ML18348A895
| ML18348A895 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 06/13/1978 |
| From: | Hoffman D Consumers Power Co |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18348A895 (108) | |
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General Offices: 212 West Michigan Avenue, Jackson, Michigan 49:201
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Director, Nuclear Reactor Regulation Att: Mr Dennis L Zieman.,.~, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-255 - LICENSE DPR PALISADES PLANT - UPDATE OF INSERVICE INSPECTIOW (ISI) PROGRAM SUBMITTALS Attachments to this letter supercede previous submittals dated March 1, 1977, May 3~ 1977, October 3, 1977 and January 13, 1978 related to the Palisades Plant proposed Technical Specifications and Inservice Inspection Program revised to meet the requirements of 10 CFR Part 50, Section 50.55a. The attachments are as follows: I. Proposed Technical Specifications changes. (Included for completeness,
~a:ngetrf:runrpre-v"4.Gus-..submittals except for editorial correc-
~.
vl.OnS. ) II. P~~4...~Be.q,ues.:t __for Relief From Provisions of 1974 ASME B&PV Code Section XI With Addenda Through Summer 1975. III. ~ Re'.1;:-~st_ _:for Exemptions of Inservice Testing of Pufilps and Valves. --~ IV. Supplemental Information on Code Update and Code Implementation.
~
V. Comparison of IWB-2600 and IS-261. VI. Inservice Inspection 40-Year Plan and Pump and Valve Program. (This attachment also includes the Pump and Valve 20-Month Update with appro-priate relief requests as required by 10 CFR 50.55a(g). The following additional information was requested during telephone conversations with Messers R Silver and G Walton of the NRC staff. 7*-*1 -------------\
*=- 660()!"';p
- 1.
Reference:
Letter to Albert Schwencer from DP Hoffman dated March 1, 1977*
Subject:
Palisades Plant - Technical Specifications Changes - Inservice Inspection and Testing Requirements, Page II-8, Item 10. The staff requested information as to the number of dissimilar metal nozzle-to-safe end welds on the pressurizer which have been examined previously, and how many will be examined in this 10-year interval. Table 1 delineates this information concerning the 14 nozzle-to-safe end welds. TABLE 1 Pressurizer Dissimilar Metal Welds Nozzle-to-Safe Ends
- Weld Identification Completed This Interval Scheduled This Interval
~CS-12-PSL-lHl-l x PCS-6-PRS-l.Al-l x PCS-6-PRS-lBl-l PCS-6-PRS-lCl-l x PCS-4-PRS-lPl-l x PCS-4-PSS-lPl-21 x
- 8 Level Indicators Note 1: There are 4 level nozzles in the upper head and 4 level nozzles in the lower head. Each level nozzle is a l" nozzle fabricated from ASTM-A-508-64 Cl 2 alloy forging and fitted with an SA-182, Type F-316 alloy end. These 1 11 nozzles are exempt from volumetric examination by Section XI ASME B&PV Code. These nozzles shall be examined in accordance with IWA-5000 and IWB-5000 (hydros and leak tests).
Note 2: PCS-6-PRS-lBl-l was not scheduled to be examined this interval due to a typographical error in the tables of the 40-year master plan. This error will be corrected and this weld will be examined this interval. Note 3: All of the 6 enumerated welds above are also scheduled for volumetric examination during each of the 3 remaining intervals.
- 2.
Reference:
March 1, 1977 letter as above, Page II-9, Item 13. The staff requested information as to whether we had baseline data on B3.l steam generator welds. The following summarizes this information:
- a. There are 17 B3.l welds on each steam generator .
. b. All 34 B3.l welds are scheduled to be examined once each interval .
- c.
d. 9 of the 34 welds were examined during the first third of the present 10-year interval. 10 welds were examined during preservice inspection.
- 3.
Reference:
March 1, 1977 letter as above, Page II-4. The staff requested further information explaining why the listed welds were inaccessible for UT. The NRC further requested a determination as to what method of testing would be substituted for the UT. Table 2 clarifies the previously submitted information. The proposed substitute examinations have not changed. TABLE 2 Inaccessible Welds Weld Identification Basis for Relief Request ESS-24-SIS-SHl-201, 202, 203, 204 Encased in steel plate missile shield. ESS-24-SIS-SH2-201, 202, 203, 204 Encased in steel plate missile shield. ESS-14-CSS-lPB-210, 211 Welds covered by pipe hanger strapping. ESS-lO-CSS-lPB-224, 225 Welds covered by pipe hanger strapping . ESS-14-CSS-lPC-213 Weld covered by pipe hanger strapping. ESS-14-SDC-LPD-213 Weld covered by pipe hanger strapping.
*ESS-14-SCS-2Hl-209 Weld encased in containment penetration structure. **ESS-8-CSS-SLA-224 Weld encased in containment penetration structure. ***ESS-8-CSS-SLB-224 Weld encased in containment penetration structure.
ESS-6-SIS-lHP-211 Weld encased in containment penetration structure. ESS-6-SIS-2HP-219 Weld encased in containment penetration structure. RWS-6-CWR-SL4-201 Weld encased in containment penetration structure.
*Typographical error previously listed this weld as: ESS-14-SCS-2Hl-204. **Typographical error previously listed this weld as: ESS-6-CSS-SLA-224. ***Typographical error previously listed this weld as: ESS~6-CSS-SLB-224.
NOTE: All of the above welds are inaccessible for NDT examination. These welds will be hydro/leak test examined in accordance with IWC-5000, Section XI.
- 4.
Reference:
January 13, 1978 letter with subject and addressee the same as your March 1, 1977 letter .
- The staff requested clarification of our code usage for ISI as stated in Paragraph I of the CP Co Code Applicability Statement No 1, specifically addressing vessels. The following should clarify the code usage:
.e
- a. Vessels will be examined in accordance with Section V and Section XI, ASME B&PV Code 1974 Edition With Addenda Through Summer 1975 (74s75).
All vessel UT exams will be conducted in accordance with Appendix I, Section XI, 74S75 Edition.
- b. Piping will be examined in accordance with Section XI and Section V, ASME B&PV Code, 74S75 Edition.
- c. CP Co Code Applicability Statement No 1, Paragraphs II and- III supple-ment Section V and Section XI with respect to both piping and vessels.
Guidance was taken from Appendix III, Section XI, ASME B&PV Code, 74W75 Edition when Paragraph IV (CP Co Code Applicability Statement No
- 1) was written to supplement Section V, ASME B&PV Code for piping ex-aminations. The CP Co Code Applicability Statement No 1 was revised and is included as part of Attachment II.
- 5.
Reference:
January 13, 1978 letter as above. The staff requested clarification of the code case cited in the CP Co Code Applicability Statement No 1 concerning the waiver of Ultrasonic Transfer Method. The following clarifies this issue:
- a.
b. A typographical error listed the code case as 1968. 1698. This should read CP Co Code Applicability Statement No 2, subject: UT Calibration Standards, addresses the acoustic similarity limitations imposed by the NRC. The NRC questions concerning acoustic similarly generated a review of the references statement which revealed an administrative error. This error has been corrected and a revised copy of Statement No 2 is included as part of Attachment II.
- 6.
Reference:
Letter to Albert Schwencer from DP Hoffman dated May 3, 1977.
Subject:
Palisades Plant, Inservice Inspection Program, Attachment 1, Page 1. The staff noted that the pressurizer was not included in the scope of the 40-year plan for Class 1 system. The omission of the pressurizer as a Class 1 vessel in the referenced letter was an oversight. The pressurizer is an integral part of the Class 1 system and has always been in the 40-year plan. The pressurizer will be examined in accordance with Section XI, ASME B&PV, 74S75 Edition, Table IWB-2600, Items B2.l to B2.ll except where relief is granted.
