 CK/SA 9 PAGE 39 0F 52 ATTACHMENT 4
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 131 Of 208 n ATTACHMEkT 4 Q TCN 7 - Lg_ l#RI_1 10/16/91 j Inservice Testing Program for Valves ; San Onofre Nuclear Generating Station (TestOrg's: M* Maintenance. 0 = Operations, T = Technical) i Discussion of Cold Shutdown Intervals, See Next Att. : i Test Notes and : Valve ' See and Type Test Valvo Code XI Size Actuator Norm and Str. Organization Relief , ClassCat(in.) Type Pos. Mode Time (Procedure) Requests !
- S31204 MOO 12 (4 012 C 358)~, HPSI Pump 3P017 Discharge Check Valve !
(Dwg.: 40ll2A503/G 3) Valve Mfg.: Anchor / Darling i 2 C 4-SCK/SA -C CVT0/CS- 0($02333.31.2) 5
S31204MUO15 (4 015 C 358), HPSI Pump 3P019 Discharge Check Valve ;
(Dwg.: 40112AS03/C-3) Valve Mfg.: -Anchor / Darling ! 2 C 4 SCK/SA C CVT0/CS 0(502333.31.2) 5 i
- S31204MU016 (4 016 C 358), HPSI Pump 3P018 Discharge Check Valve ;
(Dwg. 40ll2AS03/E 3) Valve Mfg.: Anchor / Darling 2 C 4 SCK/SA C CVT0/CS 0(5023 3 3.31.2) 5
- S31204MU017 (4017C-553),HF.iPumps3P018&3P019to32High Pressure Header (Dwg.: 40112AS03/C 1) Valve Mfg.: Anchor / Darling 2 C 4 CK/SA C CVT0/CS 0(502333.31.2) 5 ,
- S31204HU018 (3 018 A 551), HPSI Combined Header to RCS Loop 1A Check Valve
-1(Dwg.: 40112C503/D
.AC ~3 CK/SA 3)C Valve Mfg.t Anchor AT/RR
/ Darling 0(S023-33.31.1) 5 1 AC 3 CK/SA C CVT0/CS 0(502333.31.2) 5 S31204MV419_ -(3 019 A 551), HPSI Combined Header to RCS Loop 18 Check Valve
-(Dwg.: 40ll2CS03/C 3) Valve Mfg.: Anchor / Darling 1 AC 3 CK/SA C AT/RR 0(5023 3 3.31.1) 5' 1 AC 3 CK/SA C CVT0/CS 0(502333.31.2) 5 a S31204MV020 3 020 A 551), HPS1 Combined Header to RCS Loop 2A Check alve 1(Dwg.: AC40112CS03/B3)ValveHfg.:
-3 CK/SA .C AT/RR Anchor0(5023 / Darling 3 3.31.1) 5 1: ACL 3- CK/SA -C CVT0/CS 0(502333.31.2) 5
- S31204MU021 (3021-A551),HPSICombinedHeadertoRCSLoop2BCheck Valve (Dwg.: 40ll2CS03/F-2) Valve Mfg.: Anchor / Darling
-O 1: 1 AC -3 AC 3 CK/SA CK/SA C-C AT/RR CVT0/CS 0 5023-3 3.31.1 0 5023 3-3.31.2 5 5 ATTACHMENT 4 PAGE 40 0F 52
NUCLEAk ORGA5!IZAT10N ENG!Ntr. RING PROCEDURE S023-V-3.5 UNITS 2 AND ' REVISIUA 7 PAGE 132 0F 208 ATTACHMENT 4 TCN _L- 16 UNIT 3 10/16/91 b ervice Testing Program for Valves 'i San Onofre Nuclear Gent. rating Station
. e~' S : M= Maintenance. 0 = Operations. T a Technical) 3 p ** m ul Cold ShutMn Intervals, See Next Att.
l "' T9.t t Nott and an .ype Test Valve
- s. u o f . sate Nom .c Str. Organization Relief
. . . ) ;., p Pos. ..soe Time (Procedure) Requests (10 024 C 406), LPSI Pump 3P015 Discharge Stop Check Valve (Dws 1 3S03/G-S Vaive Mfg.- Anchor / Darling 2 C L SCK/SA C C'riO/06 0(5023 3-3.31.2) 5 t
k '
@ 204MUO25 (10 025-C-406), LPSI Pump 3P016 Discharge Stop Check Valve (D49.: 401126503/[-3) Valve Mfg.: Anchor / Darling 2 C 10 SO:/SA C CVT0/CS 0(S023-3-3.31.2) 5
- S31204MUO27 (l'c 427-A-551), Safety Injection Headers to RCS Loop 1A
- r. heck Valve (Dwg.:- 40113AS03/L-5) Valve Mfg.: Ar:hc., " cling x H '
1 AC "' CK/SA C AT/RR ugS023-3-3.31.1) 5 1 AC E, CK/SA C CVT0/CS O(5023-3-3.31.2) 5
- S31204HUO29 (12-025-;,554), Safety injection Headers to RCS Loop 1B Check Valve (Dwg.: 40113AS03/C-4) Valve Mfg.: Anchor / Darling 1 At I '> CK/SA C AT/RR 0(S023-3-3.31.1) 5 1 AC 12 C(/SA_ C CVT0/CS 0(5023-3-L 31.2; 5 _
4
- S31204MUO31 (12-031-A-551), Safety Injection Headers to RCS Lesp 2A Check Valve (Dwg.: 40ll3BS03/C-5) Valve Mfg.c Anchor /Darlir.g 1 AC I? CK/SA C M/RR 0(5023 3-3.31.1) 1 AC 12 CK/SA C CVT0/CS 0(5023-3-3.31.2) .
- S31204NO33 (l? 033-A-551), Safety Injection Headers to RCS Loop 2B Check Valve (Dwg.: 40113BSU3/C-4) Valve Mfg.: Anchor /Darliig 1 AC 12 CK/SA C AT/RR .0(S0i3-3-3.31.1) 5 1 AC 12 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5
- S31204MUO34 (2-034 C-329), HPSI 3P017 Miniflow (Owg.: 40ll2AS03/H-2) Valve Mfg.: Rcekwell Edwards 2 C 2 C SCK/SA CVT0/0P T(S023-V-3.5.4) a
- S3120C40035 (2-035-C-329),'HPSI 3P019 Miniflow
. ', (Dwg.: 40ll2AS03/D-3) Valve Mfg.: Rocku .1 Edwards 2 C 2 SCK/SA C CVT0/0P T(S023-V-3.5.4)
ATTACHMENT 4 PAGE 41 0F 52 l
-1 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 133 0F 208 x ATTACHMENT 4 TCH , 7-11
)
pfi1La 10/16/91 Inservice Testing Program for Valves San Or.ofre Nuclear Generating Station (Test Org's: M Maintenance. 0 = b rations, 1 - Technical) Discu.ssion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type- Pos. Mode Time (Procedure) Requests
- S31204MUO36 (2-036-C-329), HPSI 3P018 Train "A' Miniflow (Dwg.: 40ll2AS03/F-3) Valve Mfg.: Rockwell Edwards 2 C 2 SCK/SA' C CVT0/0P T(5023-V 3.5.4)
- S31204MUO37 (2-037-C 329), LPSI- Pump 3P015 Miniflow Stop Check Valve (Dwg.: 40ll2BS03/G-2) Valve Mfg.: Rockwell Edwards 2 C 2 SCK/SA C CVT0/0P T(5023-V-3.5.4)
- S31204MUO40 (12-040 A 551), Safety Injection Tank T008 Outlet Check Valve (Dwg.: 40ll3AS03/D 6) Valve Mfg.: Anchor / Darling 1,5&l8 VRR-ll (q
'f - l 1 AC 12 AC 12 AC 12 CK/SA _CK/SA C C C AT/RR CVP0/CS CVT0/RR 0/.S023-3-3.31.1) 0(S023 3-3.31.2) M(S023-1-6.160) 1,5&l8 VRR-ll 1,5&l8 VRR-ll 1 CK/SA
- S31204MUO41 (12-041-A-551), Safety Injection Tank T007 Outlet Check Valve (Dwg.: 40113AS03/D 2)_ Valve Mfg.: Anchor / Darling 1 AC 12 CK/SA C AT/RR 0(S023 3-3.31.1) 1,5&l8 VRR ll 1 AC 12 CK/SA C CVP0/CS 0(S023-3 3.31.2) 1,5&l8 VRR-ll 1 AC 12 CK/SA C CVT0/RR M(S023-1-6.160) 1,5&l8 VRR-11
- S31204MUO42 (12-042-A-551), Safety Injection Tank 1009 Cutlet Check Valve (Dwg.: 40ll3BSf'10 7 Valve Mfg.: Anchor / Darling 1 AC 12 IV C AT/RR 0(S023-3-3.31.1) 1,5&l8 VRR-ll 1 AC 12 J. C -C CVP0/CS 0(5023-3-3.31.2) 1,5&l8 VRR-11 1 AC 12 CK/ ,,A C CVT0/RR M(5023-1-6.160) 1,5&l8 VRR-11 v._s ATTACHMENT 4 PAGE 42 0F 52
NUCLEAP ORGANIZATION ENGINEERING PROCEDURE S013-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 134 0F 208 rm ATTACHMENT 4 ( ) TCH 7-16 UNIT 3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance, 0 Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S31204MUO43 (12 043-A 551), Safety injection Tank T010 Outlet Check Valve (Dwg.: 40ll3BS03/D 2) Valve Mfg.: Anchor / Darling AC 12 C AT/RR 0(S023-3-3.31.1) 1,5&l8 VRR 11 1 CK/SA AC 12 C CVP0/CS O(5023-3-3.31.2) 1,5&l8 VRR-11 1 CK/SA 1 AC 12 CK/SA C CVT0/RR M(5023 1-6.160) 1,5&l8 VRR-il
- S31204MUO63 (2-063 C-329), LPSI Pump 3P016 Miniflow Stop Check Valve (Dwg.: 40ll2BS03/D 2) Valve Mfg.: Rockw6 1 Edwards 2 C '2 SCK/SA C CVT0/0P 'i ( SO23-V-3. E . 4 )
El
- S31204HUO72 (3 072-A-552), LPSI to RCS Loop 1A Check Vala j (Dwg.: 40112DS03/d 2) Valve M'g.: Anchor / Darling.
1 AC 8 CK/SA C AT/RR 0(S023-3-3.11.1) 5 1- AC 8 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5
- S31204MUO73 (8-073-A ,552)._LPS! to RCS Loop IB rheck Valve (Dwg.: 40ll20503/F 2) Valve Mfg.: Anchor / Darling 1 - AC 8- CK/SA C AT/RR 0(S023-3-3.31.1) 5 1 AC 8 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5
- S31204MUO74 (8-074-A-552), LPSI to RCS Loop 2A Check Valve (Dwg.: 40112D503/F-2) Valve Mfg.: Anchor / Darling 1 AC 8 CK/SA C AT/RR 0(S023 3-3.31.1) 5 1 AC 8 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5
$ S31204MUO75 (8-075-A-552), LPSI to RCS Loop 2B Check Valve (Dwg.: 40112DS03/H 2) Valve Mfg.: Anchor / Darling 1 AC 8 CK/SA C AT/RR 0(S023-3-3.31.1) 5 1_ AC 8 CK/SA C CVT0/CS 0(S023-3-3.31.2) 5
- S31204MUO77 (16-077-C-645), LPSI Pump 3P016 Suction Header Check Valve (Dwg.: 40112BS03/E-7) Valve Mfg.: Anchor / Darling 2 C 16 CK/SA C CVP0/0P T(5023-V-3.5.4) 1 VRR-12 2 C 16 CK/SA C CVT0/RR T(5023-SPT-8) 1 VRR-12 m
(
)
ATTACHMENT 4 PAGE 43 0F 52 - - _ J
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 135 0F 208 m ATTACHMENT 4 i )- TCH 7-1n v-MElll 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance. 0 - Operations, T = Technical) Discussion of Cold Shutdown Intervals, see Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S31204HUO84 (16-084 C-645), LPSI Pump 3P015 Suction Check Valve (Dwg.: 40ll2AS03/G-7) Valve Mfg.: Anchor / Darling 2 C 16 CK/SA C CVP0/0P T(5023 V 3.5.4) 1 VRR 12 2 C .16 CK/SA C CVT0/RR T(5023-SPT-8) 1 VRR 12
- S31204MU387 (16-087 C-675), Containment Spray Pump 3P013 Suction Check Valve 3 (Dwg.: 40114AS03/F 6) Valve Mfg.: Anchor / Darling 2 C 16 CK/SA C: CVT0/CS 0(S023-3-3.31.2) 5 L
- S31204MU088 (16-088 C-675), Containment Spray Pump 3P012 Suction i-p)
( Check Valve (Dwg.: 40ll4AS03/C 6) Valve Mfg.: Anchor / Darling 2 C 16 CK/SA C CVT0/CS O(5023 3 3.31.2) 5
- S31204MUO99 (2-099 C-334), SI Tank Drain Header to RFWT 3T005 Contmt Isolation Valve (Dwg.: 40ll4DS03/F-6) Valve Mfg.: Kerotest 2 A 2 GL/M C AT/RR T(S023-V-3.13) 10
- S31204MU104 (2-104-C-329), HPSI 3P018 Train "B" Miniflow (Dwg.:- 40ll2A503/E-2) Valve Mfg.: Rockwell Edwards-2 C 2 SCK/SA C CVT0/0P T(5023-V-3.5.4)
- S31204MU152 (3-152-A-551), To #2 HPSI Header (Dwg,: 40111AS03/F 5) Valve Mfg.: Anchor / Darling 1 AC 3- CK/SA C AT/RR 0(5023-3-3.31.1) 1 AC _3' CK/SA C CVT0/Ct 0(5023-3-3.31.2)
- S31204MU155 (3-155-C-551), HPSI Header #1 to RCS Loop #2 Hot leg (Dwg.: 40112CS03/F-7) Valve Mfg.: Anchor / Darling 2 C 3- CK/SA C CVT0/CS 0(S023-3-3.31.2) 5
- S31204Mul56 (3-156 A-551), HPSI Header #1 to RCS Loop #2 Hot Leg Inlet Check Valve (Dwg.: 40112DS03/8 2) Valve Mfg.: Anchor / Darling 1 AC 3 CK/SA C AT/RR 0(S023-3-3.31.1) 5 g 1 AC 3 CK/SA C CVT0/CS 0(5023-3-3.31.2) 5 LJ ATTACHMENT 4 PAGE 44 0F 52
NUCLE R ORGANIZATION ENGINEERING PROCEDURE 5023-V-3.5
-UNITS 2 AND 3 REVISION 7 PAGE 136 0F 208 .(y T'
6 ATTACHMENT 4 TCH J a i f_ UNil 3 - I
.10/16/91 .
Insenice Testing Program for Valves l San Onofre Nuclear Generating Station (TestOrg's: M. Maintenance. 0 Operations, T = Technical) i Discussion of Cold Shutdown Intervals, see Next Att. Valve- Test- Notes and Sec 'and- Type iest Valve Code' XI Size -- Actuater Norm and Str. Organization Relief
. Class; Cat (in.) Type -Pos. Mode' Time (Procedure) Requests
- S31204MU157:(3-157 A 550),_HPSI Header #2 to RCS Loop #1 Hot Leg
_ ~(Dwg.: 40ll2CS03/E 2) Valve Mfg.:- Anchor / Darling
- 1- -AC: 3 CK/SA- C AT/RR T(S023-V3.13) Salo 1 -- ~ AC 3: CK/SA C CVT0/CS 0(50233-3.31.2) S&lo
- S31204MU158 (3 158 A 550), HPSI Header #1=to RCS Loop #2 Hot Leg
'(Dwg.: 40ll2CS03/G 2)_ Valve Mfg.: Anchor / Darling 1 'AC~ 3 CK/SA C- .AT/RR T(S023-V-3.13) 5&l0
-l ~AC 3 CK/SA C CVT0/CS 0(S023-3 3.31.2) S&l0
- S31204Mul99 (16-IS9-C 645), LPSI Pump'3P016 Suction Header-Check Valve ft (Dwg.: 40ll2AS03/D-7); Valve Mfg.: Anchor / Darling Q L2- -C 16 CK/SA C. CVP0/0P .T(5023V-3.5.4) . 1_VRR 12-2 C 16 CK/SA C CVT0/RR .T(S023-SPT8) 1 VRR-12
- 531204MU201 (16-201-C 645), LPSI Pump 3P015 Suction Header Check Valve (Dwg.:: 40ll28503."i-7). Valve Mfg.: Anchor / Darling.
2' C - 16 CAf SA ~ C' CVP0/0P -T(S023-V-3.5.4) 1 VRR-12 , 2 C 16' CK/SA 'C- CVT0/RR T(S023-SPT-8)' 1 VRR-12
**Sistem:. Salt. Water. Cooling
- 3HV6200, SWCS~ Pump 3P112 Discharge Valve-(Dwg.: 40126AS03/G-3) Valve Mfg.: Fisher 3 :B : 30- BTF/A0 OC BT0/0P 18 0(5023 3-3.30)
- 3; -B. 30- BTF/AO: OC -FST0/0P 0(5023-3-3.30)
-3 18- 'BTF/A0i -OC: PIT /RR _0(S023 3-3.30)
- 3HV6201, SWCS. Pump 3Pll3_ Discharge Valve
-(Dwg.: 40126AS03/E-3) Valve Mfg.: Fisher-
.3 :B. - 30 BTF/A0 _OC. BT0/0P 18 -0(S023-3-3.30) 3- B- 30 BTF/A0 -OC FST0/0P 0(S023-3-3.30)-
3- iB __30 . -BTF/A0_ OC- PIT /RR- 0(5023-3-3.30)
* -3HV6202, SWCS Pump 3P307 Discharge Valvo.