- 7.
Reference:
May 3, 1977 letter as above. The staff requested clarification of the May 3, 1977 submittal wherein Consumers Power Company referenced utilization of Appendix III, 74W75 Code. The following response was provided.
\.
Originally, Consumers Power Company had intended to fully utilize Appendix III as this portion of the code explicitly deals with UT examinations of piping. Appendix III procedural controls greatly increased the technical adequacy of the examination as compared to examinations conducted to Section V of the code. However, Southwest Research Institute took exception to Appendix III. As a result, a compromise was achieved with SWRI, the results of which are the Consumers Power Code Applicability Statements No 1 and No 2. The staff felt that since Consumers Power had submitted the above-mentioned statements, specific reference to Appendix III was no longer required provided that relief was requested allowing the use of the 100% DAC Reporting/Evaluating level. The attachments provide the necessar_y updates. This submittal is intended to address any outstanding NRC staff concerns related to the Palisades Plant proposed Technical Specifications changes and Inservice Inspection Program to meet requirements of 10 CFR 50.55a. Assistant Nuclear Licensing Administrator CC: JGKeppler, USNRC
1., ATTACHMENT I Proposed Technical Specifications Change Sections 4.3, 4.8 and 4.9 Tables 4.2.2 and. 4.3.1
- Palisades Technical Specifications Docket 50-255 License DPR-20
lq
- TABLE 4.2.2 MINI.MUM FREQUENCIES FOR EQUIPMENT TESTS FSAR Section Test Freauency Reference
- 1. Control Rods Drop Times of All Full- Each Refuel- 7.4.1.3 Length Rods ing Shutdown
- 2. Control Rods Partial Movement of All Every Two 7.4.1.3 Rods (Minimum of 6 In) Weeks
- 3. Pressurizer Safety Valves Set Point As Required 7.3.7 by Spec 4.3c
- 4. Main Steam Safety Valves Set Point As Required 4.3.4 by Spec 4.3c
- 5. Refueling System Functioning Prior to 9.11. 3 Interlocks Refueling Operations
- 6. Service Water System Functioning As Required 9.1.2 Valve Actuation (SIS-CHP) by Spec 4.3c
- 7. Fire Protection Pumps and Functioning Monthly 9.6.2 Power Supply
- 8. Primary System Leakage Evaluate Daily 4 Amend 15, Ques 4.3.7
- 9. Diesel Fuel Supply Fuel Inventory Daily 8.4.1
- 10. Critical Headers Service 150 Psig Hydrostatic Every Five 9.1.2 Water System Test Years
- 11. Charcoal and Hi Effi- Charcoal Filters Each Refuel- Amend 14, ciency Filters for Con- Checked ~ 99% Effi- ing Shutdown Ques 14.19-1, trol Room, Fuel Storage ciency per Freon 112 and at Any 6.5.1, 9.8.3 Building and Containment test (ORNL) - HEPA Time Work on Purge System (Containment Filters checked ~ 99% Filters Post-Accident Filter) Efficiency per ANSI Could Alter NlOL 1-1972 Their Integrity
- 4-15
4.3 SYSTEMS SURVEILLANCE APPLICABILITY Applies to preoperational and inservice structural surveillance of the reactor vessel and other Class 1, Class 2 and Class 3 system components. OBJECTIVE
*To insure the integrity o.f the Class 1, Class 2 and Class 3 piping systems and components. *SPECIFICATIONS
- a. Prior to initial plant operation, an ultrasonic survey shall be made of reactor vessel shell welds, vessel nozzles, vessel flange welds, piping system butt welds and major welds on the pressurizer and steam generators to establish preoperational system integrity and basic conditions for future testing.
- b. The structural integrity of ASME Class 1, 2 and 3 components, as determined by 10 CFR 50, Section 50.55a and Reg Guide 1.26, shall be verified and maintained at an acceptable level in accordance with Section XI of the ASME B&PV Code with applicable addenda as required by 10 CFR 50, Section 50.55a(g), except where specific relief has been granted by the NRC, and where provisions of Section 4.12 take precedence.
- c. Inservice testing of ASME Class l, 2 and 3 pumps and valves, as determined by 10 CFR 50, Section 50.55a and Reg Guide 1.26 shall be performed in accordance with Section XI of the ASME B&PV Code with applicable addenda as required by 10 CFR 50, Section 50.55a(g),
except where specific relief has been granted by the NRC.
- d. Sufficient records of each inspection shall be kept to allow compari-son and evaluation of future tests.
- e. The Inservice Inspection program shall be reevaluated as required by 10 CFR 50, Section 50.55a(g)(5) to consider incorporation of new 4-16
.. T
- inspection techniques that have been proven practical, and the conclu-sions of the evaluation shall be used as appropriate to update the inspection program.
- f. Surveillance of the regenerative heat exchanger and primary coolant pump flywheels shall be performed as indicated in Table 4.3.2.
- g. A surveillance program to monitor radiation induced changes in the mechanical and impact properties of the reactor vessel materials shall be maintained as described in Section 4.5.3 of the FSAR. The specimen removal schedule shall be as indicated in Table 4.3.3.
BASIS The inspection program specified places major emphasis on the areas of highest stress concentration as determined by general design evaluation and experience with similar systems. (l) In addition, that portion of the reactor vessel shell welds which will be subjected to a fast neutron dose sufficient to change ductility properties will be inspected. The inspec-tions will rely primarily on ultrasonic methods utilizing up-to-date ana-lyzing equipment and trained personnel. Preoperational inspections will establish base conditions by determining indications that might occur from geometrical or metallurgical sources and from discontinuities in weldments or plates which might cause undue concern on a postservice inspection. To the extent applicable, based upon the existing design and construction of the plant, the requirements of Section XI of the Code shall be complied with. Significant exceptions are detailed in the requests for relief which have received NRC approval and are contained in the Class 1, Class 2 and Class 3 Long-Term Inspection Plans. REACTOR VESSEL SURVEILLANCE SPECIMENS Table 4.3.3 is consistent with the surveillance program as presented in 2 the FSAR. ( ) However, the withdrawal schedule has been modified to re-flect the slightly different wall fluence values resulting from removal of the thermal shield. REFERENCES (l) FSAR, Section 4.5.6. (2) FSAR, Section 4.5.3 .
- 4-17
- J TABLE 4.3.1 (Delete) 4-18
l ..
- * . )
(INTENTIONALLY LEFT BLANK) 4-22
- 4.8 MAIN STE.AM ISOLATION VALVES APPLICABILITY Applies to periodic testing of the main steam isolation valves.
OBJECTIVE To verify the ability of the main steam isolation valves to close upon signal. SPECIFICATIONS The operation of the main steam isolation valves shall be tested as required by Specification 4.3c. to demonstrate a closure time of five seconds or less under no-flow conditions. BASIS The main steam isolation valves serve to limit an excessive primary coolant system cooldown rate and resultant reactivity insertion following a main steam break incident. Their ability to close upon signal should be verified on a regular basis. REFERENCES FS.AR, Sections 7.2.3.8 and 14.14 .
- 4-44
I 4.9 AUXILIARY FEED-WATER SYSTEM APPLICABILITY Applies to periodic testing requirements of the turbine-driven and motor-driven auxiliary feed-water pumps. OBJECTIVE To verify the operability of the auxiliary feed-water system and its ability to respond properly when required. SPECIFICATIONS The operability of the motor- and steam-driven auxiliary feed pumps, and discharge valves CV-0736A and CV-0737A, shall be confirmed as required by Specification 4.3c. BASIS The periodic testing of the auxiliary feed-water pumps will verify their operability by recirculating water to the condensate storage tank and simultaneously partially opening, one at a time, the discharge valves (CV-0736A and CV-0737A) to confirm a flow path to the steam genera-tors. Proper functioning of the steam turbine admission valve and the feed-water pumps' start will demonstrate the integrity of the steam-driven pumps. Verification of correct operation will be made both from instru-mentation within the main control room and direct visual observation of the pumps. REFERENCES FSAR, Section 9.7. 4-45
ATTACHMENT II Proposed Request for Relief From Provisions of 1974 ASME ~PV Code Section XI
- With Addenda Through Summer 1975 Pursuant to 10 CFR 50, Section 50,55a(g)(6)(i)
The following table delineates those areas of the 1974 ASME B&PV Code Section XI with Addenda through Summer 1975 which cannot be implemented at the Pali-sades Nuclear Plant. Inasmuch as the revised plant Technical Specifications will i: 1 ~orporate by reference the 1974 ASME Code with Addenda through Summer 1975, this submittal represents those areas for which it is requested that the NRC grant relief from the provisions of the 1974 ASME B&PV Code Section XI with Addenda through Summer 1975. The areas requiring relief are identified by the item numbers listed in Table IWB-2600 of the Summer '75 Addenda. The notes following the table provide information concerning the basis for each relief request and concerning the implementation of the reference code . II-1
- Area ot:
Relief: Sect XI Category: Comuonent Function Safety REQUESTS CLEAR PLANT Relief Reauested
~Of3
~8 ,
~ Testing Substituted Imule."llentation
- Bl.2 Vessel Closure Head Primary Pressure *1 Meridional & Circum. a. Vessel Hydros Boundary a.&b. Tech Specs Seam Welds Generally b. Vessel Coupons c. 40-Year Plan Inaccessible for c. Bl.l, Bl.2 Volumetrtc Exam Bl.3 Testing Bl.2 B-B Vessel Bottom Head Primary Pressure l *Meridional & Circum. a. Vessel Hydros Boundary a.&b. Tech Specs Seam Welds Generally b. Vessel Coupons c. 40-Year Plan Inaccessible for c. Bl.l, Bl.2, Volumetric Exam B.1.3 Testing B-C Vessel.to Flange Primary Pres sure l Mechanized UT To Be a. Vessel Hydros Boundary a. Tech Specs Performed Once per b. Bl.3 Testing b. 40-Year Plan Interval Coincident to Core Barrel Removal Bl.4 B-D Nozzle to Vessel Primary Pressure L Core.Barrel To Be Re- a. Vessel Hydros Boundary a. Tech Specs moved Once Each 10- b. Bl.4, Bl.15 b. 40-Year Plan Year Interval 'J.'esting
. B.1.4 B-D Nozzle Inside Primary Pressure H 1 Core Barrel To Be Re- a. Vessel Hydros H Radius Boundary a. Tech Specs I moved Once Each 10- b. Bl.4, Bl.15 Test- b. 40-Year Plan
.I\) Year Interval ing B.1.6 B-F Vessel Safe- Primary Pressure 1 Not a Dissimilar Welds Covered as End Welds Boundary
- 40-Year Plan Metal Weld B4.5, B-.1
- Bl.14 B-I-1 Vessel Cladding Primary Pressure l Core Barrel To Be .. a. Vessel Hydros Boundary a. Tech Specs Removed Once Each 10- b. Bl.13, Bl.14, b. 40-Year Plan Year Interval Bl.15 Testing*
B3.3 B-F Steam Generator Primary Pressure l Not a Dissimilar Welds Covered as 40-Year Plan Safe-End Welds Boundary Metal Weld Blf.5, B-J B4.l B-F Safe-End - To Primary Pressure l Record at 50i; Pipe Boundary None 40-Year Plan Evaluate at lOOi DAC Examination Performed as Scheduled B4.5 B-J Circuu, and Long
- Record at 50i; Prirr.ary Pressure 1 Pipe Welds Boundary Evaluate at lOOi DAC None - Examination 40-Year Plan Performed as Scheduled B-J PCS-42-RCL-1Hl-2LD, Primary Pressure l Inaccessible for UT a. Hydros 3ru*, 3, '3LD Boundary a.
- Tech Specs PCS-42-RCL-21Il.-2LD, b. Re."llaining B-J b. 40-Year Plan
, 3LU, 3, 3LD Welds in System B4.6 B-J Branch Connection >>6 11
- Primary Pressure l Record at 50'f,;
Boundary None - Examination 40-Year Plan Evttluate at lOOi DAC . Performed as Scheduled B-J Integrally Welded Primary Pressure l Supports Boundary Record at 50i; None*- Examination 4o-Year Plan Evaluate at lOOi DAC Performed a:> Scheduled
Rev. l 2 Page 2 of 3 5/u/78 Area of Sect XI Safety Relief cateso!1'. Component Function Class Relief Reguested Testi~~ Substituted ~le:nentation c2.1 C-G ESS-24-SIS-SHl-201, Pressure Boundary 2 Inaqie?ssible for UT a. Hydro a.&b. 40-Year 202, 203, 204 b. C2.l Testing on Plan
,Remainder of System c2.1 C-G ESS-24-SIS-SI'.2- Pressure Bou.'l.dary 2 Inaccessible for UT a. H;ydro a.&b. 4o-Yea.r e.
*201, 202. 203, 204 b. C2.l Testing on Plan Remainder of System C2.l C-G ESS-14-CSS-lPB- Pressure Boundary 2 Inaccessible for UT 0.. Hydro A, &'b * ,40-Yefl.r 210. 211 b. C2.l Testing on Plan Remainder of System C2.l. C-G ESS-10-<J SS-l.PB- Pressure Boundary 2 Inac~essible for UT a. Hydro a.&b. 40-Year 224, 225 b. C2.l Testing on Plan Remainder of System H c2.1 C-G ESS-14-CSS-lPC Pressure Boundary 2 Inaccessible f:or UT a. P.ydro a..&b. 4o-Year H
I 213 b. C2.l ~esting on Plan w Remainder of: System C2.l C-F
- ESS-14-SDC-LPD- Pressure Boundary 2 Inaccessible for UT a. Hydro a.&b. 40-Year 213 b. C2.l Testing on Plan Remainder of System C2.l. C-G ESS-14-SCS-2Hl.- Pressure Boundary 2.** Inaccessible for lJT. a. Hydro a.&b. 40-Year 209 b. C2.l Testing on Plan Remainder of:
System C2.l. C-G ESS-8-css-SLA- Pressure Boundary 2 Inaccessible t:or UT* a. Hydro a.&b. 40-Year 224 b. C2.l Testing on Plan Remainder of System c2.1 C-G ESS-8-CSS-SLB- Pressure Boundary 2 Inaccessible f:or )J'IL a. Hydro a.&b. 40-Year 224 b; C2.l Testing on Plan Remainder of
- System C2.l. C-G ESS-6-SIS-lHP- Pressure Boundary 2 Inaccessible f:or UT a. Hydro a.&b. 4o-Year 211 b. C2.l Testing on Plan
*RemaLrlder of System
Area of Sect XI Safety
;.Of3 +
5/11/78
~ Catego!:i! ComEonent Function ~ Relief Re9uested Testing Substituted Imolementation C2.l. 0-G ESS-6-SIS-2HP- Pressure Boundary 2 Inaccessible :for UT a.. Hydro a..&b *. 40-Year 219 b. C2.l Testing on Plan Remainder of System C2.l. c-*a RWS-6-CWR-sr.4- Pressure Boundary *2 Inaccessibl.e for UT a. Hydro a.&b. 40-Year 201 b. C2.l Testing on Plan Remainder of System 02.l. C-F ESS-12-SIS-lLP-232 Pressure Boundary 2 Inaccessible :for, UT a. Hydro a.&b. .4o-Year
- b. C2.l Testing on Plan Remainder of System C2.l. C-F SFP-8-CPL-DLI-207 Pressure Boundary 2 Inaccessible for UT a. Hydro a.&b. 40-Year
- b. C2.l Testing on Plan Remainder o:f H
System H 02.l. C-F SFP-6-CPL-SLI~207 Pressure Boundary .i::- 2 Inaccessible for UT a. Hydro b
- C2.l Testing on a.&b. 40-Year Plan Remainder of f!yst~
Notes on Relief Requests
- 1. Item Bl.2 (Long, Cir, and Meridional welds in Rx Vessel heads)
BASIS STATEMENT The dollar plates weld in the closure head is inaccessible for volumetric examination due to control rod guide tube constraints. Meridional welds in the closure head are partially accessible for volumetric examination. Determination of 10% weld length accessibility will be made during the next refueling outage. An attempt will be ma.de to volumetrically inspect the meridional and circumferential seam welds in the bottom head during the next refueling outage in which mechanized inspection is performed on the Rx vessel. REMARKS See CE Dwg E-232-139-1. IMPLEMENTATION Meridional welds in the closure and bottom heads and circumferential welds in the bottom head may be accessible for volumetric examinations due to new inspection techniques.