-(Dwg.: -40126BS03/G-3)ValveMfg.': Fisher
~
3~ 'B 30 '3TF/A0--OC. BT0/0P 18 0(S023-3 3.30) pg q 3 3: Bt 30 B- 30 BTF/AO- OC_
.BTF/A0 OC FST0/0P PIT /RR 0(50233-3.30) 0(S023-3-3.30)
ATTACHMENT 4 PAGE 45 0F 52 3
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023-V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 137 0F 20B n ATTACHMENT 4 ( _
) TCN 7_-y.g.
UNIT _3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance, 0 - Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and See and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- 3HV6203, SWCS Pump 3Pil4 Discharge Valve (Dwg.: 40126BS03/E-3) Valve Mfg.: Fisher 3 B 30 BTF/A0 OC BT0/0P IB 0(S023-3-3.30) 3 B 30 BTF/A0 OC FST0/0P 0(S023-3-3.30) 3 B 30 BTF/A0 OC PIT /RR 0(S023-3-3.30)
- 3HV6494, SWCS from CCW Heat Exchanger E002B to Overflow at Seawall (Dwg.: 40127CS03/D-3) Valve Mfg.: Fisher 3 8 30 BTF/M0 C BT0/0P O S023-3-3.30) 6,7 3 B 30 BTF/MO C PIT /RR 0 S023-3-3.30) 6,7 7T
- 3HV6495, Salt Water from CCW Heat Exchanger E002B
~) 3 (Dwg.: 40127CS03/E-2) Valve Mfg.: Fisher B 30 BTF/MO C BT0/0P 75 0(S023-3-3.30) 6 3 8 30 BTF/MO C PIT /RR 0(S023-3-3.30) 6
- 3HV6496, SWCS from CCW Heat Exchanger E001A to Overflow at Seawall (Dwg.: 40127CS03/C-3) Valve Mfg.: Fisher 3 8 30 BTF/M0 C BT0/0P 0(5023-3-3.30) 6,7 3 B 30 BTF/M0 C PIT /RR 0(5023-3-3.30) 6,7
- 3HV6497, Salt Wates from CCW Heat Exchanger E001A (Dwg.: 40127CS03/B-2) Valve Mfg.: Fisher 3 B 30 BTF/M0 C BT0/0P 75 0(5023-3-3.30) 6 3 B 30 BTF/MO- C PIT /RR 0(5023-3-3.30) 6
- S31413MU009 (30-009-D-722) SWCS Pump 3Pil2 Discharge Check Valve (Dwg.: 40126AS03/G-4) Valve Mfg.: TRW/ Mission 3 C. 30 SDCK/SA OC CVTC/0P T(5023-V-3.5.4) 3 C 30 SDCK/SA OC CVT0/0P T(S023-V-3.5.4) -
- S31413MUO10 (30-010-D-722), SWCS Pump 3Pll3 Discharge Check Valve (Dwg.: 40126AS03/D-4) Valve-Mfg.: TRW/ Mission
- 3. C 30 SDCK/SA-0C CVTC/0P T(S023-V-3.5.4) 3 C 30 SDCK/SA OC CVT0/0P T(5023-V-3.5.4)
- S31413MU0ll-(30-Oll-D-722), SWCS Pump 3P307 Discharge Check Valve
'q- (Dwg.: 40126BS03/G-4) Valve Mfg.: TRW/ Mission
/ 3 C 30 SDCK/SA OC CVTC/0P T(5023-V-3.5,4) 3 C- 30 SDCK/0A OC CVT0/0P T(S023-V-3.5.4)
ATTACHMENT 4 PAGE 46 0F 52
. NUCLEAR ORGANIZATION ENGINLER;NG PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 138 0F 200 ATTACHMENT 4
'N
) TCN 7-in
, UNIT.3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Genersting Station (TestOrg's: M Maintenance. 0 Operaiions, T = Technical)
Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and Sec _and Type Test Valve Code XI Size Actuator Norm and Str. Organization Relief ClassCat(in.) Type Pos. Mode Time (Procedure) Requests
- S31413MUO12 (30 012-D 722), SWCS Pump 3Pil4 Discharge Check Valve (Dwg.: 40126BS03/E 4)- Valve Mfg.: TRW/ Mission 3 C 30 SDCK/SA OC CVTC/0P TS023-V-3.5.4) 3 C 30 SDCK/SA OC CVT0/0P T S023-V-3.5.4)
- S31413MU013 (l'013-D-691), SWCS Pump 3Pll2 Recirculation to Cyclone Separator (Dwg.: 40126AS03/F-4) Valve Mfg.: Controlmatics 3 C 1 CK/SA C CVT0/0P T(5023 V-3.5.4)
- S31413MU016 (1-016-04?U. SWCS Pump 3Pil3 Recirculation to Cyclone 3 Separator
( ,)
~
(Dwg.: 40126AS03/D 4) Valve Mfg.: Controlmatics 3 C 1 CK/SA C CVT0/0P T(5023-V-3.5.4)
'* S 1MUO21 (1-021-D-691), SWCS Pump 3P307 Recirculation to Cyclone Separator .. .
(Dwg.: 40126BS03/F-4) Valve Mfg.: Controlmatics 3 C 1- CK/SA C CVT0/0P T(5023-V-3.5.4)
- S31413MUO24 (1024 il 691), SWCS Pump 3Pil4 Recirculation to Cyclone Separator (Dwg.: 40126BS03/0-4) Valve Mfg.: Controlmatics 3 C 1 CK/SA L CVT0/0P T(S02?-Y-3.5.4)
S31413MUO47 (1-047-D-691), Check Valve Scevice Water Supply to Salt Water Pump 3P112 (Dwg.: 40126A503/G-7) Valve Mfg.: 3 -C CK/SA C CVTC/0P T(5023-SPT-7) S31413MUO48 (1-048-D-691), Check Valve Service Water Supply to Salt Water Pump 3P113
. (Dwg.: 40126AS03/0 7) Valve Mfg.:
3 C CK/SA C CVTC/0P T(S023-SPT 7)
- 531413MUO49 (1-049-D-691), Check Valve Service Wamr Supply to Salt Water Pump 3P307 m (Dwg.: 40126B503/G-7) Valve Mfg.:
) 3 C CK/SA C CVTC/0P T(E023-SPT-7)
ATTACHMENT 4 PAGE 47 0F 52
NUCLE /.R ORGANIZATION ENGINEERING PROCEDVRE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 139 0F 208 ATTACHMENT 4 TCN , 7-in T w,) . 1/ 1 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (Test Org's: M Maintenance 0 Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve . Test Notes and See and Type Test Valve Str. Organization Relief Code XI Size Actuator Norm and Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
- S31413MV050 (1-050-D-691), Check Valve Service Water Supply to Salt Water Pump 3Pll4 (Dwg.: 40126BS03/D 7) Valve Mfg.:
3 C CK/SA C CVTC/0P T(S023-SPT-7) ,
** System: St.am
- 3HV4053, S/G E089 Blowdown Isolation Valve (Dwg.: 40141AS03/C-2) Valve Mfg.: Fisher 2 B 6- GL/A0 0 BTC/0P 9 0(5023-3-3.30) 3 2 B 6 GL/A0 0 FSTC/0P 0(S023-3-3.30) 3 77 2 B 6 GL/A0. O. PIT /RR 0(S023-3-3.30) 3
')
- 3HV4054, S/G E088 Blowdown Isolation Valve l (Dwg.:- 40141AS03/F-2)- Valve Mfg. : Fisher 2 B 6 GL/A0 0 BTC/0P 9 0(S023-3-3.30) 3 2 B .6 GL/A0 0 FSTC/0P 0(S023-3-3.30) 3 2 B 6 GL/A0 0- PIT /RR 0(S023-3-3.30) 3 !
- 3HV4057, S/G E089 Sample Isolation Valve (Dwg.: 40141AS03/B-2) Valve Mfg.: Fisher 2 B 3/4 .GL/A0 0 BTC/0P 5 0(5023-3-3.30) 3 2: B 3/4 GL/A0 0 FSTC/0? 0(S023-3-3.30) 3 2 B- 3/4 GL/A0 0 PIT /RR 0(S023-3-3.30) 3
- 3HV4058, S/G E088 Sample Isolation Valve (Dwg.: 40141AS03/F-2) Valve Mfg.: Fisher 2 B 3/4 GL/A0' 0 BTC/0P 5 0(S023-3-3.30) 3 2 B 3/4 GL/A0 0 FSTC/0P 0(S023 3-3.30 3 2 B 3/4 GL/A0 0 PIT /P.R 0(S023-3-3.30 3 3HV8200, Steam from Steam Generator E089 to AFW Pump (Dwg.: 40141CS03/E-3) Valve Mfg.: Fisher 2 B 4 GL/A0 OC BT0/0P 4 0($023-3 3.30) .
~
2 B- 4 GL/A0 OC FST0/0P 0(S023-3-3.30) 2 B 4 GL/A0 OC PIT /RR 0(5023-3-3.30) ATTACHMENT 4 PAGE 48 0F S2
NUCLEAIORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2'AND 3 REVISION 7 PAGE 140 0F 208 m ATTACHMENT 4 TCN _7 - I g f W1I.3 10/16/31 Inservice ' Testing Program for Valves
- San Onofre Nuclear Generating Station (TestOrg's: M Maintenance. 0 = Operations, T = Technical)
Discussion of Cold-Shutdown Intervals, See Next Att. Valve Test Notes and Sec and Type - Test Yalve Code :XI Size Actuator Norm and Str. Org&nization Relief
-ClassCat-(in.)-Type Pos. Mode Time (Procedure) Requests
- 2HV8201, Steam from-Steam Generator E088 to AFW Pump
_'(Dwg.:-40141DS03/E-3) Valve Mfg.: Fisher
.2 B '4= GL/A0- OC - BT0/0P 4 - 0 5023 3-3.30 2 B- 4 GL/AO- -0C FST0/0P O S023-3-3.30 2' B 4' GL/AO -0C: PIT /RR- 0 S023-3-3.30 3HV8204. Steam Generator E089 Main Steam Irolation Valve (MSIV)
(Dwg.: _40141C503/B 2) Valve Mfg.: WKM
-2 B; 40_ GA/HY :0 BTC/CS 8 _0(503-3-3.17) 3&9 .
0(S03-3-3.17) 3&9 12 :B l40 GA/HY 0 BTPC/0P 3&9-2 8 -40 GA/HY 0 FSTC/CS 0(S03-3-3.17) p# .2. 'B 40: GA/HY 0 PIT /RR 0(S03-3 3.17) 3&9
- 3HV8205, Steam Generator E088 Main Steam Isolation Valve (MSIV)
.'(Dwg.:-40141DS03/B 3) Valve Mfg.: WKM 2 B' .40 GA/HY 0 'BTC/CS 8 0(S03-3-3.17) 3&9 2- B . ' 40 .GA/HY 0 BTPC/0P -0(S03-3-3.17) 3&9
)2 B-- 40 GA/HY. 0 :FSTC/CS 0(503-3 3.17) 3&9 2 B 40' GA/HY 0- PIT /RR 0(S03-3-3.17) 3&9
~* 3HV8419, Main Steam Dump to Atmosphere (Dwg.: 401410503/E-6) Valve Mfg.: Contr Cfnp 1
- 2 :. B. 8i AV/A0 1C. BTC/CS~ 15 0(5023-3-3'.31 3&ll VRR-25
-B- 8 AV/A0 C- PT0/CS,60 0(S023-3-3.31 S&ll VRR-25 2- B :8 AV/A0- C -BTP0/0? 0(S023 3-3.31 3&ll VRR-25
- 2. B _8- AV/AO' 'C. FSTC/C5 _0 S023-3-3~31
. 3&ll VRR-25
- 2- B -8 AV/A0 C -PIT /RR 0 S023-3-3.31 3&ll VRR-25
- 3HV8421,' Main Steam Dump to Atmosphere
. (Dwg.: 40141C503/F-6) Valve Mfg.: Contr Comp 11 2- -B. _8 ' AV/A0 C -BTC/CS' 15 0(5023-3-3.31) 3&ll VRR 25 2 B. 8 : AV/A0: 'C GT0/C*, 60 0(S023-3-3.31) 3&ll VRR 25 2 B; 8; AV/AD C. BTP0/0P- 0(5023-3-3.31) 3&ll VRR-25 2- :B' .8- AV/ AO. 'C: FSTC/CS 0(S023-3-3.31) 3&1l VRR-25 2 8 8_ AV/A0 C PIT /RR' 0(S023-3-3'31) 3&ll VRR-25
-* 3PSV8401, . Main Steam Relief Val- 1
% - (Dwg.: 401410503/G-7) Valve Mfg.: Crosby i
/eLy,) - ; -2. - CL 6 .SV/SA C: RVT/RR M(S023-1-2.5) 2 ATTACHMENT-4 PAGE 4] 0F 52
.k NUCt. EAR ORGAtilZATION ENGINEERING PROCEDURE $023 V-3.5
;c REVISION 7 PAGE 141 0F 208 ATTACHMENT 4
!-:q% ; -UNIU 2 AND 3-
): TCN 7~16 UKII.)
10/16/91: - 1 Inservice Testing Program for Valves l
- San Onofre Nuclear Generating Station (TestOrg's:MMaintenance.0= Operations,T= Technical)
Discussion of Cold Shutdown Intervals, See Next Att.
' Valve. Test Notes and Valve
_ Sec and -Type Test
! Code XI Size Actuator.' Norm and Str. Organization Ralief Class Cat'.(in.) Type ~ .Pos. Mode Time (Procedure) Requests
- 3PSV8402, Main Steam Relief Valvo.
-(Dwg.: 140141DS03/G-6). Valve Mfg.: Crosby-2 C 6, C RVT/RR M(S023-I-2.5) 2 SV/SA. ;
- 3PSV8403,' Main Steam Relief Valve (Dwg.: 40141DS03/G-6)ValveMfg.: Crc,sby 2 SV/SA C- RVT/RR- M(5023-I-2.5) 2 C _. : 6--
l
- 3PSV8404',- Main Steam Relief Valve (Dwg.: 40141DS03/G-5) Valve' Mfg.: Crosby E ..
2_' 'C' 6- SV/SA- C RVT/RR M($023-I-2.5)- 2 l "(T
- 3PSV8405, Mein Steam Relief Valve i
,G L (Dwg.: 401410503/G-5) Valve Mfg.: Crosby f2 .C l6 :SV/SA. C - RVT/RR .- M(S023-1-2.5)- 2 L i - l
'*- 3PSV8406, Main Steam Relief Valve _
q t (Dwg.: 401410503/G 4) Valve Mfg.: Crosby .
- 2- C .- 6: SV/SA C~ RVT/RR M(5023-I-2.5) 2 3PSV8407.-Main Steam Relief Valve L (Dwg.: 40141DS03/F-5) Valve Mfg.: Crosby-L -2 . C -- 6- SV/SA' C RVT/RR M(S023-I-2.5) 2 1* n 3PSV8408, Main Steam Relief Valve L
L J (Dwg,: 40141503/f-5) Valve Mfg.: Crosby-l 2- C: !6 SV/SA .C- _RVT/RR M(S023-I-0 ' - 2 3* 3PSV8409.- Main Steam Relief Valve
. '(Dwg. : ' 401410503/F-5) ' Valve Mfg. : Crosby- i E =2- C 6 SV/SA -C- .RVT/RR h(S023-1-2.5) 2
- 3PSV8410, Main Sten Relief Valve
. (Dwg.: 40141CS03/G-7; V-Jve. Mfg.: Crosby -
E :2 C 6L SV/SA- C -- -RVT/RR= M(5023-I-2.5)' 2
- 3PSVB411, Main Steam Relief Valve (Dwg.: 401410503/G 6)- Valve' Mfg.: -Crosby K q! y -. 2 -C 6 SV/SA. C .RVT/RR M(5023-I-2.5) 2 ATTACHMENT 4 PAGE 50 0F.52 m
NUCl. EAR OPSANIZATION ENGINEERING PROCEDURE 5023 V-3.5 UNIT 3 2 AfI, 3 REVISION 7 PAGE 142 0F 208 A , ATTACHMENT 4
-( ) TCN 7-18 1/ 1 Inservice Testing i ogram for Yalves San Onofre-Nuclear Generating Station ~*
(Test Org's: H.Haintenance, 0 Operations, T = Technical) Discussion of Cold Shutdown Intervals, See Next Att. Valve Test Notes and Sec and Type Test Valve Code XI Size Actuator Norm and Str. Oeganization Relief Class Cat (in.) Type Pos. Mode Time (Proc.edure) Requests
- 3PSV8412,- Main Steam Relief Valve (Dwg.: 401410503/G-6) Valve Mfg.: Crosby 2 C 6 SV/SA C RVT/RR M(S023-I-2.5) 2
- 3PSV8413, Main Steca Relief Valve (Owg.: 40141CS03/G-5) Valve Mfg.: Crosby 2- 6 C- RVT/RR M(S023-I-2.5) 2 C SV/SA
- 3PSV8414, Main Steam Relief Valve (Dwg.: 40141CS03/G-5) Valve Mfg.: Crosby 2 C 6- SV/SA C RVT/RR M(5023-I-2.5) 2
- 3PSV8415, Main Steam Relief Valys
"/ (Dwg.: 401410503/G-4) Valve Mrg.: Crosby
-2 C 6 SV/SA C RVT/RR M(5023-1-2.5) 2
- 3PSV8416, Main Steam Relief Valve (Dwg.: 40141CS03/G 4) Valve Mfg.: Crosby 2 C 6 SV/SA C RVT/RR M(5023-I 2.5) 2
*- SPSV8417, Main Steam Relief Valve (Owg.: 40141CS03/G-3) Valve Mfg.: Crosby
.2 C 6 SV/SA C RVT/RR- M(S023-I-2.5) 2
- 3PSV8418, Main Steam Relief Valve-(Dwg.: 40141CS03/G 3) Val.e Mfg.: Crosby 2 C 6 SV/SA t RVT/RR M(S023-I-2.5)- 2
=* S3130lMU003 (4-003-D-620), Check Valve on Steam Supply from E088 to AFP Turbine K007 (Dwg.: 40141CS03/F-1) Valve Mfg,: Anchor / Darling a 3 C 4 CK/SA C CVP0/0P T(S023-V-3.S.4) 1&l8 VRR-18 3 C 4 CK/SA C CVTC/RR M(S023-I-6.160) 1&l8 VRR-18 3 C 4 CK/SA C CVT0/CS 0(1.ater) 1&l8 VRR-18
- S3130lHU005 (4-005-D-620), Check Valve on-Steam Supply from 0089 to AFP Turbine K007 (Dwg.: 40141CS03/E-2) Valva Mfg.: Anchor / Darling
;p) 3 C 4 -CK/SA C' CVP0/0P T(S023-V 3.5.4) 1&l8 VRR-18 3 C 4 CK/SA C CVTC/RR M(5023-I-6.160) 1&l8 VRR-18 3 C 4 CK/SA C CVT0/CS O(Later) 1&l8 VRR-18 ATTACHMENT 4 PAGE 51 0F 52
it-NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 143 0F 208
<~Y ATTACHMENT 4
() TCN 7*16 UNIT.3 10/16/91 Inservice Testing Program for Valves San Onofre Nuclear Generating Station (TestOrg's: H Maintenance, 0 Operations T - Technical) Discussion of Cold Shutdown Intervals, see Next Att. Valve Test Notes and See and Type Test Valve Code XI hize Actuator Norm and Str. Organization Relief Class Cat (in.) Type Pos. Mode Time (Procedure) Requests
*' $3130lMUO27 (3/4 027 F-636), Instrument Air Supply Check Valve for 3HVC419 (Dwg.: 401415030/D-6) Valve Mfg.: Anchor / Darling 2 AC 3/4 CK/SA C AT/RR 0(S023-3 2.18.1) 12 0(S023 3 3.30) 12 2 AC 3/4 CK/SA C CVTC/0P
- S3130lMUO34 (3/4-034-P 536), Instrument Air Supply Check Valve for -
3HV8421 (Dwg.: 40141503C/E-5) Valve Mfg.: Anchor / Darling 2 AC 3/4 CK/SA C AT/RR 0(S02?-3 2.18.1) 12
- 2 AC 3/4 CK/SA C CVTC/0P 0(S023-3-3.30) 12
/
\
%) ** System: Sumps and Drains
* 'PiV5803, Containment Sump to Radwaste Sump (Dwg.: 40ll7AS03/E-2). Valve Mfg.: WKM 2 A 3 GA/M0 0 AT/RR -
T(S023-V-3.13) 3,5,6&l0 2 .A 3 GA/M0- 0 BTC/0P 18 0(S023-3-3.30) 3,5,6&l0
-2 A _3 GA/MO O PIT /RR 0(S023 3-3.30) 3,5,6&l0
- 3HV5804, Containment Sump to Radwaste Sump Isslation Valve '
(Dwg.: 40ll7AS03/E-1) Valve Mfg.: Fisher 2 A 3 CA/A0 0 AT/RR T(5023-V-3.13) 3,5&l0 2 A 3 GA/A0 0. BTC/0P 5 0(S023-3-3.30) 3,5&l0 2 A 3 GA/A0_ 0 FSTC/0P 0(5023-3-3.30) 3,5&l0 2 A 3 GA/A0 0 PIT /RR 0(5023-3-3.30) 3,5&l0 g ATTACHE NT 4 PAGE 52 0F 52
. . .- - . . .. . - - ~-
NUCLEAR' ORGANIZATION ENGINEERING PROCEDURE S023-V 3.5 UNITS 2 AND 3 REVIS10N 7 PAGE 144 0F 208 ATTACHMENT 5 (W) . TCH 7-16 UNIT 3 JUSTIFICATION FOR VALVES NOT. TESTED QUARTEklY
** System: Auxiliary Feedwater
'* S31305MU121 (6-121 D 598), AFP 3P140 Supply to -S/G E089 Exercising this valve while.the plant is at power would result in placing unnecessary thermal stresses on the feedwater piping, which could result .in. premature' failure of _this piping.
=
- S31305MU126 (6-126-D 598), AFP 3P141 Discharge Check Valve Same as S31305Mul21..
- S31305MU532.-(6 532 0 598), AFP 3P504 Discharge Check Valve.
Same as $31305Mul21.
* 'S31305MU5;7 (6-547-D 598), AFP 3P140 Discharge Check Valve c Same as-S31305MU121.
** System: Boric Acid Makeup-4
- 13HV9235,'BAMU Tank T072 to Gravity Feed to Charging Pump Suction 77 Opening this valve would result in injecting highly concentreted boric (J acidLinto th1 reactor;ccolant system,. causing plant shutdown.
2* ' sHV9240, -8 AMU Tank T071; to Charging Suct ton Header Control Valve Same:as HV-9235.
*E3HV9247, BAMU Pump-to. Charging Pump Suction Control Valve Same'as HV-9235.
- S31218MUO33:. (3-033 D-675),~ Boric Acid Makeup ~ Pump'3Pl?5 Discharge Check Valve Full' stroke exercising of this valve during plant. power operation
=would ' result in over-boration of the reactor coolant. system and plant
. shutdown.
*' 531218MUO35 (3-035-D-675),: Boric Acid Makeup Pump 3Pl74-Discharge Check Valvo Same as S31218MUO33. .
** System: Chemical and Volume Controi
* -3HV9200, Charging Pumps to Regenerative Heat. Exchanger E063
-Exercising while the plant -is at power would isolate normal charging to the RCS. This wouldiresult~ in non-compliar.ce with Technical. '
Specification' 3.1.2.2', which requires two flow paths for_ boration during power operation, n
'(" JL *' 3HV9205, Regenerative Heat Exchanger E063 to Letdown Heat Exchanger
-Exercising this valve during power operation would result in unnecessary thermal transients.on_the regenerative heat exchanger and reactor coolant system charging nozzles.
ATTACHMENT-5 PAGE 1 0F 12 e & 'v V
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 145 0F 208 i n ATTACHMENT 5 7-16 (f TCN UNIT 3 JUSTIFICATION FOR V7LVES NOT TESTED QUARTERLY
- 3LV02278, VCT Outlet Valve Closing this valve requires shifting charging pump suction and injecting highly concentrated boric acid into the RCS, causing plant shutdown.
- 3TV9267, Letoou Containment Isolation Valve Same as HV-9205.
- S31208MUO15 (4 015-C-675), VCT to Charging Pump Suetior Check Valve Same as LV-0227B, S31208MUO82: (3 082-C-675), Gray Feed - BAMU Tanks to Charging Pump s
3P190 Suction Same as HV9235.
- S31208MUO83 (3 083-C-675), BAMU Pumps to Charging Pumps Suction Header Same as HV9235.
-* S31208MU130 (2-130-0-334), Contmt Isol. - Chg Pump Disch to Aux.
r3 Spray Regen HX Bypass Q Exercising this valve while the plant is at power would result in unnecessary thermal transients on the pressurizer spray nozzle.
*t System: Component Cooling Water
- 3HV6211, CCW Non-Critical Loop-to Containment Isolation Valve Exercising this valve during operation would secure or-direct cooling water flow from RCP seals, which could result in seal damage and plant shutdown.
- 3HV6212, CCW From Hent Exchanger E001A to Non-Critical Loop Same as HV-6211.
- 3HV6213, Component Cooling Water Discharge to Non-Critical Loop Same as HV-6211.
- 3HV6216, Isolation Valvo - CCW Ncn-Critical Loop from Containment Same as HV-6211.
* -3HV6218, CCW Pump Suction from Non-Critical Loop Same as-HV-6211.
- 3HV6219, CCW Pump Suction from Non-Critical loop Same as HV-6211.
- r w
- 3HV6223, Isolatiot Valve - CCW Non-Critical Loop Containment inlet
) -Same as HV-6211.
- 3HV6236, Containment isolation - CCW Non-Critical Loop Return
-Same as HV-6211.
ATTACHMENT S PAGE 2 0F 12
25; NUCLEAR ORGANIZATIOW ENGINEERING PROCEDURE S023 V-3.5 UNITS:2 AND 3 REVISION 7 PAGE 146 0F 208 e ATTACHMENT 5 7-18 ( TCN UNIT 3 > JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY - !
- 3HV6500, Component Cooling Water from SDCS Heat Exchanger E003 Same as HV-6211. .
*
- 3HV6501, Component Cooling Water from SDCS Heat Exchanger E004 l Same as HV:6211.-
- S31203MU101 (28-101-D 725), CCW Pump 3P024 Discharge Check Valve ;
Full-stroke exercising of this valve during power operation would require civwting CCW from the Reactor Coolant Plant seals, which . would result in seal damage and plant shutdown.
- S3120iMU102 -(28-102-D-725), CCW Pump 3PG26 Discharge Check Valve Same as S31203MU101.: .
- S31203Mul03 (28-103 D-725), CCW Pump 3P025 Discharge Check Valve Same-as-S31203MU101.
S31203MU264l (1-264aD 627),-Nitrogen Supply to Component Cooling Water Surge Tank T003A . Stroke -Test requires placing the affected CCW loop out of service. '
' )N * . S31203MU265 (1-265-D 627), Nitrogen Supply to Component Cooling Water Surge Tank T003A
- Same as S31203MU264. ,
.,
- S31203MU266: (1-266-D 627), Nitrogen Supply to Component Coolir.g Water Surge Tank T004B
.Same as S31203MU264.
- S3'1203MU267 -(1-267-0-627), ~ Nitrogen Supply to Component Cooling Wahr Surge Tank-T004B Same as S31203MU264-S31203MU268 (1268-D-627), Nuclear Plant' Service Water Supply to CCW Loop A
'St.me as S31203MU264.
* 'S31203MU269 (1-269-D f 27), Nuclear Plant Service Water Supply to CCW Loop B Same as'S31203MU264.
** System: Condans ce and Feedwater-
'* 3HV1105, S/G E089 Feedwater Bypass Valve Exercising this valve during plant operation would disturb steam f generator level control and could restilt in plant shutdown.
V
- 3HV1106, S/G E088 Feedwater Bypass Valve Same as HV 1105.
ATTACHMENT 5 PAGE 3 0F 12 e - -e-* q p
J l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5-UNITS--2 AND-3 REVISION 7 PAGE 147 0F 208 n Y ATTACHMENT 5 7-16 i TCN m) . UNIT 3 JUST'FICATION FOR VALVES NOT TESTED QUARTERLY
- 3HV4047, feedwater Block Valve - Staam Generator E08C Full-stroke exercising this valve during power operation would result in loss of feedwater flow to the steam generator, which could result in a, plant shutdoven.
- 3HV4048, Feedwater Isolation Valve Steam Gancrator E088 Same as HV 4047.
- 3HV4051, Feedwater Block Valve - Steam Generator E009 Same as HV-4047.
- 3HV4052, Feedwater Isolation Vilve - Steam Generator E089 Same as HV-4047.
- S31305MUO3G '(20-036 C-609), Main Feed Check Valve at Steam Generator E089
- The valve cannot be stroked during any mode in which main feed must remain uninterrupted. It therefore can only be stroked open when main feed is . initiated following a plant shutdown. ,
p(" /
- S31305HU124 (6-124+C-599), AFW Check Valve at Steam Generator E089 Exercising this valve while the plant.is at power would result in placing unnecessary thermal stresses on the feedwater piping, which could result in premature faiiure of this piping.
- S31305Mul29 (20129-C-609), Main Feed Check Valve at Steam Onerator
. E088 This valve cannot be stroked during any mode in which main feed must retrain uninterrupi.ed. It therefor- can only be stroked open when main feed is initiated following a plar, shutdown.
- S31305MU448 (6-448-C-599), AFW Check Valve at Steam Generator E088 Same as S31305Mul24.
** System: Containment HVAC (Normal)
- 3HV9948, Containment Purge Supply See Valve Relief Request No.19. This valve is passive except in Modes 5 and 6, at which time it is tested. In addition, exercising this valve during plant power operation would result in non-complic.ce with the Technical Specifications.
- 3HV9949, Containment Purge Supply Same as HV-9948, q
- 3HV9950, Containment Furge Exhaust jg Same as HV 9948.
- 3HV9951, Containment Purge Exhaust Sa'rie as HV-9948. .
ATTACHMENT 5 PAGE 4 0F 12
n NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023 V 3.5 REVISION 7 PAGF 148 0F 200 UNITS 2'AND 3 ATTAC'iMENT 5 (^T ( ,/ TCN __7 _13 UNIT 3 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
** System: Containment Spray
- 3HV8150, Isolation Valve - SDCS Heat Exchanger E004 to LPSI Header Applying power or opening this valve while the plant is at power would result in non compliance with the T.rchnical Specification. Opening this valve could defeat both iains of LPL.
- 3HV8151, Isolation Valve - SDCS Heat Exchanger E003 to LPSI Header Same as P'-8150.
- S31206MU004 (8 004 C-406), Spray Header #1 Containment Isolation Stop Check Valve Exercising this valve with flow either during operation or cold shutdown would result in a spraydown of the containment building.
- S31206MU006 (8 006.r,-406), Spray Header 32 Containment Isolation
,p Check Valve Same as $31206MU0v .
/~'
- S31206MUO12 (8 012 C-406), Spray Pump 3P012 Discharge Stop Check Valve V) Full stroke exercising of this valve while the plant is at pomr would require disabling both trains of LPSI.
- S31206MUO14 (8-014 C 406), Spray Pump 3P013 Discharge Stop Check Valve Same as 531206MUCl2.
- S31206MUO29 (8 029-C-645), Spray Pump 3P012 Discharge to SDCS HV E004 Check Valve Same as S31206MU012.
- S31206MUO30 (8-030-C-645), Spray Pump 3P012 Discharge to SDCS HV E003 Check Valve
- Same as S.'1206MUO12.
** System: Fire Protection
- 3HV5686, Containment Isol. Fire Protection (Outside Containment)
Exercising this valve during plant operation will activate the Fire Protection system in the Unit 3 Containment building.
** System: Fuel Stor. Pool & Refueling
- 3LV0227C, RWST to Charging Pump Suction Opening this valve wauld result in injecting highly concentrated boric acid into the reactor coolant system, causing plant shutdown.
7
)
- S31219MU052 (6-052-C 675), RWST T006 to Charging Pump Suction Header Same as LV-02270.
ATTACHMENT 5 PAGE 5 0F 12
NUCLEAk ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 149 0F 208
's ATTACHMENT 5
) TCN _7 ~ 113 Uh!T 3 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
** System: Reactor Coolant
- 3HV0296A, Reactor Head Vent This valve is part of the Reactor Coolant system Boundary isolation.
Opening this valvs while the Reactor Coolant System is pressurized would release Reactor Coolant to the vent' system. Further, power is normally removed from the solenoid.
-* 3HV0296B, Reactor Head Vent This valve is part of the Reactor Coolant system Boundary isolation.
Opening this valve while the Reactor Coolant System is pressurized would release Reactor Coolant to the vent system. Further, power is normally removed from the solenoid.
- 3HV0297A, Pressurizer Vent Valve This valve is part of the Reactor Coolant system Boundary isolation.
Opening this valve while the Reactor Coolant System is pressurized would release Reactor Coolant to the vent system. Further, power is normally removed from the Jolenoid.
)
- 3HV02978, Pressurizer Vent nlve This valve is part of the Reactor Coolant system Boundary isolation.
Opening this valve while the Peactor C M ;nt System is pressurized would release Reactor Coolant to the w a system. Further, power is normally . removed from.the solenoid.
- 3HV0298, Vent to Contmt from Reactor Head / Pressurizer This valve is not considered accessible during power operation.
Further, power is normally removed from the solenoid. ,
- 3HV0299, Quench Tank Inlet from Reactor Head / Pressurizer Vent This valve is normally inaccessible during power operation. Further, power is' normally removed from the solenoid.
- 3HV9201, Regenerative Heat Exchanger E003 to Auxiliary Spray Exercising this valve while the plant is at power would result in unnecessary thermal transients and stress on the pressurizer spray nozzle.
- 7 V9202, Regenerative Heat Exchanger E063 to RCS Loop 2A Thi. .alve must remain open during power operation in order to ensure consistency with assumptions made regarding system flow to the RCS cold legs in the accident analy!.is and to comply with the intent of LCO 3.5.2.
s
- 3HV9203, 0,eDenerative Heat Exchanger E063 to RCS Loop 1A
, ) Same as HV-9202. J ATTACHMENT 5 PAGE 6 0F 12 i .
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5
-UNITS 2 AND 3 KEVISION 7 PAGE 150 0F 208 .s ATTACHMENT 5
(<j) TCH _1 - 1 n UNIT 3 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
- 3HV9204, RCS Loop 2B to Regenerative Heat Exchanger E063 Exercising this valve during power operation would result in unnecessary thermal stress transients on the regenerative heat exchanger and reactor coolant system charging nozzles.
- 3HV9217, DCS Blnd Off to Volume Control Tank Exercising this valve could result in Reactor Coolant Pump seal failure and subsequent reactor shutdown.