- 2. Item Bl. 3 _(Vessel to flange weld)
BASIS STATEMENT. Mechanized UT Examinations to be deferred to end of interval. REMARKS Deferment to the end of 10 year interval will allow all Mechanized UT Examinations to be performed during the same outage when core barrel is removed. Intent of ASME Section XI Code Committee is to require removal of core barrel only once every ten years, as evidenced by the 74w75 Addenda. IMPLEMENTATION Relief requested to defer Item Bl.3 examinations to the end of interval. II-5
3* Item Bl.4 (Nozzle to Vessel Welds) BASIS STATEMENT Complete Mechanized UT Examinations of Rx vessel nozzles can be accomp-lished only when core barrel is removed. REMARKS Core barrel is scheduled to be removed only at end of each interval. All Mechanized UT Examinations to be accomplished when core barrel is removed. Performance of Rx vessel no~zle examinatian,s at th~ ~nd_of the inter.val is consistent with the former 10 yea:r plan and with the_ intent .Of. the_ Section ________ _ XI Code Cammi ttee, as expressed- in Item. Bl. 3 above. - IMPLEMENTATION Relief requested to defer Item Bl.4 examinations to the end of the interval.
- 4. Item Bl.6 (Nozzle-to-safe-end-welds)
BASIS STATEMENT The transition pieces between the carbon steel nozzles and the carbon steel piping are also carbon steel and thus not dissimilar metal safe ends
- The nozzle-to-safe-end-welds are therefore classed as B4.5, B-J welds rather than Bl.6, B-F welds.
Although it is recognized that the nozzle-to-safe-end areas will be sub-jected to the higher stress levels associated with terminal ends and wall thickness transitions, examination other than mechanized UT from the inside of the nozzle is not possible due to accessibility constraints. REMARKS See CE Dwg E-232-119-11. The VT has been dropped from the Code. IMPLEMENTATION Relief requested as before *
- II-6
- 5. Item Bl.14 {Vessel cladding)
BASIS STATEMENT Cladding patch examination can be accomplished only when core barrel is removed. Core barrel is scheduled to be removed only at end of each interval. Remote visual examination to be accompl1shed when core barrel is removed. 0 Supplementary examination during interval to include remote visual examination of Vessel Interior {Item Bl.15), Closure Head Cladding {Item Bl.13), and if possible clad surface of outlet nozzles. IMPLEMENTATION Relief requested to defer Item Bl.14 examinations to end of interval.
- 6. Item B3.3 {Nozzle-to-safe-ends)
BASIS STATEMENT See Bl.6. See Bl.6. IMPLEMENTATION Relief requested as before. II-7 *
- 7. Items B4.l, B4.5, B4.6, B4.9 (Pressure retaining piping)
BASIS STATEMENT Section V, ASME B&PV Code J4S75 Edition requires defect evaluation, (from UT Examinations) at the 20% DAC level. Newer technology has shown that numerous nonrelevant and geometric reflectors are detected at the 20% DAC level. More recent codes (ie. Section XI, ASME B&PV, 74W75 Edition with Appendix III) allows use of notch reflectors and 100% DAC evaluation level. CPCo will record all UT indications at the 50% DAC level and evaluate all UT indications at the 100% DAC level for piping (see CPCo Applicability Statements Nos 1 and 2, which are attached). CPCo further* intends to uti-lize hole type reflectors (where possible) rather. than notch type reflectors thereby. increasing sensitivity by a factor of about two. IMPLEMENTATION Relief requested allowing use of 100% DAC evaluation level in lieu of 20% DAC evaluation level for UT indications. 8* Item B4.5 (Pressure retaining piping) BASIS STATEMENT Welds PCS-42-RCL-1HJ.-2LD, 3LU, 3, 3LD, and PCS-42-RCL-2Hl-2LD, 3LU, 3, 3LD are located inside the cement reactor shield and are inaccessible for UT. REMARKS The area between the last known weld (at the elbow entrance to the steam generator} and the reactor shie:i_d was visually examined; no welds were* ____________ _ apparent in this region. Therefore, it is concluded that the welds are buried inside the reactor shield.
- IMPLEMENTATION Relief requested to allow those welds to be examined solely in accordance with IWA/IWB-5000 *
- II-8
- 9. Item C2.l (Pressure retaining piping)
BASIS STATEMENT Welds encased in steel plate missile shield; welds inaccessible for NDT Examination. REMARKS Ba.sis statement applicable to the following welds: ESS-24-SIS-SHl-201, 202, 203, 204; ESS-24-SIS-SH2-201, 202, 203, 204. IMPLEMENTATION Relief requested to examine above welds in a Hydro/Leak Test.
- 10. Item C2.l (Pressure retaining piping)
BASIS STATEMENT Welds covered by p,ipe hanger strapping; welds inaccessible for NDr Examination. REMARKS Ba.sis statement applicable to the following: ESS-14-CSS-lPB-210, 211 ESS-10-CSS-lPB-224, 225 ESS-14-CSS-lPC-213 ESS-14-SIX::-LPD-213
--IMPLEMENTATION Relief requested to examine the above welds via Hydro/Leak Test.
II-9
- 11. Item C2 .1 (Pres sure retaining piping)
BASIS STATEMENT Welds encased in containment penetration structure. Welds are inaccess-ible for NDl' Examination. REMARKS Basis Statement a:pplicable to the following welds: ESS-14~SCS-2Hl-209 ESS-12-SIS-lLP-232 ESS-8-CSS-SLA-224 SFP-3-CPL-DLI-207 ESS-8-CSS-SLB-224 SFP-6-CPL-SLI-207 ESS-6-SIS-lHP-211 ESS-6-SIS-2HP-219 RWS-6-CWR-SL4-201 IMPLEMENTATION As above *
- II-10
Addenda To ATTACHMENT II Concerning CP Co Code Applicability Statements II-11 *
- 4/13/78 Rev 1
- PALISADES CODE USE FOR INTERVAL THIRD 10/31/76 TO 2/28/80 CONSUMERS POWER COMPANY CODE APPLICABILITY STATEMENT NO 1
SUBJECT:
PIPING AND VESSEL EXAMINATIONS I. The basic requirements for piping and vessel examinations shall be in accordance with Section V, 1974 Edition of the ASME Boiler and Pressure Vessel Code with addenda through Summer 1975 as referenced in Section XI, 1974 Edition of the ASME Code with addenda through Summer 1975. Guidance was taken from Section XI, Appendix III, 1974 Edition of the ASME Code with addenda through Winter 1975 for piping examinations. II. The Section V requirements should be modified by the application of: A. Code Case 1698 - Waiver of Ultrasonic Transfer Method B. Code Case 1705 - Ultrasonic Examination - Calibration Block Tolerance. III. The requirements of Paragraph T-511 of Article 5 of Section V will be modified as follows: A. A pulse-echo type ultrasonic flaw indication instrument shall be used. B. The instrument shall be equipped with a gain control calibrated in units of 2 dB or less. IV. The ultrasonic examinations of piping componen~s shall have the additional requirements as follows: A. Ultrasonic examinations shall be performed in accordance with a written procedure which shall include the following information:
- 1. Weld type and configuration including thickness dimensions, mat~rial, and product form (casting, forging, etc).