3HV9218. RCS Bleed Off to VCT Isolation Valve Inside Containment Same as HV-9217.
- 3TV0221, Letdown Isolation Valve Exercising this valve during power operation would result unnecessary thermal transients on the regenerative heat exchanger and rea: tor coolant system charging nozzles.
S3120lMU019 (2 019-A 554), Auxiliary Spray Check Valve Exercising this v-alve while the plant is at power would result in g3 unnecessary thermal transients on the pressurizer spray nozzle.
'd
- S3120 MUO20 (2-020-A-554), Charging Line Check Valve to RCS Loop 2A This valve cannot be tested without closing HV 9203 (discussed elsewhere in this table).
S3120lMUO21 (2 021-A-554), Charging Line Check Valve to RCS Loop 1A This valve cannot be tested without closing HV-9202 (discussed elsewhere in this table). 53120lMU129 (2-129-A-554), Auxiliary Spray to RCS From Charging Pumps Same as S3120lMU019. S3120lMU200 (14-200-C-645), Pump 3P016 Suction Check Valve This valve can only be exercised when plant is on shutdown coc!eg.
+
S3120lMU202 (14-202-C-645), LPSI Pump Suction Check Valve Same as $31201Fb200.
** System: Resp. & Service Air System
- 3HV5388, Containment Isolation Valve for Instrument Air Exercising this valve during plant power operation isolates instrument air to the Containment building and could result in a plant shutdown.
** System: Safety injection
/]
- 3HV0396, Flow Control Valve mi Pumps to Shutdown Cooling System v Full stroke testing of this valve _uring power operation would result in non-compliance with Technical Specification 3/4.5.2, which requires this valve to be closed with power to the valve operator removed. .
ATTACHMENT 5 PAGE 7 0F 12
~_
NUCLEAR ORGANIZATION ENGlHEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 151 0F 208 r~N ATTACHMENT 5 () TCN _ 7, y UNIT 3 JUSTIFICATION FOR VALVES NOT TE3TED QUARTERL
- 3HVS152, Isolation Valve - SDCS Heat Exchanger E004 Inlet Same as HV 0396.
- 3HV8153, Isolation Valve SDCS Heat Exchanger E003 Inlet Same as HV 0396.
- 3HV8160, Flow Control Valve - SDCS Heat Exchanger Bypass Full stroke exercising of this valve during power operation would result in non compliance with Technical Specification 3/4.5.2, which requires this valve to be open with power removid.
- 3HV8161, Block Valve - LPSI to SDCS Heat Exchanger Bypass Same as HV 8160.
- 3HV8162. Bleck Valve - LPSI Pump 3P015 Miniflow Same as HV 8160.
- 3HV8163, Block Valve - LPSI Pump 3P016 Miniflow Same as HV-8160.
,o (')
- 3HV9337. Isolation Valve - SDCS to LPSI Pump Suction This valve is required by Te:hnical Specification 3/4.5.2 to be interlocked to prevent opening whenever reactor coolant systoi '
. pressure exceeds 376 psia.
- 3H 1, Isolation Valve - Shutdown Cooling System from RCS Loop 2 Same .4 HV 9337.
- 3HV9340, Safety injer. tion Tank T008 Outlet Valve to RCS :.oop 1A Restoring power to this valve or opening this valve while the plant is at power would result in non compliance with the T uhnical Specifications.
- 3HV9345, Safety Ir.jection Tank T008 Vent During power operation, Technical Specifications require power to be locked out for this valve. This prevents inadvertent pressurization of the SIT.
- 3HV9350, Safety Injection Tank T009 Outiet Valve to RCS Loop IB Same as HV-9340.
- 3HV9355, Safety injection Tank T007 Vent Valve 3ame as HV-9345.
- 3HV9360, Safety . Injection Tank T009 Outlet Valve to RCS Loop 2A
(~3 Same as HV-9340.
- 3HV9365, Safety Injection Tank T009 Vent Valve Same as HV-9345.
ATTACHMENT 5 PAGE 8 0F 12 9
NUCLEAR ORGANI'lATION' EnJINEERING PROCEDURE _ S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 152 0F 208 ATTACHMENT 5
/y TCN 7"16 (7 i UNIT 3 JUSTIFICATION FOR VALVES'NOT TESTED QUARTERLY
- 3HV9370, Sarety injection Tank T010 Outlet Valve to RCS Loop 28 Same as-HV 9140.
- 3HV9375, Safety Injection Tank-T009 Vent Valve Same as HV 9345.
- 3HV9377.. Isolation Valve - SOCS Bypass to LPSI Suction Same as HV 9337.
* -3HV9378, Isolation Valve - SOCS Bypass to LPSI Suction Same.as HV 9337.-
* '3HV9420. Control: Valve - HPSI Header #1 to RCS L 2 Hot Leg Same as HV-0396.
- 3HV0434, Control.. Valve - HPSI Header #2 to RCS Loop 1 Hot Leg Same as'HV-0396.
*~ S31204MV012 (4 012 C-358), HPSI Pump 3P017 Discharge Check Valve This valve cannot Se exercised while-the plant is-at power because the j
1 q( j - HPSI pump cannot o.e come RCS pressure. To exercise disc to fully open position requires 200 GPM.
- S31204MU015'(4-015-C 358), HPSI Pump 3P019 Otscharge Check Valve Same as S31204MUO12.
- S31204MU016 (4 016 C 358), HPSI Pump 3P018 Discharge Check Valve Same as S31204MUO12.
1
'* S31204MU017-
-(4 017-C-553), HPSI Pumps 3P018 & 3P019 to #2 High Pressure Header Same-as S31204MUO12.
L - * '531204MU018- .(3 018-A T51)', HPSI Combined Header to RCS Loop 1A Check L .. -
. Valve c Exercising this valve while-the plant is at power would result in L non-compliance with' Technical Specification 3/4.3.5.2.
'4
- S31204MU019 (3-019-A-551) HPSI Combined Header to RCS Loop 18 Check
- Valve L.- Same.as $31204MU018.-
- S31204MUO20-- (3-020-A 551), HPSI Combined-Header to-RCS Loop 2A Check L
l Valve !' Same as $31204MV018.
*DS31204MUO21 .(3-021-A-551), HPSI Combined Header to RCS Loop 28 Check u Valve-
'Same'as $31204MU018.
ATTACHMENT 5 PAGE 9 OF 12-
NUCLDR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 153 0F 208 ,y. ATTACHMENT 5
) TCN *z~1n UNIT 3 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
- S31204MUO24 (10-024 C-406), LPSI Pump 3P015 Discharge Stop Check Valve While the plant is at power, LPSI pumps cannot overcome RCS pressure.
Additionally, aiigning the system discharge to the RWST would defeat both trains of List.
- S31204MUO25 (10-025 C-406), LPSI Pump 3P^16 Discharge Stop Check Valve Sama as S31204MUO24.
- S31204MUO27 (12 02/ A 551), Safety injection Headers to RCS Loop 1A Check Valve During power operation, there is no full flow path available to stroke test this valve. Neither the LPSI nor HPSI pumps can overcorge the RCS pressura. Requires 2000 gpm for full stroke.
- S31204MUO29 (12-029-A-551), Safety injection Headers to RCS Loop IB Check Valve Same as $31'204MUO27.
- S31204MUO31 (12-031 A-551), Safety injection Headers to RCS Loop 2A fm Check Valve
) Same as S31204MUO27.
- S31204MUO33 (12-033-A-551), Safety injection Headers to F.CS Loop 2B Check Valve Same as S31204MUO27.
- S31204MUO40 (12-040-A 551), Safety injection Tank T008 Outlet Cneck Valve Opening this valve during power operation .is not possible against normal RCS operating pressure. A partial stroke test is the only test possible during Cold Shutdown due to system configuration. See Valve Relief Request Number 11.
- S31204MUO41 (12-041-A-551), Safety injection Tank T007 Outlet Check Valve Same as S31204M7040.
- S31204MUO42 (12-042-A 551), Safety.Irjection. Tank T009 Outlet Check Valve Same as S31204MUO40.
- S31204MUO43 (12-043-4 551), Scfety Iajection Tank T010 Outlet Check Valve Same as S31204MUO40.
n
- S31204MUO72 (8-072-A-S52), LPSI to RCS Loop 1A Check Valve
(#) There is no flow path to exercise this valve during power operation. LPSI pumps cannot overcome RCS pressure while the plant is at power. ATTACliMENT 5 PAGE 10 0F 12
F NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 9 _ UNITS-2 AND 3 REVISION 7 PAGE 154 0F 208 m ATTACHtiENT 5 7-10 (v)- TCN UNIT 3 1UST!*! CATION FOR VALVES NOT TESTED QUARTERLY
'* S31204MUO73 (8 073 A-552), Lril to RCS Loop 1B Check Valve Same as S31204MUO72.
- S31204MUO74 (8-074 A 552), LPSI to RCS Loop 2A Check Valve Same as S31204MUO72.
- S31204MUO75 (8 075-A 552), LPSI to RCS Loop 2B Check Valve Same as S312047,0072.
- 531204MUO87 (16-087 C-675), Containment Spray Pump 3P013 Suction Check Valve Same as S31206MUO12.
- S31204MUO88 (16-088 C-675), Containment Spray Pump 3P012 Suction Check Valve Some as S31206MU012.
- S31204Mul50 (3-152-A 551),_To #2 HPSi Header Valve cannot be stroked at power because the HPSI pumps cannot (7 overcome Reactor Coolant System pressure. Additionally, opening the
~~~ ') HPSI Header Isolatior' Valve during power operation would result in ncn-compliance with Technical Specification 3/4.5.2.
S31204HU155 (3 155-C-551),'HPSI Header #1 to RCS Loop #2 Hot Leg Exercising this valve while the plant is at power would result in non-compliance with Technical Specification 3/4.3.5.2. ~ In-addition, while the plant is at power, HPSI pumps cannot overcome RCS pressure.
- S31204MU156 -(3-156-A-551), HPSI Header #1 to RCS Loop #2 Hot Leg Inlet Check Valve Same as S31204MU155.
S31204MU15/ (3-157-A 550), hPSI Header #1 to RCS Loop #1 Hot leg Same as S31204Mul55.
'* S31204MU158'(3-158 A-550), HPSI Header #1 to RCS Loop #2 Hot Leg Same as S31204MU155.
** System: Steam
- 3HV0204,. Steam Generator E089 Main Steam Isolation Valve (MSIV)
Full stroke exercising at full plant power would cause a loss of 50 % of our host removal from the primary coolant system, a reactor trip on assymetric power in the core and actuation of the steam and pressurizer (primary) reliefs.
,4 -
> ('") 3HV8205, Steam Generator E088 Main Steam Isolation Valve (MSIV)
Same as HV-8204. ATTACHMENT 5 PAGE 11 0F 12
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 155 0F 208 [ 6
) N UNIT 3 JUSTIFICATION FOR VALVES NOT TESTED QUARTERLY
- 3HV8419, Main Steam Dump to Atmosphere Full stroke exercising this valve during power operation could result in a reactor plant. transient due to energy released via the steam dump.
- 3HV8421. Main Steam Dump to Atmosphere Same as HV-0419.
\m f~, V ATTACHMENT 5 PAGE 12 0F 12
r s
~ NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND .REVIS10N 7 PAGE 156 0F 208 ATTACHy*i6-I6 TCN ASME XI
.-TABLE IWV 3510 1 CATEGORY C.- SAFETY AND RELIEF VALVES Testing Schedule
~iime Period Number of Valves to be Tested
-Startup . Minimum of N /60 x total valves in this through 1st' category (Noke(1))
.. refuel ing -
- Ist refueling- - Additional valves to make cumulative tested through 2nd: at.least N,/60 x total valves in this refueling -category-(Note (l)]
- 2n'd refue' ling- ' Additional valves to make cumulative' tested -
.f\ through.3rd at least N /6 Q refueling etc.
category, .dc.0 x total
-(Note (l)] valves in this.
4 NOTE.
. (1)' N refuelibg.. N ,. N , 'etc'..Lare the numbers of When
.$eco$drefueling,thirdrefueling,etc. months N from is -a' startup numbertolarger
' first.-
than 60,. all; valves which have not been tested =during the preceding 5 year period shall be tested. The following-period'shall then be considered to be the sar.a as "startup to first refueling"J for purposes of determining test frequency, with the added requirement that at each refueling,all valves which have not.been tested during the preceding 5 year-period shall be tested.1The .
. subsequent period:.will~be consiciered the same as the first refueling.to the
-second refueling,' etc., with N determined by counting months from the new starting. point.
O 0155d-7T.wSIL ATTACHMENT 6 PAGE 1 0F 1
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023-V-3.5 l Uh?TS 2 AND 3 REVISION 7 PAGE 157 Of 208
, ATTACHMENT 7
; TCN 7-16 0
VALVE RELIEF REQUEST INDEX VRR No. Subiect PJLqt 1 (Withdrawn - justification for Reactor Coolant system check valve 3-152 A-5F1 was moved to the cold shutdown table) 160 2 Alternate Testing for Safety Injection System Check ValtOs; 24-001-C-724, RW Tank 2T005 to Spray Pump 2P012 Suction Header, and, 24-002-C-724, RW Tank 2T005 to Spray Pump 2P013 Suction Header 161 3 Alternate Testing for Safety Injection System Check Valves; C4-003-C-724, Outlet Check Valve - Containment Emergency Sump, and, 24-004-C-724, Outlet Check Valve - Containment Emergen y Sump ,
. 166 4 (Withdrawn - justification for Safety injection system check valve 3-155-C-551 was moved to the colv, shutdown table) 169 m 5 (Withdrawn - justification for Safety injection e;; ten check I
() valve 3-156-C-551 was mnved to the enld shutdowr. table) 170 6 (Withdrawn - justification for Safety Injection system check valves 3-157-A 550 and 3 158 A-550 were moved to the cold shutdown table) 171 7 (Withdrawn - justificatior for Safety Injection system check valves 4-012-C 358, 4-015-C-358, and 4-016-C-358 were move; to the cold shutdown table) , 172 8 Alternate Testing for Safety Injection System Check Valves; 10-006-C-675 HPSI Pumps 2P017 and 2P018 Suction Check Valve, and, 10 008-C-675, HPSI Pumps 2P018 and 2P019 Suction Check Valve 173 (Withdrawn - justification for Safety Injection system check valve 4-017-C-553 was moved to the cold shutdown table) 174 10 (Withdrawn - justification for Safety Injection system check valves ~3-018 A-551, 3-019-A-551, 3 020-A-551 and 3-021-A-551 were moved to the cold shutdown table) 175 11 Alternate Testing for Safety Injection System Check Valves; 12-040-A-551, Safety injection Tank T008 Outie Check Valve, 12-041-A-551, Safety Injection Tank T007 Outlet Check Valve, , m 12-042-A-551, Safety Injection Tank T009 Outlet Check Valve, ( 1 and, 12-043 A-551, Safety Injection Tank T010 Outlet Check L V' Valve 176 ATTACHMENT 7 PAGE 1 0F 48
i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3,5 UNITS 2 AND 3- REVISION 7 PAGE !!8 0F 208 W ATTACHMENT 7 (v ) TCN T*16 VALVE RELIEF REQUEST INDEX (Continued) i VRR No. Sub_iect P_gg 12 Alternate ld'np for Safety injection System Check Valves; 16 077-C 645, LPSI Pump 2P016 Suction Header Check Valve, 16-084 C-645, LPSI Fump 2P015 Suction Check Valve, 16199 C 645, t. PSI Pur.n 2P015 Suction Header Check Valve, and, 16 201 C-645, LPSI Pump 2P015 Suction Header Check Valve 179 13 Alternate Testing for Containment Spray System Check Valves; 8 004-C-406, Containment Isolation Stop Check Valve - 5) ray
- Header #1, 8 006 C-405, Containment Isolation Stop Chec(
Valve - Spray Header 82 182 14 Alternate Testing for Chemical and Volume Control System Check Valve 2-122-C 554, Charging Pumps Check Valve to Regen Heat Exchanger E063 185 15 (Withdrawn - Testing of HVAC system valves 2(3)HV7800, 2(3)HV7801,2(3)HV7802,2(3)HV7803,2(3)HV7805,2(3)HV7806, p; A 2(3)HV7810 and 2(3)HV781) only if a containment purge is not in progress) 186 16 All Power Operated Valves 187 17' (Withdrawn - Testing of the vacuum breaker on the spray additive tanks (Valve 2-159-C-611)) 189 x _18- Alternate Testing for Main Steam System Check Valves; 4-003-D-620, Steam Supply - S/G E088 to AFP Turbine K007 Check Valve, and, 4-005-D-620, Steam Supply - S/G E089 to AFP Turbine K007 Cneck Valve 190 19 -(Withdrawn - Testing of HVAC system valves HV9948. HV9950, HV9949 ano HV9951 at cold shutdown intervals is explained in tM cold shutdown table) 193 L 20 Alternate Testing for Condensate and Fee 6 ater System Check Valves; 20 036-C 609, Main Feed Check at steam Generator E089, and, 20-129-C-609, Main Feed Check at Steam Generator E088 194 n 21 (Withdrawn - HV-8204 and HV-9949 will be exercised as required by the code. Valvt Test Interval Justification l moved to Cold Shutdown Tables) 197
/V 22 (Withdrawn - Containment Spray valves 2-054-C-611 ar.d 2-069-C-611 will be exercised open quarterly) 198 p ATTACHMENT 7 PAGE 2 0F 48 L
, _ n . -
HUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 159 0F 208 ATTACHMENT 7 f) TCN 7*16 a VALVE RELIEF REQUEST INDEX (Continued) yRR No. PJLqt SubJrn 23 Use of Average / Reference Stroke time in determining entry into increased frequency testing (ALERT) 199 24 Determining the portion of Cold Shutdown interval valves to be tested in an outage 201 25 Atmospheric Dump Valve Stroke Testing frequency 203 v,O G V ATTACHMENT 7 PAGE 3 0F 48
/ NUCLEAR ORGANIZATION ENGINEERING PROCCDURE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 160 0F 208
,e ATTACHMENT 7 !, 3u,j TCH 7-16 '
1 VALVE RELIEF REQUEST NO. 1 This VRR was withdrawn by letter, SCE to NRC, Docket No. 50 361, - July 5, 1983. The refueling interval testing justification for ' Reactor Coolant system check valve 3-152 A 551 was moved to the cold shutdown table. (~h
) , 's t
ATTACHMENT 7 PAGE 4 0F 48
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5
-UNITS 2 AND 3 REVISION 7 PAGE 161 0F 208 , <m ATTACHMENT 7
( ) TCN T~16 v , VALVE RELIEF REQUEST NO. 2 System: Safety injection Components: Safety Injection System Check Valves: 24-001 C-724, RW Tank 2T005 to Spray Pump 2P012 Suction Header, 24-002 C 724 RW Tank 2T005 to Spray Pump 2P013 Suction Header Class: 2 Function: These valves prevent back-flow frem the High Pressure Safety Injection Suction Header, Low Pressure Safety injection Suction Header and Spray Pump Suction header to the Refueling Water Storage Tanks (RWST's). Test Requirement: IWV 3411, exercise these valves open and closed every three months. Basis for Relief: INTRODUCTIQB The source of flow to these valves is borated water from the RWST's, the pumps that produce flow 1.hrough these valves are- the High pressure Safety-Injection (HPSI) Low Pressure Safety injec-tion (LPSI) and Containment Spray pumps. They discharge into the Reactor Coolant System (RCS) or containment building spray nead-
.ers.