- 2. Surface or s"urfaces from which the examinations shall be the performed.
- 3. Surface condition.
- 4. The couplant used in the examination shall be the same as used in the calibration.
- 5. The examination technique (straight beam, angle, beam, contact, and/or immersion) shall be specified .
II-12
- 6. The angles and mode or modes of wave propagation in the material shall be specified.
- 7. The type, frequency, and transducer sizes shall be speci-fied.
- 8. Special search units, wedges, shoes, or saddles if used shall be specified.
- 9. The type and length of search unit cables shall be specified.
- 10. The ultrasonic instrument type shall be specified.
- 11. A description of the method of calibration shall be speci-fied.
- 12. The direction and extent of the scanning shall be specified.
- 13. Data to be recorded and the method of recording in either automatic or manual mode shall be specified.
- 14. The use of the automatic alarm and recording equipment, or both, if used shall be specified.
- 15. Any rotating, revolving, or scanning me~hanisms if used shall be specified.
- 16. Personnel qualification requirements shall be specified.
- 17. The procedure shall be approved as required by Paragraph IWA-2120 of Section XI.
B. Instrument screen height linearity and amplitude control linearity shall be in accordance with established procedures and quality assurance requirements. C. Pipe marking identification shall be in accordance with CP Co's Master Plan. D. Calibration shall be checked by verifying the instrument sen-sitivity and sweep range calibration at the start and finish of each examination, with any change in examination personnel, and at least every 4 hours during the examination. E. Calibration data shall include the following information:
- 1. Calibration sheet identification and date
- 2. Examination personnel II-13
- 3.
4. Examination procedure number and revision. Basic calibration block identity.
- 5. Ultrasonic instrument identity and serial number.
- 6. Beam angle, couplant used, mode of wave propagation, and material examined.
- 7. Orientation of search unit with respect to the pipe longi-1 tudinal or circumferential direction.
- 8. Search unit identity, frequency, size, and manufacturer's serial number.
- 9. Special search units, wedges, wedge type, and saddle identity if used.
lO. Search unit cable type and length. ll. Clock time of the initial calibration and all subsequent calibration checks.
- F.
- 12. Amplitude and sweep readings obtained from calibration reflectors.
Examination data sheets shall include at least the following information:
- 1. Data sheet identity number and date.
- 2. Examination personnel.
- 3. Examination procedure and revision.
- 4. Applicable calibration sheet identity number.
- 5. Identification and location of the weld or volume scanned.
- 6. Surface or position from which the examination is conducted.
- 7. Record of indications or statement that no recordable indi-cations were observed.
G. All ultrasonic reflectors producing a response 50% or greater of the reference level shall be recorded on the appropriate Examination Record. All ultrasonic reflectors 100% or greater of the reference level in piping, shall be investigated to determine the shape, size, identity, and location of the reflector and reported to Consumers Power .
- II-14
All ultrasonic reflectors 50% or greater of the reference level in vessels shall be investigated to determine the shape, size, identity, and location of the .reflector and reported to Consumers Power. II-15 __J
PALISADES CODE USE FOR INTERVAL
- 4/13/78 Rev 1
SUBJECT:
I. THIRD 10/31/76 TO 2/28/80 CONSUMERS POWER COMPANY CODE APPLICABILITY STATEMENT NO 2 UT CALIBRATION STANDARDS All UT Standards will be fabricated from material in accordance with Section XI, Appendix I, Paragraph I-3120, 1974 Edition of the ASME Boiler and Pressure Vessel Code with addenda through Summer 1975. II. All UT Standards will be fabricated to conform in radius of curvature, thickness, and dimensional tolerance as specified on AE drawings sup-plied by Consumers Power Company. Standards will be designed for nominal piping, vessel head, or vessel shell, as appropriate. III. Deviations from these requirements may be made in accordance with guidance existing in Paragraphs I-3130 and I-3140 of the above-referenced code. Deviatio~ from Material Specifications will be allowed provided the sub-stitution is Code Acceptable under the applicable Code Section. Each deviation in material, curvature or *thickness ~ill be addressed on a case-by-case basis. Sufficient justification and approvals are required for each deviation. IV. Basic reflector locations for Piping and Vessel Standards shall conform to Paragraph I-3200 of the above-referenced code or equivalent. It is noted that the curved basic calibration block listed as Figure I-3240 in the 1974 Edition of Section XI, ASME code was deleted from the Summer 1975 addendum and re-issued in the Winter 1975 addendum. Curved basic calibration blocks to be utilized by Consumers Power Company will be in accordance with Figure I-3240, 1974 Edition Section XI, ASME Code. V. Basis This policy is intended to provide guidance for the procurement and utili-zation of UT Standards throughout the entire 40-Year Planned ISI Program. This policy conforms to existing codes and is expected to conform to the future trend of the code. This policy is also based on a reasonable and economic approach to UT Standards. VI. Allowances Although this policy commits CF Co's ISI program to a higher level of calibration block quality than required by the existing code, this policy does not require modification of vendor ISI procedures provided that these procedures are within the limits specified in Section V and Section XI, ASME Code. It is felt that the increased cost incurred as well as the burden on a vendor (who may utilize these same procedures at numerous other facilities) resulting from this policy would not be in the best interest of both parties. Therefore, vendor procedures are deemed accept-able if they are code acceptable. Likewise, the vendor will use solely those standards deemed acceptable by CF Co. VII. Implementation This policy will be implemented during the remainder of the present 3 1/3 year interval. II-16
ATrACHMENT III Proposed Request for Exemptions of Inservice Testing of Pumps and Valves Pursuant to 10 CFR 50, Section 50.55a (g)(6)(i) Period of Applicability 11/1/76 - 6/30/78
- INSERVICE TESTING OF PUMPS AND VALVFB REQUEST FOR EXEMPTIONS Inservice testing of ASME Code Class 1, Class 2 and Class 3 pumps and valves shall be performed in accordance with the 1974 ASME B&PV Code Section XI with Addenda through Summer 1975 and including Appendix III from Winter 1975 with the following exceptions:
INSERVICE PUMP TESTING L. Plant system designs do not include provisions for measuring the suction pressures of any pumps included under this program. Suction pressures will be calculated as applicable by taking the differences between each pump section and its associated expansion tank level plus expansion tank pressure. To measure pump suction pressure would require extensive m9dification (elec-trical/mechanical). The method currently used will give adequately accurate results.
- 2. The design of the service water pumps does not permit measurement of bearing temperatures or monitoring of pump lubrication since the pump is submerged in water *
- 4.
The design of the charging pumps does not permit measurement of bearing temperature since the bearings are inaccessible unless the pumps are disassembled, and crankcase oil temperature is not representative of bearing temperatures because of the installed oil coolers. The design of the concentrated boric acid pumps does not permit direct measurement of bearing temperatures. A representative temperature will be obtained by measuring the surface contact temperatures of the bearing housing. Since there are not installed oil coolers, these temperatures are responsive to oil temper~tures which are, in turn, responsive to bearing temperatures. INSERVICE VALVE TESTING
- 1. With respect to those Category A valves for w):l.ich seat leakage is important from a containment isolation standpoint but not from a system f'unctional standpoint, the leakage rates will be determined at the test pressure speci-fied in Technical Specification Section 4.5.2, Local Leak Detection Tests (between 70 psia and 80 psia). Since these pressures are representative of system pressure at the valve during containment isolation, no exemption is requested.
NOTE: Application of IWV 3420(c)(5) is not required in the testing of these valves.
- 2. Category C relief valve tests may be distributed over each refueling cycle such that the required number of relief valves will have been tested by the end of each cycle.
III-1
.e
- 3. Normally open valves for which it is impractical to partially stroke during operations are identified and full stroke tested during each required cold shutdown.
- 4. It is unreasonable to follow the timing acceptance requirements of IWV-3410 (c)(3) for valves with stroke times under 10 seconds (ie, Palisades has had experience where a valve operates in 1 second one month and 2 seconds the next; therefore, test frequency is required to be increased). Palisades will apply the following acceptance criteria for valves with stroke times less than 10 seconds: If an increase in stroke time of 25% or more from the previous test for valves with stroke time greater than 10 seconds or 50% or more for valves with stroke time from 5 to 10 seconds, or an increase of 5 seconds for valves with stroke times under 5 seconds, test frequency shall be increased to once each month until corrective action is taken, at which time the original test frequency shall be resumed.
DESCRIPTION OF PUMP AND VALVE TESTING PROGRAMS Complete descriptions of the established procedures for inservice testing of selected pumps and valves are included in the Palisades Plant Engineering Manual~ Procedure No EM-09-04, dated 10/14/76, provides general require-ments for the performance and administration of the inservice testing program for selected pumps. Procedure No EM-09-02, dated 10/29/76, provides general requirements for the performance, administration and evaluation of inservice testing and exercising of selected valves. III-2
ATTACHMENT IV Supplemental Information On Code Update & Code Implementation
The following notes delineate, in. part, the implementation of Section :x:I through the Palisades Technical Specifications. No relief is requested for any of the items which follow. This attachment was written to impart to the regulatory authority information concerning previously approved relief requests which are hereby withdrawn, or information concerning our inability to perform examinations due to the nonexistance of components or to document our interpretation of the Code.
- 1. Item Bl. 5 (Vessel Penetrations)
BASIS STATEMENT Penetration welds can be subjected to the visual examination during the prestart-up hydro. REMARKS 1971 Code called for volumetric inspection of all vessel penetrations in-cluding CRDs. The 1974 Code now lists CRD housing welds as Bl.18, B-0, requiring volumetric examination of the peripheral CRD housing welds. The Bl.5 examination is a hydro visual only. Both the Bl.18 and Bl.5 examina-tions can be performed and will be so scheduled. IMPLEMENTATION No relief requested.
- 2. Item Bl.11 (Pressure Retaining Bolting)
BASIS STATEMENT None. REMARKS The original exemption addressed bolting~ 2 11
- The 1971 Code and the 1974 Code both address bolting~ 2". Since certain penetration bolting falls in this category and will at times be available for VT Examination, this category will be added to the 40-year plan.
IMPLEMENTATION No relief requested. IV-1
- 3. Item Bl.12 (Vessel Supports)
BASIS STATEMENT The vessel supports are welded to bosses integrally formed from I'ein-. forcing material that is part of the nozzle forging. The bosses repre-sent material beyond that which is required for the nozzles themselves. It can be postulated that the support weld heat affected zone may extend into the material within the normal nozzle geometry. This would con-servatively identify these supports as integrally welded to nozzles. Category B-H specifically excludes supports integrally welded to nozzles from the required exams. Therefore, these weld areas need not be examined. See CE Dwg E-232-111-3 and E-232-116-5. IMPLEMENTATION No relief requested.
- 4. Item Bl.15 (Vessel Interiors)
- BASIS STATEMENT None.
REMARKS Remote visual-examination to be conduct~d u5iiig.-,:lliderwater-TV camera. IMPLEMENTATION No relief requested *
- IV-2
**\
- 5. Item Bl.16 (Interior attachments and core support structure)
BASIS STATEMENT None. REMARKS Category B-N-2 applies only to BWRs. Therefore, no inspection is required for the bottom snubbers and drop prevention supports. - IMPLEMENTATION No relief requested (none required) * . 6. Item Bl.17 (Core support structure) BASIS STATEMENT None. The core barrel flange and associated vessel support ledge are *inspectable and will be so scheduled. IMPLEMENTATION No relief' requested. IV-3
- 7. Item B2.2 BASIS STATEMENT See Item 23.
REMARKS AJ.l nonexempt penetrations will be examined in accordance with the cited code. Exempt components will be examined in accordance with IWA/IWB-5000. IMPLEMENTATION No relief requested*.
- 8. Item B2. 3 (Heater penetra ti. ons)
BASIS STATEMENT None.
"REMARKS 74875 requires VT during hydro only. This examination will be scheduled.
- IMPLEMENTATION No relief requested.
- 9. Item 2.4 (Heater penetration) (IS-261)
BASIS STATJ!MENT None. REMARKS Heater Connections (E~2)° ha~_no 74s75 counterpart. IMPLEMENTATION No relief requested. IV-4
\
- 10. Item B2.4 {Nozzle-to-safe-end welds)
BASIS STATllMENT There are 14 d.issimiliar metal nozzle-to-safe-end welds, of which eight are one inch level nozzles. The vessel stainless cladding is carried over the weld ends of the carbon steel nozzles. The safe ends are either stain-less or Inconel. The nozzles-to-safe-end welds appear as Category B2.4, B-F. REMARKS See CE Dwg #-231-985-11. IMPLEMENTATION No relief requested. J ll. Item B2.5, B2.6, B2.7 {B-G-1) (Pressure retaining bolting) BASIS STATEMENT None. REMARKS There is no pressurizer bolting ~2 IMPLEMENTATION*. 11 No relief requested (none required).
- 12. Item B2.8 (Integrally welded vessel supports)
BASIS STATEMENT The welds can be volumetrically inspected and will be so scheduled. None. IMPLEMENTATION No relief requested. IV-5
- 13. Item B3.l (Long and circ welds, steam generator)
BASIS STATEMENT None. REMARKS Original Technical Specifications appear to be in error since these welds do exist and are inspecta.ble. The welds will be so scheduled. IMPL:EMENTATION No relief requested.
- 14. Item B3.4, B3.5, and B3.6 (B-G-1) (Pressure retaining bolting)
BASIS STATEMENT None REMARKS There is no steam generator bolting ~2" *
- IMPLEMENTATION No relief requested (none required).
- rr-6
- 15. Item B4.l BASIS STATEMENT There are six nozzle-to-safe-end dissimilar metal welds and 49 pipe-to-nozzle dissimilar metal welds of which 40 are smaller than l". The nozzle-to-safe-end welds will appear as B4.l, B-F and the pipe-to-nozzle welds as branch connection B4.6 or B4.7, B-J.
The primary coolant pump suction/discharge-to-transition piece welds are dissimilar metal welds. Since there is no pUm.p-to-safe-end category, these will be arbitrarily classed B4.l, B-F. REMARKS See CE Dwg E-232-673-7, E232-675-4 and E-232-676-7. IMPLEMENTATION No relief requested.
- 16. Item B4.2, B4.3, B4.4, (B-G-1) (Pressure retaining bolting)
BASIS STATEMENT None.
- REMARKS There is no pipe bolting~2".
IMPLEMENTATION No relief requested.(none required).
- 17. Item B5.l, B5.2 and B5.3 BASIS STATEMENT None.