These safety injection system check valves prevent post accident recirculation flow from escaping the normal flow path into the RWST. Plant conditions can be grouped into three test situations with respect the these valves; (1) RCS Pressurized and at normal operating temperature, (2) RCS depressurized and cooled down, and,(3) RCS open during refueling. These conditions are dis-cussed below: (3 (J ATTACHMENT 7 PAGE 5 0F 48
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.S UNITS 2 AND 3 REVISION 7 PAGE 162 0F 208 ATTACHMENT 7 fq TCN 1-16 j VALVE RELIEF REQUEST tl0. 2 (Continued) Basis for Relief: (Continued) (11 RCS PRESSURIZED AND AT NORMAL OPERATING TEMPERATURE These valves cannot be full-stroked using flow during power operation, for the following reasons:
- a. The HPSI (shutoff head 1500 psi) and LPSI (shutoff head 200 psi) pumps are unable to overcome RCS system pressure (nomi-nal operating pressure = 2000 psi). There is no full fics recirculation to the RWST from either pump.
As a result, only pump recirculation through the miniflow line is produced using these pumps while the RCS is pressur-ized. Although this is sufficient for a partial stroke test, flow for a full-stroke test is not available.
- b. A quarterly test at power, using the only available flow path, would either inject borated water into the RCS or r3 spray down the containment building: or both, if injection
( ,) were possible during operation, the test would not be per-formed because the result would be an immediate, uncontrolled and complete reactor shutdown (as a result of the borated water) and/or flooding and resultant degradation of tha components and systems located in the containment building (as a result of the containment building spray down),
- c. The containment spray pumps chnnot be utilized to full-stroke these valves using flow, as the only full flow path during plant operation is through the containment spray header and nozzles.
(2) RCS DEPRESSURIZED AND COOLED DOWN These valves cannot be full-stroked using flow during cold shut-down for the following reasons:
- a. IEf~ WILL ALL PUMPS IN A LOOP: Sufficient flow to fu. .roke the RWST outlet check valves is not achievable in u ;s condition. Return flow from the HPSI and LPSI pump discharge lines is very limited, consisting of mini-flow recirculation lines and RCS vent lines.
- b. TESTING WITH THE CONTAINMENT SPtaY PUMP: The containment m Spray (CS) pumps have a 6" recirculation line to the RWST's, I) but these pumps by themselves cannot develop full-stroke
\-- flow for the RWST outlet check valves. ATTACHMENT 7 PAGE 6 0F 48
NUCLEAR ORGANIZAT:0N ENGINEERING PROCEDURE S023-V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 163 0F 208 ATTACH 1ENT 7 (n. v) TCN 7"16 VAI.VE RCLIEF REQUEST NO. 2 ~, (Continued) Basis for Relief: (Continued) f2) RCS DEPRESSURIZED AND COOLED DOWN (Continued)
- c. JESTING WITH THE i_ PSI PUMPS:
Stroking the RWST outlet check valves with flow from the LPSI pumps is pr+ ibited by the Technical Specifications in Cold Shutdown bt; w e the LPSI pumps must be aligned to take suction from tu RCS to provide shutdown cooling during this mode of operation. The LPSI pumps cannot, therefore, take a suction through the RWST outlet check valves.
- d. TESTING WITH THE HPSI PUMPS: The equivalent of the combined CS, LPSI, and HPSI flowrate cannot be developed with the HPSI pump alone. The HPSI pumps cannot be used to exercise these valves during cold shutdown because of the risk of exceeding cooldowm rate limits. The barated water in the RWST is normally at an ambiciit temperature of = 6fd F and the cooled down RCS is nominally at = 13S' F.
A e. CONCLUSIORt The Code required testing of the RWST outlet t kj check valves while the plant is in Cold Shutdown could only be performed after significant redesign of the system, such as the addition of an instrumented full flow test line. (3) RCS OPEN DUJING REFUELING
- a. ELQW PATH: The RWST outlet check valves are in the 24" supply line to the suction headers of the HPSI, LPSI and Containment Spray Pumps. To full-stroke the RWST outlet check valves using flow during refueling with tne Reactor Vessel head removed, would require that the system achieve a test flow of approximately 6500 gpm (full accident flow).
There is one check valve for each of the two trains of pumps. Full flow from the RWST through the check valves of interest is only achieved with all of the pumps in oae train running at the same time (one HPSI pump, one LPSI pump and one Spray pump). A large flow could be achieved in the refueling mode during refueling cavity fill. The HPSI, LPSI and containment Spray pumps could take a suction from the RWST and discharge to l the RCS. With the Reactor Pressure Vessel head removed, flow would first fill and then overflow the Reactor Pressure Vessel into the Refueling Cavity. p V l l ATTACHMENT 7 PAGE 7 0F 48 l l l
- . . - -.-, - - - . . - . .. ~ .--
l i NUCLEAR ORGANIZATION- ENGINEERING PROCEDURE _ S023.V 3.5 UNITS 2 AND 3- REVISION 7 PAGE 164 0F.208
. ATTACHMENT 7 TCN 7-18 i
VALVE RELIEF REQUEST NO. 2 1 (Continued) Basis for Relief: (Continued) f31 RCS OPEP DURING REFUELING (Continued)
- b. CAQLDOWN LIMITSt The only discharge path that exists for this flow is into the core through-the safety injection headers to the cold legs and/or the 6" recirculation line from the Containment Spray pump discharge to the RWST (this 6* line alone has insufficient capacity for the full stroke of the RWST outlet check valves using flow). The borated '
water in the RWSi-is normally at an ambient temperature of
= 65' F and the Cooled down RCS-is nominally at = 136' F.
Injection of the borated RWST water could result in a cool-down rate in violation of the Technical Specifications (See Figure 3.4-5, RCS Maximum Allowable Cool-Down Rates) for the reactor vessel. CONCLUSION From the above discussion, it can be seen that no allowable flow path exists in any plant mode for a full-stroke of the RWST_ cutlet g check valves using flow. Testing of these valves could only be accomplished after significant redesign of the system, such as installation of a fully instrumented' full . flow test loop. NRC l Generic Letter 89-04 Attachment 1,:_Pasition 2, identifies partial-disassembly and inspection as-an acceptable alternative for
- stroking a valve when it is impractical to use flow, in this case, there is no way to stroke these. valves'with the existing system design using flow.
TEST SCHEDULE Disassemble and inspect both of'these valves each refueling outage y requires the associated piping to.be drained. This generates a , significant--amount of liquid radioactive waste. In addition, l: considerable radiation exposure can be received by personnel-performing the partial . disassembly, hand stroking and inspection.
- ' -As a consequence,_there is a clear advantage in reducing the number of partial disassembly and hand stroking tests required in each refueling.
l l I ATTACHMENT T PAGE 8 0F 48
NUCLEAR ORGAN!ZAT!0N ENGINEERING PROCEDURE 5023 V-3.5 UNITS 2 AND 3 REVISION 7- PAGE 165 0F 208 i ATTACHPLENT 7 (O TCN 7"16 LJ VALVE RELIEF REQUEST NO. 2 I (Continued) l Alternate Testing: Quarterly, perform a partial stroke test (open) of each valve using system flow. At each refueling outage, test the valve by partial disassembly, inspection and manual stroking on a rotating basis (one valve per refueling). During partial disassembly, the valve internals will be visually inspected for worn or corroded parts, and the valve disk will be manually exercised. If it is found that the full stroke capabili-ty of the disassembled valve is in question, the other valve will be similarly disassembled and inspected and manually full stroked during the same outage. Following reassembly, the valve will be tested by partial stroking using system flow. We will actively pursue the use of non-intrusive diagnostic techniques to demonstrate that these valves twing fully open during partial flow testing, when another method is developed to verify the full-stroke capability of these check valves, this relief request will be revised or withdrawn. U Notes: (1). The NRC Safety Evaluation Report transmitted by letter, L. E. Kokajko (NRC) to H. B. Ray (SCE) and G. D. Cotton (SDG&E), Safety Evaluation Report of the Inservice Testing (IST) Program for Pumps and Valves, September 24,1990, Table 1, has required that a full stroke test using flow be accomplished at refueling intervals for these valves. (See NRC SER, 1 4.2.2.3) Relief was denied for partial disassembly and inspection. (2) This version was submitted by letter, R. H. Rosenblum to NRC, Inservice Test.4..;. Program for Pumps and Valves TAC Nos. 55120/1, July 31, 1991. (3) NRC approval of the current version, above, was documented in letter, James 2. Dyer to H. B. Ray and G. D. Cotton, Safety Evaluation of Licensee Responses to Staff's Technical Evaluation Report Items and Revised Relief Requests to the IST Program for Pumps and Valves, October 2, 1991. l l L)C ATTACHMENT 7 PAGE 9 0F 48
- . . - . . -- -.- - . - .. . , - - . - ~ . - . - . . - . - - . - .
NOCLEAR ORGANIZATION . ENGINEERING-PROCEDURE: 5023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 166 0F 208 - ATTACHMENT 7
, TCN Tala VALVE ret.IEF REQUEST NO. 3
' System: Safety _ injection Components:
-Safety Injection System Check Valves:
24 003-C-724, Outlet Check Valve Containment Emerqancy Sump
-24 004 C-724, Outlet Check Valvo Containment Emergancy Sump Category: C Class: 2 ,
Function:- These valves open to provide recirculation flow from the contain- 4 ment sump to the suction piping of the HPSI, LPSI and Containment : Spray pumps, . tTest Requirement: IWV 3411, exercise these valves every three months, [ Basis for Relief: Test Methodoloav
@ MAL PLANT OPERATION
-The only source of water to the inlet of the containment sump
-outlet check valves is the containment building sump -During ,
normal plant operation this sump is required-to be-kept dry and-the isolation vahes shut, This system lineup precludes either full-stroke or partial stroke of these check valves _ using flow in thi s - mode ,-- f f f O ATTACHMENT 7 PAGE 10 0F 48
- _. . - . _ _1._, _ _.~. . .--. .._. _ . _ _ _ . . - . _ . - . , _ _ . _ . . -
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 167 0F 208 ATTACILMENT 7 TCN T*16 [O-) VALVE REllEF REQUEST NO. 3 (Continued) Basis for Relief: (Continued) pp1D SHUTDOWN AND REFUELING MODES In cold shutdown or reactor refueling modes, part stroke exercis-ing of these valves is possible with flow from the containment sump, however, the sump is not maintained at a cleanliness level consistent with the internals of the Safety injection or Reactor Coolant system piping. The cleanup of the containment sump to a cleanliness level consistent with the internals of the Safety injection or Reactor Coolant system would be labor intensive. If part stroke exercising were conducted by filling the sump with water and flow testing these valves, this would potentially contaminate the safety injection systems, the refueling water storage tank, and/or the reactor coolant system with low quality water. This contamination of the systems would cause accelerated corrosion and degradation. Extensive flushing and cleanup follow-ing such testing would therefore be required. b%./ CONCLUSION The Code required testing could only be performed after signifi-cant system modifications involving considerable costs. These system modifications would involve additional containment pene-trations and long runs of large diameter piping with associated supports and isolation valves. NRC Generic Letter 89-04, Attach-ment 1,' Position 2, identifies partial disassembly and inspection as an acceptable alternative for stroking a valve when it is impractical to use flow. In this case, there is no practical way to full-stroke these check valves using flow with the existing system design. IELT SCHEDULE Disassembly and inspection of these valves each refueling outage requires the associated system piping to be drained. This gener-ates a significant amount of liquid radioactive waste. This generates a significant amount of liquid radioactive waste. In addition, considerable radiation exposure can be received by personnel performing the partial disassembly, hand stroking and inspection. As a consequence, there is a clear advantage in reducing the number of these tests required in each refueling. D (v ATTACHMENT 7 PAGE 11 0F 48
I NUCLEAR ORGANIZATION ENGINEERING PROC 'URE S023-V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 168 0F 208
, ATTACHMENT 7 f ,' TCN 7"16 O
VALVE REllEF REQUEST N0, 3 (Continued) Alternate Testing: The valves will be partially disassembled, inspected and manually full stroked at each refueling outage on a rotating basis (one valve per refueling). During partial disassembly, the valve internals will be visually inspected for worn or corroded parts, and the valve disk will be manually exercised. If it is0found that the full stroke capability of the disassembled valve is in question, the other valve will be similarly disassembled and inspected and manually full stroked during the same outage. A method of partial flow testing will be developed and used following the partial disassembly and prior to returning the valve (s) to service. Additionally, we will actively pursue the use of non-intrusive diagnostic techniques to demonstrate that these valves swing fully open during partial flow testing. When another method is developed to verify the full-stroke capability of these check valves, this relief request will be revised c r withdrawn. l Note: (1) NRC Safety Evaluation Report transmitted by letter, L. E.
% Kokajko (NRC) to H. B. Ray (SCE) and G, D. Cotton (SDG&E), Safety Evaluation Report of the Inservice Testing (IST) Program for Pumps and Valves September 24, 1990. Table 1, has required that a post inspection, part-st:oke exercise test be performed following the refueling interval partial disassembly and manual stroking.
(2) This version was submitted by letter, R. M. Rosenblum to NRC, Inservice Testing Program for Pumps and Valves TAC Nos. 55120/1, July 31, 1991. (3) This revision commits to a PARTIAI. STROKE TEST of these valves (each valve each refueling). One way this can be accom-plished is using a portable pump discharging clean water to the 2" test connection at the valve inlet (See PalD 40ll2A, Coord. B-6), isolating the containment sump, RWST, L PSI and Spray pumps from the valve outlet and verifying that there is appropriate flow from a vent or drain downstream of the valve under test. (> ATTACHMENT 7 PAGE 12 0F 48
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2_AND 3 REVISION 7 PAGE 169 0F 208 ATTAClHENT 7
,3 TCN 7-10
- ( s)
~
VALVE RELIEF REQUEST NO. 4 This VRR was withdrawn by letter, SCE to NRC, Docket No. 50-361, July 5, 1983. The refueling interval testing justification for Safety Injection system check valve 3 155-C 551 was moved to the cold shutdown table.
!,3 /
1 l l o N ATTACHMENT 7 PAGE 13 0F 48 l
NOCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3' REVISION 7 PAGE 170 0F 208 ATTACHMENT 7 TCN 7-16 Q[
-VALVE RELIEF REQUEST No. 5 This VRR was withdrawn by letter, SCE to NRC, Docket No. 50 361, July 5, 1983. The refueling interval testing justification for Safety injection system check valve 3 156 C-551 was moved to the cold shutdown table.
V ATTACHMENT 7 PAGE 14 0F 48 l
l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 171 0F 208 s ATTACHMENT 7 ' i TCN 7-16 (s_/-
- VALVE RELIEF REQUEST NO. 6 This VRR was withdrawn by letter, SCE to NRC, Docket No. 50-361, July 5,1983. The refueling interval testing justification for Safety Injection system check valves 3-157 A 550 and 3-158 A 550 were moved to the cold shutdown table.
0 O 9 l 1 ATTACHMENT 7 PAGE 15 0F 48
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3- REVISION 7 PAGE-172 0F 208
- ATTACliMENT 7 TCN 7-10
(]s-VALVE RELIEF REQUEST NO. 7 This VRR was withdrawn by letter, SCE to NRC, Docket No. 50 361, July-5, 1983. The refueling interval testing justification for Cafety injection system check valves 4 012-C-358, 4-015 C 358, and 4-016 C-358 were moved to the cold shutdown table.
- o .
F ATTACHMENT 7 PAGE 16 0F 48 a _ . - - -
- . - . - . - - - - . - - ~ . . - - .. - -..
=
N, e
- ! NUCLEAR ORGANIZATION - .
ENGINEERING PROCEDURE -S023-V-3.f ' PAGE 173 Oi 208' W$ tUNITS 2-AND 3; REVISION 7 ATTACHMENT 7-TCH 9' - 1 6 -
. VALVE RELIEF REQUEST NO.-8 System:; . Safety: Injection Components:
Safety injection System Check Valves: 10-006-C 675, HPSI Pumps 2P017 and 2P018 Suction Check Valve, and, 10 008 C-675. HPSI Putos 2P018 and 2P019 Suction Check Valve. Category C Class:- 2 Function: These valves open to allow a flow of water. into the suction. piping of the high; pressure safety. injection pumps.- Test Requirementi , IWV-3411, exercise these valves every three months. g . Basis for Relief: :
' - This check valve cannot be full stroke exercised during power acerations because the high pressure safety injection pumps cannot overcome. reactor coolant system pressure. During cold shutdown-full stroke' exercising this valve could result-in.a low tempera -
ture over pressurization of: the; reactor coolant system. Alternate Testing: These valves will be full stroke exercised at each refueling, h while using the high pressure safety injection pumps to fill the-refueling pool canal, and part stroke exercised quarterly during routine inservice testing of the HFSI pumps. Notes:. (1). This version was submitted by letter, SCE to NRC.. Docket'Nos. 50-361, July 5, 1983-(2) This Relief Request has been approved. See NRC Safety Evalcation Report transmitted by letter,-L. E. Kokajko-(NRC) to H. B._ Ray-(SCE) and G. D. Cotton (SDG&E), Safety Evaluation. Report of-4 S e Inservice Testing.(IST) Program for Pumps and Va'iis, i.e deptember 24,1990, ' Table 1- and TER,1 4.2.2.1. l L ' O ATTACHMENT 7 PAGE 17 0F 48 D orr .myp; tgay ,g g at
.W = g .4 -
,ggg pyg e gw ec es. 4y-+g ---gw.- '
- 2 NUCLEAR ORGAN!ZATIGN ENGINEERING PROCED,URT. S023-y 3.5 UNITS 2 AND 3 -REVISION 7 PAGE 174 0F 208 ATTACHMENT 7
{}- ICN 7-16 VALVE RELIEF REQUEST NO. 9 This VRR was withdrawn by letter, SCE to NRC, Docket No. 50-361, July 5, 1983. The refueling interval testing justification for Safety injection system check valve 4-017-C-553 was moved to the cold shutdown table.. l u I 4 5 h I \.J A 4 h ef v e ( ATTACHMENT 7 PAGE 18 0F 48 l l
NUCLEAR ORGANIZATION ENGINEERING PROCENRE 5023-V-3.5 l UNITS 2 AND 3 REV1310h i PAGE 175 0F 208 ATTACHMENT 7 TCN _ h o VALVE RELIEF REQu'iST NO 10 This VRR was withdrawn by lettee, 5CE to NRC, Docket No. 50 361, July 5, 1983. The refueling intet val testing justification for Safety injection system check valves 3-018 A 551, 3-019-A-551, 3-020-A-551 and 3-021 A 551 were moved to the cold shutdown table. O O ATTACHMENT 7 PAGE 19 0F 48
- p. _. _ __ ___ _ - . _ . _ - - ~
dy
.d a
-NUCLEAR ORGAN!ZATION ENGINEERING PROCEDURE 5023 V 3.5--
~
- UNITS-2 AND 3 REVISION 7 PAGE 176 Of 208- j
- ATTACHMENT-7 -l TCN 7-16 VALVE RELIEF REQUEST NO. 11 ;
hp^ i$ystem: Safety injection 1 Components: Safety Injection System Check Valvesi 12 040.A-551, Safety injection Tank T008 Outlet Check Valve, 12 041.A 551, Safety injection Tank T007 Outlet Check Valve,
-12 042 A 551, safety injection Tank T009 Outlet Check Valve, and, 12 043-A-551, Safety injection Tank T010 Outlet Check Valve.
Category: AC , Class:' 1 W : Function:' ' These valves open to allow a flow of water from the Safety Injec-tion Tanks into the Safety injection Header of each Primary loop.
' Test" Requirement:- !
IWV-3411, exercise these valves every three months.
~ Basis -for Relief: ,
QRING NOMM. OPERATION- $ These check valves cannot be stroked during normal operation
-without violating the Technical Specification requirements for.
safety injection tank pressure and level bands. In addition, these valves cannot be full strcked.except under &ctual loss of .; H coolant accident conditions, .i.e. no full flow path available. ; i
-A. The SIT pressure is = 600 psi and cannet overcone RCS system-
-pressure (nominalioperating' pressure = 2000 ps'l). As a- '
result, no flow through 'those check valves is possible ! during normal operation. ] K b. A quarterly test at power using flow (if it were possible) would not be performM because it would inject borated water ' into the RCS. If injsetion were possible during operation, the result would be an imediate, uncontrolled and complete reactor shutdow (as a result of the borated water). I LO ATTACHMENT 7 PAGE 20 0F 48
i , 2 NUCLEAR 0RGANIZAT10N ENGINEERING PROCEDURE S023-V-3,5 m , -UNITS 2 AND 3 REVIS10N 7- PAGE 177 0F 208 ; ATTACHMENT _7 l TCN 7 - 1.6 VALVE RELIEF REQUEST NO. 11
/ (Continued) w *
' Basis for Relief: (Continued)
DURINLCQLD SHtJTDOWN OPERATION I During cold shutdown, a full-stroke using flow cannot be accom-plished because it could lead to a low-temperature over pressurization of the RCS due to-the 1 sci o. uxpansion volume ; necessary to accommodate the large quantity of water which must be discharged into the RCS. Further, this flow path is not equipped _ i with the flow rate instrumentation necessary to_ verify a ! full-stroke of these check valves. , CONCLUSION Code required testing can only be performed after significant modifications, such as installation of an instrumented test loop full-stroke testing.these valves using flow. The high costs of-
-the necessary design changes-involved would not be justified by the improvement of the valve testing. Further, the addition of
-valves and piping--to the system could result in reduced plant Oy- reliability. NRC Generic Letter 89 04, Attachment 1 Position 2, M identifies partial disassembly and inspection as- an acceptable
-alternative for stroking a-valve when it is impractical'to use flow. In this case, there is no way to full-stroke these valves with the existing system design using flow.
TEST SCHEDULE Because of its effect on_the operability.of the associated equip-ment, performing _a test by partial disassembly and hand stroking requires' considerable manipulation of plant conditions and imposes - significant restrictions on-the structure of a refueling outage. Because of the need for draining systems in order to disassemtle the valves, performance of these tests generates a significant amount of radioactive liquid waste. Considerable radiation expo-sure can received by personnel performing the tests. As a conse-quence, there is a clear advantage in reducing the number of these tests required in each refueling.- ,
- Alternate Testing:
Partial stroke test these check valves on a cold shutdown inter-val. At refueling intervals, test these valvos by partial disassembly e and hand stroking. The valve internals shall be visually inspect-ed for worn or corroded parts, and the valve disks shall be 4 manually exercised, ATTACHMENT 7 PAGE 21 0F 48 __ _ __ _ _. . s _ _.
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 178 0F 208 ATTACHMENT 7 TCN _7 ig , VALVE RELIEF REQUEST NO. 11 (Continued) i Alternate Testing: (Continued) l It shall be verified that the valve is capable of full-stroking and that the internals of the valve are structurally sound. This testing shall be conducted at each refueling outage on a rotating basis. One valve of this group will be tested each successive refueling outage, until the entire group has been tested. If the disassembled valve is not capable of being full-stroke exercised or there is binding or failure of the valve internals, the remain?ng valves in this group shall also be disassembled, inspected, and manually full stroke exercised during the same outage. A partial flow test shall be performed on the disassembled valve before it is returned to service. Additionally, we will actively M' sue the use of non-intrusive diagnostic techniques to demonstiate that.these valves swing ially open during partial flow testing. When another method is devel-
.O O
oped to verify t!- full-stroke capability of these check valves, this relief request will be revised or withdrawn. Notes: (1) This version was submitted by letter, R. M. Rosenblum to NRC, inservice Testing-Program for Pumps arid Valves TAC Nos. 55120/1, July 31, 1991 (2) This kelief Request has been approved provided a partial flow test is perfonned on the disassembled vcives before they are returned to service and all valves in this group receive a part-stroke exercise on a cold shutdown interval. See NRC Generic Letter 89-04, Position 2, and NRC Safety Evaluation Report trans-mitted by letter, L. E. Kokajko (NRC) to H. B. Ray (SCE) and G. D. Cotton (SDG&E), Safety Evaluation Report of the Inservice Testing (IST) Program for Pumps and Valves, September 24,1990. Table 1. i
- r~r ATTACHMENT 7 PAGE 22 0F 48
, NUCLEAR ORGANIZATION ENGINEERING PROCEDURE' S023-V.3.5 UNITS 2-AND 3- ' REVISION 7 PAGE 179 0F 208
.. ATTACHMENT 7-f 'TCN 7*'6 Lf VALVE RELIEF REQUEST N0, 12 System:. -Safety injection Components:-
Safety injection ~ System Check Valves; 16-077 C-645, LPSI Pump 2P016 Suction Header Check Valve,- ' 16 084-C-645, LPSI Pump 2P015 Suction Check Valve, 16-199-C-645, LPSI Pump 2P015 Suction Header Check Valve, and, 16-201-C 645, LPSI Pump 2P015 Suction Header Check Valve. Category:. C Class: 2 Function: These valves open_ to allow a flow of water from the refueling water storage tank (RWST) into the suction piping of the Low , Pressure Safety _ Injection (LPSI) pumps. Test. Requirement: IWV 3411, exercise these valves every three months.
]v~ Basis for Relief:
DlgING POWER OPERATION Full-stroke exercising.of the LPSI pump suction check-valves with
, flow requires the passage of the maximum required accident flow
' rate.through the valves The LPSI suction checks are in the
-suction lines of the associated LPSI pumps and deliver 1 borated water to these pumps'from,the RWST's. The' pumps in' turn discharge
~
to the' RCS ' Shutdown Cooling heat exchanger and the mini-flow recirculation lines (returning tne flow to the RWST's). These-valves cannot be full-stroke exercised using flow during power operation, for the.following reasons:
- a. The mini-flow recirculation lines ::annot provide enough flow through the LPSI pump suction check valves, as the maximum
-flow achievable through this path is less than required accident-flow. Although' this_ is sufficient for a partial stroke test, flow for a full-stroke is not~ available.
b, During-power operation, the Shutdown Cooling System is iso-lated and cannot be used as a flow path because it must remain isolated due to interlocks controlled by Technical j Specification 3.4.5.2.d. l ATTACHMENT 7 PAGE 23 0F 48 lL
NUCLEAR ORGANIZATION -ENGINEERING PROCEDURE S023 V 3.5 .
; UNITS 2 AND 3 REVISION 7 PAGE 180 0F 208 l ATTACHMENT 7 p TCN 7-16 (f
VALVE RELIEF REQUEST NO. 12 (Continued) Basis fcr Relief: (Continued) DJRING POWER OPERATION (Continued)
- c. Injecting water into the RCS during power operation is not possible. The Low Pressure Safety injection (LPSI) pumps (shutoff head = 200 psi) are unable to overcome RCS system pressure (nominal operating pressure = 2000 psi) and there-fore there can be no flow into the RCS in this plant mode.
If a test at power could be conducted, it would result in injection of borated water into the RCS. The result would be en immediate, uncontrolled and complete reactor shutdown (as a result of the borated water). COLD SHUTDOWN The Technical Spacifications require that the LPSI pumps reihain aligned to provide shutdown cooling at all times while the plant is in Cold Shutdown. The LPSI suction check valves are, accord-(3 ingly, bypassed and cannot be full-stroke tested using flow. () Compliance with the Code requirement to perform quarte;'ly testing could only be accomplished aftar a major modification of he system design. The improvement of the testing in cold shutdown would not justify the high-costs involved. Alternate Testing: Quarterly, part-stroke exercise these valves. A flow path exists during the filling of the refueling canal with the LPSI pumps in plant Mode 6 (refueling). The suction of the LPSI pumps can be aligned to the RWST and the discharge to the LPSI header or shutdown cooling header. Flow could then be directed through the LPSI Suction Header Check Valves et full flow (LPSI Pump Design Flow is 4150 gpm at 400 psid) for a-short period of time sufficient to full-stroke these valves with flow. There-fore, the valves will be full stroke exercised using flow at reactor refueling intervals. Notes: (1) Relief has not been granted to allow partial disassembly and inspection on a sampling basis, See NRC Safety Evaluation Report transmitted by letter, L. E. Kokajko (NRC) to H. B. Ray (SCE) and G. D. Cotton (SDG&E), Safety Evaluation Report of the Inservice Testing (IST) Program for Pumps r "alves, September 24, 1990, Table 1. The NRC SER, 1 4.2.2.2, granted relief to part-stroke i G quarterly provided the valves are full-stroked with flow during l () refueling outages. l
- ATTACHMENT 7 PAGE 24 0F 48
h ..ntnTION ENGINEERING PROCEDURE S023 V-3.5 U ,,,. 4 AND 3 REVISION 7 PAGE 181 0F 208 ATTACgENT7"10 TCH VALVE RELIEF REQUEST NO. 12 (Continued) i Notes: (Continued) ) (2) The current version was submitted by letter, R. M. Rosenblum to NRC, inservice Testing Program for Pumps and Valves TAC Nos. 55120/1, July 31, 1991 (3)- NRC approval of the current version, above, was documented in letter, James E. Dyer to H. B. Ray and G. D. Cotton, Safety Evaluation of Licensee Responses to Staff's Technical Evaluation i Report Items and Revised Relief Requests to the IST Program for Pumps and V61ves, October 2, 1991. m 9 v ATTACHMENT 7 PAGE 25 0F 48
1 i NUCLEAR ORGANIZATION EN31NEERING PROLEDURE S023 V-3.5 ) UNITS 2 AND 3 REVISION 7 PAGE 182 0F 208 l ATTACHMENT 7 C l- TCN 7-16 gj-VALVE RELIEF REQUEST NO. 13
-System: Containment Spra)
Components: Containment Sprai System Check Valves; 8 004-C 406, Containment Isolation Stop Check Valve Spray Header #1, 8 006 C-406, Centainment Isolation Stop Check Valve - Spray Header #2, Category: AC Class: 2 Function: These valves open to allow a flow of water from the contai.iment spray pump discharge into the containment spray ring headers. Test Requirement: IWV-3411, exercise these valves every three months. g) k Basis for Relief: FULL FLOW TESTING These valves are in the line leading from the Containment Spray - -- pump discharge to the riser inside the containment building that leads up to the ring headers and spray nozzles. As a consequence full-stroke exercising these valves through this flow path using the containment spray pumps would' result in a containment-spray down and consequent potential equipment damage as well as create additional liquid radwaste to be removed from the Containment Building symp. PARTIAL FLOW TESl @S The riser inside the containment building that leads up to the ring headers and spray nozzles is drained each refueling and refilled prior to returning the plant to service. When the riser is being filled with water, .the water can be put in the system opstream of each stop check valve. Therefore, this flow through the Spray Header Containtaent Isolation Stop Check Valves during the filling of the riser would result in a partial stroke of these valves. f) ! V ATTACHMENT 7 PAGE 26 0F 48
i NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V-3.5 4 UNITS 2 AND 3 REVISION 7 PAGE 183 0F 208 -! ATTACHMENT 7 ; (] TCN 7'16 j LJ l l VALVE RELIEF REQUEST NO. 13 (Continued) Basis for Relief: (Continued) CONCLUSION l A usable flow path does not exist in any pant mode to allow a full-stroke of the Containment Isolation Stop Check Valves for the Spray Headers using flow. The Code required full-stroke testing using flow could only be performed after considerable modification of the system design, such as installation of an instrumented test loop. The high costs of the necessary design changes involved would not be justified by the improvement of the valve testing. Further, the additional valves, piping, supports and penetrations could result in reduced plant reliability. NRC Generic Letter 89-04, Attachment 1. Position 2, identifies partial disassembly and inspection as an acceptable alternative for stroking a valve when it is impractical to use flow, in this case, there is no way to stroke these valves with the existing system design using flow. TEST SCHEDULE [') Disassembly and inspection of both of these valves each refueling U outage requires additional draining of the associated system piping over and above draining the riser as previously discussed. This generates a significant amount of radioactive liquid waste, in additien, considerable radiation exposure can be received by pers".nel performing the partial disassembly, hand stroking and inspection. As a consequence, there is a clear advantage in reducing the nuther of theu tests required in each refueling. Alternate Testing: At each refueling cutage, (1) perform a partial stroke test (open) of each valve using system flow, and, (2) test the valves by partial disassembly, inspection and manual stroking on a rotating basis (one valve per refueling). During partial disassembly the valve internals shall be visually inspected for worn or corroded parts, and the valve disks will be manually exercised, if it is found that the full stroke capabili-ty of the disassembled valve is in question, the other valve will be similarly disassembled and inspected and manually full stroked during the same outege. r~N O ATTACHMENT 7 PAGE 27 0F 48
- . . _ ~ _ .._ ._. _ .._. _ _ _ , _
p
-NUCLEAR ORGANIZATION; ENGINEERING PROCEDURE S023 V-3.5 UNITS 2 AND 3 -REVISION 7- -.
PAGE 184 0F 208
-= ; - s- ATTACHMENT 7-
.TCN 7-1A VALVE RELIEF REQUEST NO. 13.