VT can be performed on PCS pump nuts and ligaments during teardown inspection and will be so scheduled. IMPLEMENTATION No relief requested. IV-7
~
t' e -
- 18. Item B5.4 BASIS STATEMENT The primary coolant pump s\Ipports are thought to be welded to the cast stainless casings with partial penetration welds. UT Examination will be attempted.
REMARKS See BJ Dwg 2F-1129. IMPLEMENTATION No relief requested.
- 19. Item B5.6 BASIS STATEMENT Pump casing material and design make meaningf'u.l UT Examination of t.he welds difficult. Area background will preclude RT. UT.Examination will be attempted, probably from the inside of the pump casing *
- REMARKS Casing is cast stainless.
IMPLEMENTATION No relief requested at this time.
- 20. Item B5.7 BASIS STAT:EMENT None.
REMARKS The visual examination can be performed on pump teardown and will be so scheduled. IMPLEMENTATION No relief requested *
- IV-8
- 21. Items B6.l, B6.2, B6.3 (B-G-1) (Valve bolting)
BASIS STATEMENT None. REMARKS No
- valve bolting ~2".
IMPLEMENTATION No relief requested (none required).
- 22. Item B6.6 (B-M-1) (Valve seam welds)
BASIS STATEMENT None. No seam welded valves have been used. IMPLEMENTATION No relief requested (none required).
- IV-9
- 23. Generic Statement on Code Allowable Exemptions BASIS STATEMENT ASME B&PV Code, Section XI. 74S75 Edition REMARKS The 40-year Master Plan implements the above cited code to include frequency of examinations, extent of examination, the type of examination and perin.itted exemption except as delineated in notes 1 through 22 above.
The 40 year Master Plan implements exemptions pursuant to the following paragraphs of the above cited code.
- 1. IWB-1220
- 2. IWB-2500
- 3. IWB-2600
- 4. IWB-5000
- 5. IWC-1220
- 6. IWC-2500
- 7. IWC-2600
- 8. IWC-5000
- 9. IWD-2600
- 10. IWD- 5000
- IMPLEMENTATION No relief requested (none required) *
- IV-10
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COMPARISON OF IWB-26o0 & IS-261
- INTRODCJCTION The attached table compares Section XI IWB-2600 (74s75) and IS 261 (71).
The table was drawn up for internal accounting purposes. A need exists to document and follow the evolution of both the ASME E&PV Code, Section XI, and the ISI portion of the Palisades Technical Specifications. This is important because of the requirement (10 CFR 50.55a(g)) to update the Technical Spec-ifications ISI program every 40 months and because Palisades was constructed prior to 1971. A few words of explanation concerning the tables may be helpful in inter-preting them.
- 1. It is not possible to make a one-to-one correspondence between Item Numbers in each Code Edition. Additionally, there is not a direct correspondence between the Section XI category components to be examined, or the examination method under each item number.
- 2. The remarks section attempts to delineate the history behind relief requests. The remarks section contains four categories of statements concerning the history of relief requests.
- a. No relief requested
- b. Relief request in the past and the present
- c. Relief requested in the past but not in the *present
- d. No relief in the past, but relief is presently requested
- 3. The table does not include Class 2 components since Class 2 was not inspected pursuant to the 1971 Section XI Code *
- V-1
Rev. 1 Page 1 of 3 5/ll/78 COMPARISON OF IWB-2600 & IS261 Item Nwnber Component Remarks IWB-26oO rs261 Bl.l 1.1 Rx Vessel Welds - Beltline Region No Relief Requested Bl.2 1.2 Rx Vessel Welds - Non Beltline Relief Requested from IWB-2600 & IS261 Bl.3 1.3 Vessel-to-Flange & Flange-to-head Relief Request from IWB-2600 Bl.4 1.4 Nozzle-to-Vessel Relief Request from IWB-2600 Bl.5 1.6 Vessel Penetrations No Relief Requested Bl.6 1.7 Nozzle-to-Safe ends Relief Requested from IWB-2600 & IS261 Bl.7 1.8 Closure Studsc2" No Relief Requested Bl,8 1.8 Closure Studs ~2" No Relief Requested Bl.9 1.9 Ligaments between Stud Holes No Relief Requested Bl.10 1.10 Closure Washers No Relief Requested <I Bolting< 2" No Relief Requested f\) Bl.11 1.11 Bl.12 1.12 Integrally Welded Supports No Relief Requested Bl.13 1.13 Closure Head Cladding No Relief Requested Bl.14 1.14 Vessel Cladding Relief Requested from IWB-26oO Bl.15 1.15 Vessel Interior No Relief Requested
.:J Bl.16 1.15 Interior Attachments Not Applicable to PWR Bl.17 1.15 Core Support Structure No Relief Requested Bl.18 1.5 CRD Housing No Relief Requested from IWB-26oO Relief Formerly Requested from IS261 Bl.19 Exempted Components Exemptions will be Inacordance with Section XI, 74875, and Specific Relief Granted by the NRC B2.l 2.1 Longitudinal & Circwnferential Welds No Relfef' Request B2.2 2,2 Nozzle-to-Vessel Welds No Relief' Request B2.3 2.3, 2.4 Heater Penetraticns No Relief Request Relief Formerly Requested from i tern 2.3, rs261
~
IWB-2600 B2.4 B2.5 Is261 2.5 Component Nozzle-to-Safe end Bolting ~2"
- Remarks Rev. 1 Page 2 of 3 5/11/78 Relief Formerly Requested from item 2.2 Is26r; Relief Formerly Requested from item 2,5 rs261 B2,6 2.5 Bolting~2" Relief Formerly Requested from item 2.5 rs261 B2.7 2.5 Bolting ~2" Relief Formerly Requested from item 2.5 rs261 B2.8 2.7 Integrally Welded Supports Relief Formerly Requested from item 2, 7 rs261 B2.9 2.8 Vessel Cladding No Relief' Requested B2.10 Exempted Components See Item Bl.19 Above B2.ll 2.6 Bolting<2" No Relief Requested B3.l 3.1 Longitudinal & Circumferential Welds Steam Generator No Relief Request and Heat Exchangers Relief Formerly Requested from IS261 B3.2 3.2 Nozzle-to-Head Welds No Relief Request B3.3 3.3 Safe-Ends See Item Bl.6 above
<! B3.4 3.4
- Bolting ;::_2 11 No Relief Requested I
w B3.5 3.4 Bolting ~2" No Relief Requested B3.6 3.4 Bolting ;::2" No Relief Requested B3.7 3.6 Integrally Welded Supports No Relief Requested B3.8 3.7 Vessel Cladding No Relief Requested B3.9 Exempted Components See Item Bl.19 above B3.10 3.5 Bolting<2" No Relief Requested B4.l 4.1 Safe-end-Welds Relief Requested from IWB-26oO & IS261 B4.2 4.3 Bolting~2" No R~lief Requested B4.3 4.3 Bolting2:2" No Relief Requested B4.4 4.3 Bolting C:,2" No Relief Requested B4.5 4.2, 4.7 Longitudinal & Circumferential Pipe Welds Relief Request from IWB-2600 B4.6 4.2 Branch Connection Welds> 6" Diameter Relief Request from IWB-2600 _____J
Rev. 1 Pa,ge/3 of 3 5/11 78 Item Number Component Remarks IWD-26oO rs261 B4.'( 4.2, 4.8 Branch Connection Welds~ 6 11 Diameter No Relief Requested B4.8 4.8 Socket Welds No Relief Requested B4.9 4.5 Integrally Welded Supports Relief Requested from IWD-2600 B4.10 4.6 Support Components No Relief Requested B4.ll Exempted ComponEnts See Item Bl.19 above B4.12 B5.l 4.4 5.4 Bolting (2" Bolting~2" No Relief Requested No Relief Requested e. B5.2 5.4 Bolting ~? No Relief Requested B5.3 5.4 Bolting 2:2"* No Relief Requested B5.4 5.6 Integrally Welded Supports No Relief Requested B5.5 5.7 Support Components No Relief Requested B5.6 5.1 Pump Casing Welds' No Relief Requested; Relief Formerly Requested from IS261 <: B5. 7 5.2 Pump Casing No Relief Requested; Relief 1 Formerly Requested from IS261 I B5.8 Exempt Components + See Bl.19 above B5.9 5.5 Pressure retaining Bolting No Relief Requested B6.l 6.4 Bolting ?,2" No Relief Requested B6.2 6.4 Bolting 2: 2" No Relief Requested
~
B6.3 6.4 Bolting ~2" No Relief Requested B6.4 6.6 Integrally Welded Supports No Relief Requested B6.5 6.7 Support Components No Relief Requested B6.6 6.1 Valve Body Welds No Relief Requested B6,7 6.2 Valve Body No Relief Requested B6.8 Exempt Components See Bl.19 above B6.9 6.5 Bolting( 2" No Relief Requested
ATI'ACHMENT VI INSERVICE INSPECTION 40-YEAR PL.AN AND PUMP AND VPL VE PROGRAM
INSERVICE INSPECTION ON 40-YEAR PLAN EXTENT OF COVERAGE
The Palisades Plant Inservice Inspection Program has been updated per 10 CFR 50, Section 50.55a requirements as noted below:
- a. Applicable Code: ASME E&PV Code Secti'on XI, 1974 Edition through Summer '75 Addenda*
- b. Period of Applicability: 10/31/76 through 2/28/SO (current interval 12/31/71 through 6/30/83).