(Continued) Atlernate Testing:- (Continued)- 4 Following reassembly and-prior to return to service, the valve a will be tested by partial stroking using system flow. Additional- - ly, we will actively pursue the use-of non intrusive diagnostic techniques to demonstrate w at these valves swing fully open , i during partial flow testing. When another method is deveload to ; verify the full-stroke capability of these check valves.:this relief request will be. revised or withdrawn, ,. 1 Notes: .(1) The NRC Safety Evaluation Report transm'itted by letter, L. E. Kokajko (NRC) to H. B. Ray (SCE) and G. D. Cotton (SOG&E), Safety Evaluation Report of the Inservice Testing (IST) Program for Pumps and Valves, September 24,1990, Table-1, has- required that a
- post-inspection, part-stroke exercise test be performed following.
the-refueling interval partial disassembly and manual stroking. Alse- see the NRC SER. -1 4.3.1.~1. (2) The current version was submitted by letter, R. M. Rosenblem to NRC, Inservice Testing Program for Pumps and Valves TAC Nos. 55120/1, July 31,- 1991
-(3) - The revised Alternate Testing adds partic I stroking of the valve following partial disassembly.; Air can~be used to stroke ~
the valve during the period when the riser is dry. The valve motion is confirmed using a listening 1 device on 'the valve body.
~This operation ean.be conducted at the end of-each. refueling outage to-satisfy the'SER requirrte t fcr the.-post-disassembly-partial flow test.
r F O ATTACHMENT 7 PAGE 28 0F 48
_ m NUCLEAR GT,CANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 185 0F 208 _ ATTACHMENT 7 7-In (} v TCN VALVE RELIEF REQUEST NO 14 System: Chemical and Volume Control Component: Check Valve 2 122 A Sb4 Category: AC Class: 2 Function: This valve cpens to allow normal charging flow to the reactor coolant system. In addition, this valve is a containment isola-tion valve in the event of a charging line rupture. Test Requirem6nt: IWV 341'., exercise these valves every three months. Basis for Relief: Verifying closure of this valve requires a seat leak test (Appen-dix"J'), Seat leak testing of tnis valve requires isolating n normal charging and draining a portion of the charging line. This i would violate Technical Specification 3.1.2.2 which requires two (d boration flow paths Alternate Testing: This va:ve will be verified closed during refueling outages whi'.e performing Appendix "J" testing. Also, this valve will be exer-cised open quarterly curing toutine inservice testing of the charging pumps. Notes: (1) The NRC Safety Evaluation Report transmitted by letter L. E. Kokajko (NRC) to H. B. Ray (SCE) and G. D. Cotton (SDG&E), Safety Evaluation Report of the Inservice Testing (IST) Program for Pumps and Valves, September 24,1990. Table 1, approved this relief request. See the NRC SER, 1 4.4.1.1. (2) ..e current version was subtitted by letter, SCE to NRC, Doc k". No. 50 361, July 5, 1983. J ATTACHMENT 7 PAGE 29 0F 48
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION / PAGE 186 0F 208 l ATTAcigENT7-10 TCH VALVE RELIEF REQUEST NO. 15 This VRR was withdrawn by letter, SCE to NkC. Docket Nos. 50 361 and 50 352, inservice Testing Prograin for Pumps and Valvss. TAC Nos. 55120/1 Hay 18. 1990. Testing of HVAC system valves 2(3)HV7800, 2(3)HV7801, 2(3)HV7802. 2(3)HV7803 ?(3)HV7805 2(3)HV7806, 2(3)HV7810 and 2(3)HV7811 "only if a containment purge is not in progress", was not acceptable to the NRC and is an unrecessary restriction on the testing. The purge can be secured if conflicts arise during IST. This NRC recomendation to with-draw was discussed in a telephone conversation with the NRC on December 11. 1989. O 4 O ATTACHMENT 7 PAGE 30 0F 48
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 187 Of 200 ATTACHMENT 7 [-) v TCH 7*10 VALVE REllEF REQUEST HO. 16 System: All Systems Components: All Power Operated Valves Category: A and B Class: 1, 2 and 3 Function: N/A Test Requirement: IW 3413(c): If an increase in stroke time of 25 % or more from the previous test for valves with stroke times greater than 10 sec, or 50 % or more for valves with stroke times less than or equal to 10 sec. is observed, test frequency shall be increased to ' once each month until corrective action is taken, at which time the original test frequency shall be resumed. Bisis for Relief: O lt has been observed through surveillance testing and corrective t'j action that thn repeatability of velve stroke times for valves with short stroke times is sporadic and independent of 6grada-tion. For valves with rapid stroke time' compliance with the stroke time trending and corrective action requirements of the Code is impractical because much of the difference in stroke times from test to test comes from inconsistencies in the operator or timing device. Therefore, compliance with the Code requirements would of ten result in costly maintenance when no degradation has actual-ly occurred. An alternative acceptable to the NRC staff regarding stroke time measurements for rapid acting valves is explained in detail in Generic letter 89 04, Attachment 1, Position 6. Alternate Testing: Valves with stroke times of 2 seconds or less are referred to by the NRC as ' rapid acting valves." An increase in stroke time of 50 % or more for a rapid acting valve (stroke time of 2 seconds or less) shall not resuli; in a test frequency increase to once each month. However, if a valve stroke time does exceed its maximum stroke time value, it shall be declared inoperable, t
<3 b
ATTACHMENT 7 PAGE 31 Of 48
t NUCLEAR ORGANIZAT!DN ENGINEERING PROCEDURE 5023 V 3.5 L UNITS 2 AND 3- REVISION 7 PAGE 188 Of 208 ATTACHMENT 7 O TCN 7*16 VALVE RELIEF REQUEST NO. 16 (Continued) Notes: (1) This Relief 1 Request has been approved, provided the 2 second definition of 'Ropid Acting Volve' is used. See NRC Safety Evaluation Report transmitted by letter, L. E. Kokajko (NRC) to H. B. Ray (SCE) and G. D. Cotton (SDG&E), Safety Evaluation Report of the Inservice Testing (IST) Program for Pumps and Valves, Septem-ber 24,1990. Table 1 and Attac1ed TER f 4.1.2.1. (2) The cur ent version was submitted by letter, R.-M. Rosenblum to NRC, inse . ice Testing Program for Pumps and Yalves TAC Nos. 55120/1, Jult .il, 1991 O i O ATTACHMENT 7 PAGE 32 0F 48
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 189 Of 208 ATTACHMEN1 7 TCN 7"16 [mv) VALVE RELIEF REQUEST NO. 17 This VRR was withdrawn by letter, SCE to NRC, Docket Nos. 50 361 and 50 362, Inservice Testing Program for Pumps and Valves, TAC Nos. 55120/1, May 18, 1990. Testing of the vacuum breaker on the s> ray additive tanks (Valve 2159 C 611) is no longer needed since tiis system has been decommissioned and is not longer in service, g n L) ATTACHMENT 7 PAGE 33 Of 48
y;ymm3 7 . )3,;: f, p$ ' pjtw ,r.6ANIZAT10N ENGINEERING PROCEDURE S023 V 3.5 . .J 4 W .il i AND 3 REVISION 7 PAGE 190 0F 208 g/ ATTACHMENT 7 TCN 7"18 VALVE RELIEF REQUEST NO. 18-
- System: Nain Steam Components:
Main Steam System Check Valves; 4 003 D 620, Steam Supply S/G E088 to AFP Turbine K007 Check Valve, and, 4 005 D 620, Steam Supply S/G E089 to AFP Turbine K007 Check Valve.
^ttegory: C Class: 3 Function:
These valves are in the main steam supply to the turbine driven auxiliary feedwater pump. In the event of a main steam line break, these valves provide reverse flow check-to isolate the affected steam generator. Test Requirement: IWV 3411, exercise the valves every three months. Basis-for Relief: The AFP steam supply check valves are in the steam supply lines from the main steam system to the inlet of the steam driven AFP turbine trip and throttle valves. SURING PLANT OPERATION , During normal plant ' operation,- main steam pressure tends to open these valves. No pressure source exists to reverse this pressure in the-~ steam line where these valves are located and allow detec-tion of valve closure or valve leakage.: Consequently, with the - present system design, verifying the closure of the AFP Steam Supply check valves by leak testing or with reverse flow, while the. plant is operating,-is not sractical._. Although a temporary external pressure source could )e hooked up to .the down stream piping, and apply reverse pressure to these check valves, the required valve lineup would cause the associated auxiliary feedwater pump to be-inoperable during the test. O ATTACHMENT 7 PAGE 34 0F 48 r-, , , r A. n ..-,m -.,,.e.-n- -rr-----.-,- --*rer-,--e s- -cs, + - - "7--'-
NUCLEAR ORGANIZAT10N ENGINEERING PROCCDURE S02 M 1.5 REVISION 7 PAGE 191 Of 208 UNITS 2 AND 3
=q f ATTACHtiENT 7 7-16 i Q
TCN VALVE RELILF REQUEST NO. 18 ! i (Continued) Basis for_ Reliefs (Continued) QQlt1NG COLD $HlfiD0WN OR REFUELING N00ES Regardless of pla.nt mode, there is no positive means of verifying that the valve disc travels to the closed position. System ! connections, such as vents and drains (and appropriate line isola-tion valves) are not present in the system to allow verification ; that a pressure differential exists across the AFP Steam Supply check valves when they are in the closed position. GONCLUSION
-Testing of these valves could only be accomplished after signifi. !
cant redesign of the system, such as installation of additional isolation valves and appropriate vents and drains in the high pressure steam piping. The high cocts of the necessary design changes involved would not be justified by the improvement of the
-valve testing. Further, the addition of valves, supports and necessary piping modifications could result in reduced plant Os - reliability. NRC Generic Letter 89 04, Attachment 1 Position 2, identifists partial disassembly and inspection as an acceptable alternative for stroking a valve when it'is impractical to use flow. In this case, there is no way to test these check valves .
closed with the existing system design using reverse flow or ! pressure. IUl_EHDlM Disassembly and inspection of both of these-valves each refueling . outage requires the associated system piping to be opened up. This is a.significant effort requiring substantial manpower and refueling outage time. As a consequence, there is a clear advan. tage in reducing the number of these tests required in each refueling. Alternate Testing: l Quarterly, perform a partial stroke test (open) of sch valve using system flow.- At each refueling outage.. test the valves hy. partial-disassembly, inspection and manual stroking on a rotating - basis tone valve per refueling). j
,o '
l ATTACHMINT 7 PAGE 35 0F 48 l.
^
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE $023.V 3.5 ! UN!TS 2 AND 3 REVISION 7. PAGE 192 0F 208 ATTACHMENT 7 t O 1CN 7-16 l VALVE RELIEF REQUEST NO. 18 ;
' Alternate Testing: (Continued)
During partial disassembly the valve internals will be visually l inspected for worn or corroded parts, and the valve disks shall be manually exercised, if it is found that the full stroke capabili- ; ty of the disassembled salve is in question, the other valve will ! be similarly disassembled and inspected and manually full stroke i exercised during the same outage. Followinij reassembly and prior ! to return to service, the valve will be tes;ed by partial stroking : using system flow. , We are actively pursuing the use of non intrusive diagnostic !
+
techniques such as-acoustics or radiography to demonstrate that these-valves close when subjected to reverse flow conditions. -!f another method is develo)ed to verify the reverse flow closure ; capability of these chec( valves, this relief request will be revised or withdrawn. j Notes: (1) This Relief Request has been approved provided we perfonn o . partial stroke test using flow following reassembly of the hand i p stroked volve and prior to returning it to operable status, See .7 NRC Safet Evaluation Report transmitted by letter, L. E. Kokajko ; (NRC) to~ . 8. Ray (SCE) and G. D. Cotton (SDG&E), Safety Eval- ' untion Report of the Inservice Testing (IST) Program for Pumps and Valves, September-24,1990. Table-1 (and 14.5.1.1), and NRC Generic Letter 69 04,-Position 2. ; (2) The current version was submitted by letter, R. M. Rosenblum I to NRC, inservice Testing Program for Pumps and Valves TAC Nos. 55120/1, July 31,1921 (3) NRC approval of the current version, above, was documented in , letter, James E. Dyer to H. B. Ray 'and G. D.- Cotton, Safety . i Evaluation of Licensee Responses to Staff's Technical Evaluation Report-Items and Revised Relief Requests to the IST Program for Pumps and Valves October 2, 1991. l I
}
O - ATTACHMENT 7 PAGE 36 0F 48-i
,_.-_4 .~_,_.-.,_,,.<_-.,_,_-.._._.._a..,._,,..-~,., ..__._,...,_,_,.,..-,M.,m,._- ,, . , a, . _.~.-r-.-_, ,,,c..,
l NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 REVISION 7 PAGE 193 Of 208 ! UNITS 2 AND 3 ATTACHMENT 7 ! O , TCN 7 a 1 n i VALVE RELIEF REQUEST N0. 19 This Relief Request is not necessary See NRC Safety Evaluation Report transmitted by letter, L. E. Kokajko (NRC) to H. B. Ray . f$CE) and G. D. Cotton ($DC&E). Safety Evaluation Report of the
,nservice Testing (IST) Program for Pumps and Valves. September 7 24,1990 Table 1. Also. see NRC SER,14.7.1.1.- This VRR was withdrawn by The current version was withdrawn by letter. SCE to j NRC, Docket No. 50 361 and 50 362 Status of NRC Safety Evaluation '
Report, Appendix C. Items for the Inservice Testing Program for Pumri and Yalves. April 12, 1991. An official withdrawn version
-was trassmitted by letter, R.N. Rosenblum to NRC, inservice !
Testing Program for Pumps and Valves TAC No.s $5120/1, June 18, 1991. Testing of HVAC system valves HV9948. HV9950. HV9949 and i HV9951 at cold shutdown intervals was explained in the cold ; shutdown table. . 1 O l i r O ATTACHMENT 7 PAGE 37 0F-48
. ~ _ . .. a .- -
?
NUCLEAR ORGANIZATION ENGIN(ERING PROC [ DURE $023 V 3.5 : UN115 2 AND 3 REVISION 7 PAGE 194 0F 208 ! ATTACHMENT 7 O- TCN 7-16 .! VALVE REllEr REQUEST N0. 20 System: Condensate and Feedwater ; Componentst-Condensate and Feedwater System Check Valvest 20 036 C 609, Main Fied Check at Steam Generator [089, and, ! 20129+C 609, Main Feed Check at Steam Generator E088. Category: C. s Class: 2 , Function:. ! These check valves are in the main feedwater supply to the steam: , generators. During a loss of feedwater accident, these check i valves will close isolating the main feedwater piping from auxil-inry feedwater flow. lest Requirement: IWV 3411, exercise these valves every three months. [ Basis for Relief: i i INTRODUCTION : The main. feed check'valvos at the Steam Generators prevent reverse _; flow from exiting the steam generators in the event of a. feed line break between the steam generator feedwater inlet nozzle and the first power operated isolation v41ve inside conteinment. DURING POWER OPERATION These check valves pass full feedwater flow into each steam generator during power operation, the check valves remain fully
- open and cannot be closed without disrupting the feedwater flow ;
into the associated steam generator. . If. the Check valve were . closed for test.-the resulting reduction of feedwater flow would .i
- cause control of the steam generator-level to be lost, resulting in a plant trip.- ,
t LO ATTACHMENT 7 PAGE 38 0F 48 y f $ . . .;3 ,. ...___....,.__.,_._,...,__.n,.._..__ , _ . _ , . . - . . _ . . . _ . . _ . . ,_ _ :
NUCLEAR ORGANIZATION ENGINEERING PROC [ DURE 5023 V 3.5 UNITS 2 AND 3 REVISION 1 PAGE 195 Of 208 ATTACHMENT 7 (c) \ / TCH 7~10 VALVE RELIEF REQUEST NO. 20 (Continued) Basis for Relief: (Continued) DElliG COLD SH4IEQFJLMDEEULL11tG flow is not present during cold shutdown, however, thero are no test connections installed in this system to enable leak testing of these valves to verify closure. No instrumentation is in-stalled in this system which could enable closure verification of these valves by measuring reverse differential pressure across the valves nor are these valves equipped with position indication. CaliEW$10li Compliance with the Code requirements could only be achieved after a significant redesign of the system. The high costs of the necessary design changes involved would not be justified by the improvement of the valve testing. Further, the addition of valves, supports and necessary piping modifications could result in reduced plant reliability. NRC Generic letter 89 04, Attach-n inent a Position 2, identifies partial disassembly and inspection ( ) as an acceptable alternative for stroking a valve when it is impractical to use flow. Ifil_$C!lEEULE Because of its effect on the operability of the associated equip-ment, performing these tests requires considerable manipulation of plant conditions and imposes significant restrictions on the structure of a refueling outage. As a consequence, there is a clear advantage in reducing the number of these tests required in each refueling. Alternate Testing: At cold shutdown intervals, perform a full stroke test (open) of each valve using system flow. At each refueling outage, test the valves by partial disassembly, inspection and manual stroking on a rotating basis (one valve per refueling). During partial disassembly the valve internals shall be visually inspected for worn or corroded parts, and the valve disk will be manually exercised, if it is found that the full stroke capabili-ty of the disassembled valve is in question, the other valve will g be similarly disassembled and inspected and manually full stroked during the same outage. ATTACHMENT 7 PAGE 39 Of 48
NVCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 196 Of 208 e ATTACHMENT 7 ( TCH 7-16 VALVE RELIEF REQUEST NO. 20 (Continued) Alternate Testing: (Continued) Following reassembly and prior to return to service, the valve will be tested by p:rtial stroking using system flow. We are actively pursuing the use of non ittrusive diagnostic techniques such as acoustics or radiography to demonstrate that these valves close when subjected to reverse flow conditions. If another method is developed to verify the reverse flow closure capability cf these check valves, this relief request will be revised or withdrawn. Notes: (1) This Relief Request has been a) proved, See NRC Safety Evalua-tion Report transmitted by letter, L. E. Kokajko (NRC) to H. B. Ray (SCE) and G. D. Cotton (SDG&E), Safety Evaluation Report of the Inservice Testing (!$T) Program for Pum ber 24,19')0, Table 1 and NRC SER,14.6.1.ps Reifff wasand Valves, Septem-granted provided we part-stroke exercise the volve tu 4e open position withflowofterreassembly. /^\ U (2) The current version was submitted by letter, R. M. Rosenblum to NRC, inservice Testing Program for Pumps and Valves TAC Nos. 55120/1, July 31, 1991 (3) NRC approval of the current version, above, was documented in letter, Jares E. Dyer to H. B. Ray and G. D. Cotton, Safety Evaluation of Licensee Responses to Staff's Technical Evaluation Report items and Revised Relief Requests to the IST Program for Pumps and Valves, October 2. 1991. (3 w) ATIACHMENT 7 PAGE 40 0F 48
NUCLEAR ORGANIZATION ENGINEERING PROCEDURL $023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 197 Of 208 ATTACHMENT 7 O TCH 7-10 VAL.VE RELIEF REQUEST NO. 21 This Relief Request is no longer necessary and this version was withdrawn by letter. SCE to NRC. Docket Nos. 50 361 and 50 362, Au9ust 21, 1987. HV 8204 and HV 9949 will be exercised as re-quired by the code. Valve Test Interval Justificat.on coved to Cold ihutdot:n Tables (Attachments 3 and 5) O i i O ATTACHMEN' i PAGE 41 0F 48
1 NUCLEAR ORGANIZATION ENGINEERING PROCEDURE 5023 V 3.5 k UNITS 2 AND 3 REVISION 7 PAGE 198 Of 708 i I
" ATTACHKENT 7 '
-TCN 7*16 :
I VALVE RELIEF REQUEST No. 22 l This Relief Request is no longer necessary and this version was i withdrawn by-letter, SCE to NRC. Docket Nos. 50 361 and 50 362, i April 4, 1985. Containment Spray valves 2 054 C 611 and ! 2 069 C 611 will be exercised open quarterly. ! l l i I e I O ATTACHMENT 7 PAGE 42 0F 48 ; _._.._..m.- ___ . _ . - , _ __-.. _ ._...m-_ - _ . . _ . . . . . _ _ _ _ . _ _ _ _ = . . . _ _ _ . .
ENGINEERING PROCEDURE 5023 V 3.5 REVISION 7 PA3E 199 0F 208 ATTACH #NT7 ' 3 TCH ,,,, * ~ 1 6 (d ; YE RELIEF 9EQUEST NO. 23 td Valves if ali increase in stroke time of 25 % or more from est for valves with stroke times greater than 10 nore for valves with stroke times less than or is observed, test freqvoney shall be increased to Jntil correctivo action 12 taken, at which time t frequency shall be resumed. the orevious t ui oftea causes a needless and \ - try into the increased frequency of testing. A suit of low value cen often occur iunediately tenance in which, for example, the stem is lubri-test after a normal 92 day interval, can result ne normal valve stroke time. If the difference o times is more than that allowed <25 % (or < 50 11 be put in the increased frequency of testing ective action. This happens frequently and causes ; subject of corrective action even when they are erly and normally, e or everage value of valve stroke time for st data versus the previous stroke time is a native to Code requirements, While still being in the Code, a continual increase in valve stroke period could result in significant valve degrada-test frequency being increased or corret.tive en. This is because the test data is compared ious stroke time and each incremental increase in d be less than that specified in Paragraph mparing tett results to a reasonably derived n average stroke time insures that such an not occur, while at the same time eliminating ective action. lue of stroke time used for comparison of test bQ stablished when the valve is known to be in gond ion. ATTACHMENT 7 PAGE 43 0F 48
)
l
\
NUCLEAR ORGAN!!ATION- ENG;NEERING PROCEDURE SO:3.Y.3.5 UNITS 2 AND 3. RIVISION 7 PAGE 200 0F 208 : l g- ATTACHgEN17
-TCN
- LO VALVE RELIEF REQUEST NO, 23 (Continued)
Alternate Testing:- ! Instead of the previous stroke time, use a Ef1MEL.illL0KE TIME, f i If an increase in stroke time of 25 % or more f.*om the Rf1MKE STROKE TIM for valves with stroke times greater than 10 sec. (or !
$0 % or more for. valves with stroke times less than or equal to 10 ;
sec.)-is observed, test frequency shall be increased to once each month until corrective action is taken, at which time the original j test frequency shall be resumed. j REFERENCE Sit 0KE TIMI is the average stroke time since the last #
--maintenance that could have affected stroke time (or last thrce strokes,whicheverisgreater). The RflMEL$1Glif._Ijlt[-value :
if used for comparison of test data shall tie c3tablished when the ; valve is known to be in good opeiating condition. Notes (1) The current version was submitted by letter, R. M. Rosenblum < to NRC, inservice Testing Program for Pumps and Valves TAC _ Nos. 55120/1, July 31,1991, i O . . (2) This Relief Request has been approved. NRC Safety Evaluation Report transmitted by letter L. E. Kokajko (NRC) to H. B. Ray-
-1 l
(SCE) and G. D. Cotton (SDG&E),-Safety Evaluation Report of the inservice Testing (IST) Program for- Pumps and Valves September
- 24. 1990, Tabie 1. This relief has been grcnted provided -
reference volves of stroke time are established when the volves are known to be in good operating conditlon. See NRC SER, T 4.1.3.1. , A l t f LO u l ATTACHMENT 7 PAGE 44 0F 48 k b .-- + w ww , o ,..r... M,,.. ,,;,,,_ 'y
1
, : NUCLEAR ORGAW1ZATION ENGINEERING PROCEDURE .5023 V 3.5 m UN!15 2 AND 3 - REVl$1CN 7 PAGE 201 0F 200 ATTACHMENT'7 TCN 7-1g VALVE RELIEF REQUEST NO. 24 {
~
-$ystem: All Systems l Components: All Valves Tested at Cold Shutdown Intervals .
Category: All ! Class: 1, 2 and 3 l Function: N. A. Tt Pequirement ! l Code section IW 3412(a) requires that valves that cannot be exercised-during plant operation shall be specifically identified t by-the Owner and shall be full stroke exercised during cold q shutdowns. Full stroke exercising during cold shutdowns for all i : valves not full-stroke exercised during plant operations sSall be i onafrequencydeterminedbytheintervalsbetmeenshutdownsas- , follows: for intervals of a uohths or longer, exercise during i each shutdown for intervals of less than 3 months, full stroke *
. exercise is not required unless 3 months have passed sincelast !
O shutdown exercise. Basis for Relief: ! If a plant cold shutdown is 'of such short curation that all of the cold shutdown testing cannot be completed as: required, then the ! plant startup can be delayed for this testing. This has not-been 3 required of other plants with approved Inservice Testing Programs. Requiring completion of all required valve testing prior to plant
- restart would be a hardship because it coul_d result in costly extensions of cold. shutdowns.
Alternate Testing: Valve testing at cold' shutdown shall comence not later than 48 1
-hours'after cold shutdown and continue until required testing is completed or plant is ready to return to service. Completion of all required valve testing is not a requisite to plant startup.
j Valve: testing which is not completed during a cold shutdown will be performed during subsequent cold-shutdowns starting from the last test performed at the previous cold shutdown, to meet the-Code specified testing requirements. No valve need be tested more often that once every 92 days. For planned cold shutdowns where ample time is available exception to the 48 hours may be taken. if- ' testing of all the " Cold Shutdown" valves identified in the 151 Program will se completed before return to power operation. 1 E ATTACHMENT 7 PAGE 45 0F 48 _._ m_,. .m_._-._ - . _ _ . _ _ ~ . . . _ _ . _._.._.____._.a.-.._ _ _ _ _ _
NUCLEAR ORGAN!ZATION ENGINEERING PROCEDURE 5023 V-3.5 UNITS 2 AND 3 REVISION 7 PAGE 202 Of 208 ATTACHMEN1 7
'q TCH i36 q)
VALVE RELIEF REQUEST NO. 24 (Continued) Notes: (1) The current version was submitted by letter, R. H. Rosenblum to NRC. Inservice Testing Program for Pumps and Valves TAC Nos. 55120/1, July 31, 1991. (2) This Relief Reauest has been approved. See NRC Safety Evaluation Report transmitted by letter, L. E. Kokajko (NRC) to H. B. Ray (SCE) and G. D. Cotton (5DG&E), Safety Evaluation Report of the Inservice Testing (IST) Program for Pumps and Valves, Septem+ ber 24,1990, Table 1 and see SER,14.1.1.1 m (0 f~' i C) ATIACHMENT 7 PAGE 46 Of 48
NUCLEAR ORGAN!ZAT!ON ENGINEERING PROCEDURE 5023 V 3.5 UNiiS 2 AND 3 REVIS10N 7 PAGE 203 Of 208 ATTACHMENT / (3, TCN _7 ".16 V VALVE REllEF REQUEST fl0. 25 System: Main St u m Components: Atmospheric Dump Valves (ADV's) 2(3 HV8419 2(3 HV8421 Category: B Class: 2 Function:
- r. lose en Main Steam isolation $tgna) (MSIS). Time to close is 3.6 sec. Open remotely and manually. There is no response time associdtea with opening the ADV in any accident analysis (except for 20 min, nperator response timo).
Test Requirennt: Full troke exercise cuarterly in accordan:o with the ASME Code. Section XI, lWV 341). ' s ? Basis fer Relief: P MEMLLY1TJH L1HEUR The ADV's are rarely opened during power operat 1n and are only used during plant heat up and cool downs when tile condenser is not available. Therefora, the valves are normally in their MSIS actuated position, and there is generally no ne8td to perform a full closed stroke test of the ADV's. WARIIBLI.Il1Lji1RQf4 Fully opening an ADV without isolation of the steam flow path at power risks plant upset and trip as this allows a large steam release, approximately 5 % of 3410 MW thermal, and a resultant pressure transient when the ADV is tripped closed. The pressure transient could result in RCS temperature excursions that could cause an Engineered Safety Feature (ESF) initiation with the associated reactor trip. There is a maintenance block valve upstream of the ADV. This valve could be closed to block steam flow to allow the ADV to be fully opened for test without releasing s;eam. However, an isolated ADY is unavailable to perform its function with the block valve closed necessitatirig entry into the action requirements of ( ,) Technical Specification 3.7.1.6 and aggravating the unavailability V of the ADV's from a plant reliability point of view. ATTACHMENT 7 PAGE 47 Of 40 l
i NVtLIAR ORGANIZA110N ENGINEERING PROCEDURI SD23 V 3.5
.UNilS 2 AND 3 REVISION 7 PAGE 204 Of 208 ATTACHMENT 7
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TCN 1 ~ LQ (G VALVE RELIEF REQUEST ND. 25 (Continued) Basis for Relief: (Continued) pgtJgyggg,JIjillHG W1TRlRES$1E APPL 1ED A partial stroke of the ADV can be performed, while the ADV is experiencing full system pressure, by opening the valve to approx-imately 25 %. The ADV's are designed with integral pilot valves that assist in opening the ADV when it is under pressure. The pilot valve equalizes pressure across the ADV (partially) during the open stroke. Partial stroke exercising with main steam pressure applied fol. lowed by closing the ADV in a similar manner as would a MSIS actuation, demonstrates the ADV and its pilot valve's ability to open And close under actual operating conditions. Q,0NCLUS10N 16:1s proposed alternative testing method would be analogous to actual dest h conditions for ADV operation and can be performed {q e j with minitrt impact to plant operations. The pilot valve stroke length is the first 5 % of the stem travel. This fully exercises the pilot valve and piston ring, and partially exercises tt< main plug. The pilot valve serves no function when the ADV is not under system pressure. The depressurized stroke test is an artificiali-ty that does not demonstrate the ability of the ADV to function under design cor.ditions. Alternate Testing: Perform a partial stroke test of the ADV under actual operating conditions (without isolation of the main steam pressure) on a quarterly basis, full stroke the valve on a cold shutdown basis. Notes: (1) The current version was submitted as a new VRR by letter, R. M. Rosenblum to NRC. Inservice Testing Program for Pumps and Valves TAC Nos. 55120/1, July 31,1991 (3) NRC approval of the current version, above, was documented in letter, James E. Dyer to H. D. Ray and G. D. Cotton, Safety Evaluation of Licensee Responses to Staff's Technical Evaluation Report items and Revised Relief Requests to the 151 Program for (- Pumps and Valves, October 2, 1991, ATTACHMENT 7 PAGE 48 0F 48 L__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
1 NUCLEAR ORGANIZATION INGlHEERIHG PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 205 0F 20B _ AliACHMENT B f} TCN 7*10 m-STROKE TitiLEC.EE1 BILE CRITERIA FOR VALVES REQVJRED TO STROC-Al OTHER THAN THElR_ SAFE 1Y ANALYSIS LIMITS See Note 3 in Attachment 1 to this procedure. For valves referencing note 3 in Attachments 2 and 4, the maximum stroke times are protected values. These upper I mits may not be increased without a revision to the Final Safety Analysis and/or the Technical Specifications. This is discussed in Rtference 2.3.4. Stroke tinies in Attachments 2 and 4 without note 3 are not 1rotected and may be changed with the approval of the Cognizant Supervisor (tiese maximum stroke times are assigned pursuant to Reference 2.4.2, and Reference 2.4.5, Paragraph IWV 3413). To comply with Reference 2.4.2, many valves have IST Program stroke time limits shorter than the required times of the accident snalysis. They are as follows: Safety Analysis IST yJ1yr Stroke limit Stroke limit 2(3)HV4712 BTC 40 36 BTO 41.5 36 ( k>
') 2(3)HV4713 BTC 40 36 B10 41.5 36 2(3)HV4714 BTC 40 10 BTO 41.5 10 2(3)HV4715 BTC 33.5 10 BTO 35 10 2(3)HV4730 BTC 33.5 10 BTO 35 10 2(3)HV4731 BTC 40 10 BTO 41.5 10 2(3)HV9205 40 4 7(3)TV9267 40 13 2(3)HV9900 40 14 2(3)HV9920 40 12 2(3)HV9921 40 26
,, 2(3)HV9971 40 13 (v j)
ATTACHMENT 8 PAGE 1 0F 4
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 206 0F 208 m ATTACHMENT 8 t v
) TCN 7-16 STROKE TIME ACCEPTANCE CRITERIA FOR VALVES REQUIRED T0_11EQKE A1 OTHER THAN THEIR SAFETY xNALYSILLIMITS (Continued)
Safety Analysis IST hlyg Stroke Liml1 Stroke limit 40 15 2(3)HV6211 40 15 2(3)HV6216 40 15 2(3)HV6223 40 15 2(3)HV6236 12 8 2(3)HV6500 12 8 2(3)HV6501 2(3)HV5686 40 33 7, 40 31 !] 2(3)HV7258 2(3)HV7259 40 5 2(3)HV7512 40 17 2(3)HV7513 40 7 2(3)HV5434 40 4 gi 2(3)HV5437 40 2 2(3)HV0508 40 33 2(3)HV0509 40 4 2(3)HV0510 40 24 2(3)HV0511 40 5 2(3)HV0512 40 31 2(3)HV0513 40 5 2(3)HV0514 40 31 l
) 2(3)HV0515 40 2
( i ATTACHMENT 8 PAGE 2 0F 4 I
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 207 0F 208 ATTACHMEN1 8 (N
-() TCN _7
- i G STROKE TIME ACCEPTANCE (31TERIA FOR VALVES RLOVlRED TO STROKE AT OTHER THAy THEIR SAFETY ANALYSIS LIMlli (Continued)
Safety Analysis IST YAlya Stroke Limit Ettoke limit 40 #5 2(3)HV0516 40 29 2(3)HV0517 40 7 2(3)HV7911 40 15 2(3)HV9217 40 5 2(3)HV9218 2(3)HV5388 40 2 2(3)HV9306 40 30 2(3)HV9307 40 30 2(3)HV9322 30 16 2(3)HV9325 30 16 2(3)HV9328 30 16 2(3)HV9331 30 16 2(3)HV9334 40 13 2(3)HV9347 40 32 2(3)HV9348 40 32 2(3)HV4053 20 9 2(3)HV4054 20 9 2(3)HV4057 20 5 2(3)HV4058 20 5 2(3)HV8419 BTC 20 15 ATTACHMENT 8 PAGE 3 0F 4 (]) 1
- _ _ _ _ _ _ .____.._.._____o
NUCLEAR ORGANIZATION ENGINEERING PROCEDURE S023 V 3.5 UNITS 2 AND 3 REVISION 7 PAGE 208 0F 208 _'T ATTACHMENT 8 (V TCN _ h y g STROKE TIME ACCEPTANCE CRITERIA FOR VALVES REQUIRED TO STROKE AT OTHER THAN THEIR SAFETY ANALYSIS LIMITS (Continued) Safety Analysis IST Yglyg Stroke Limit Stroke Limit 2(3)HV8421 BTC 20 15 2(3)HV5803 40 18 2(3)HV5804 40 5 These differing stroke times reflect the methodology used to establish strole times for the power operated valves in Units 2 and 3. It also reflects the absolute limits on stroke times versus the IST Program limits developed in 6ccordance with NRC Generic Letter 89 04. ,
,m
([ ~ T V 0155d-7T.wS1 AITACWiENT 8 PAGE 4 0F 4 i _ - - - _ _ _ _ _ _ - - _ - _ - _ _ - - - _ _ _ _ _ _ _ _ _ _ - _ _ _ - - _ _ _ _ - - _ _ - _ _ _ _ _ _ _ _ - - _ _ - _ -___ ___ _ _ ._}}