- c. Component Identification: This attachment covers the extent o~ the ISI program. Tables within the program plan itemize ea.ch component by a unique identifier and list ASHE Section XI item number and category.
Components were selected for coverage by the plan through use of the Palisades Code Classification P&ID (developed by application of Reg Guide 1.26) for Classes 1, 2. and 3 components and Technical Specifica-tions, Section 4.12 for the high energy piping.
- d. Inservice Requirements: Examination categories and methods are detailed within the program plan. The plan requires that code unacceptable dis-continuities by dispositioned through application of Consumers Power Quality Assurance Program Procedure 16-51, Deviations. .Fulfilling the requirements of this procedure will initiate, as required, addi-tional code (IWB-2430, IWC-2430, IW-4000) requirements which will be implemented by plant and/or General Office procedures, as necessary
- VI-1
The Plan covers the four 10-yee.r inspection intervals that comprise the 40-year lifetime of the plant. Selected portions of the major components and/or systems to be e..~a.mined in accordance vith Section XI are as follows: (1) Class 1 (a) Reactor Pressure Vessel (b) Reactor Pressu:e Vessel Closure Head (c) Steam Generators - Primary Side
. ( d) Pressurizer (e) Piping (i) Prima.l7 Goola.nt System (ii) Engineered Sa.feguards System (iii) Chemica.J. a.nd Volume Control System
(_f) Pr:f.Lla.r-.r Coolant Pumps (g) Valves (2) Class 2 (a.) Pressure Vessels: (i) Air Receiver Tanks (ii) Deborating Ion Exchanger (iii) Concentrated Boric Acid Tanks (iv) Volume Control Tank. (v) Safety Injection* Tanks (vi) Boric Acid Fi1ter (vii) Purification Filters (viii) Steam Genera.tors - Secondar.r Side (ix) Regenerative Heat Exchangers (x) Letdo~-n Heat Exchanger {xi) Shutdovn Cooling Heat Exchangers VI-2
- (b) Piping:
(i) Primary Coolant System (ii) Ma.in Steam System (iii) Feed;rater System. (iv) Engineered Sai'eguards System (v) Chemical and Volume Control System (vi) Primary Makeup Water System (vii) Radwa.ste System (viii) Waste Gas System (L"t) Vent and Air Conditioning System (x) Contaimnent Air System (c) Pumps: ( l. I Containment Spray Pumps (ij) Charging Pumps
*(iii) Concentrated Boric Acid Pumps (iv) High Pressure Sa.f'ety Injection Pumps (v) Low Pressure Sa.f'ety Injection Pumps (3) Class 3 (a) Pressure Vessels:
(i) Condensate Storage Tank (ii) Component Cooling Surge Tank (iii) Emergency Diesel Generator Day Tanks (iv) Fuel Pool Demineralizer Tank ( v) Ra.dva.ste Demineralizer Tanks V~cuum Degasifier Ta.nk (vi) (vii) Safety Injection and Refueling Water Tank. (viii) Shield Cooling Ta.'1...lt VI-3
..-'\.
(ix) Waste Gas Surge Tank (x) Waste Gas Decay Tanks (xi) Spent Resin Storage Tank (xii) Quench Tank (xiii) Prima.r,r System. Drain Tank (xiv) Pril!lar.r System Make-up Storage Tank (:x.v) Clean Waste Distillate Tank (xvi) Radwaste Polishing De!!lineralizer Tank. (xvii) ?A'.iscellaneous Waste Distillate Tanks (rriii) Spent Resin Storage Tank (addition) (xix) Waste Gas Decay Tanks (addition) (:qc) (.xxi.) (:a.ii) Iodine Re!ll.oval Na.OH Tank Iodine Removal Make-up Ua.OH Ta.Ilk Vacuum Degasifier Seal. Coolant Tank (xxiii) Fuel Peel Fi1ter (=iv) Dirty Waste Filter (xxv) ta.uncL."j" Drain FiJ.ter ' (xxvi) Primary System Filters (xxvii) Evaporate Concentrate Filter (xxviii) Miscellaneous Wa.ste FiJ.ter (x:d.x} Spent Fuel Pool Heat Exchangers (xxx) Component Cooling Heat Exchangers (x:xxi) Letdown Heat Exchanger (xx:d.i) Shutdo'Wll Cooling Heat Exchangers (.x:cdii) (x:cd.v) Shield Cooling Heat Exchanger Radwaste Evaporators VI-4
- (xxxv)
(xxxvi) Engineered Safeguards Room Coolers Control Room Air Conditioning Units (xxxvii) Contai:cm.ent Air Coolers (b) Piping: (i) Primary Coolant System (ii) Main Steam System (iii) Feedwa.ter System (iv) Engineered Safeguards System (v) Chemical and Volume Control System (vi) Service Water System (vii) Component Cooling System (viii) Waste Gas System (ix) Rad.waste System (x) Shield Cooling System (xi) Chemical Addition System (xii) Emergency Power System (xiii) Ventilation and Air Conditioning System. (xiv) Spent Fuel Pool System (xv) Makeup and Domestic Water Sy3tem (xvi) Primar/ Makeup Water System (xvii) Utility Water System (c) Pumps: (i) Service Water Pumps (ii) Auxil.ia...-y Feedvater Pumps (iii) Fuel Pool Cooling Pum~s (iv) Component Cooling Pumps (v) SIRW Tank RecircuJ.aticn Pump V:C-5
{vi) Shield Cooling Pumps {vii) Miscellaneous Waste Distillate Pumps {viii) Miscellaneous Waste Tra,.nsf'er Pumps {ix) Clean Waste Transf'er Pump . (x) Evaporator Concentrate Transfer Pumps (xi) Recycled Boric Acid Pump. (xii) Clean Waste Distillate Pumj;>s {xiii) Steam. Generator Blowdavn Pumps (xiv) Waste Gas Compressors (xv) Vacuum Degasifier Compressor (xvi) Waste Gas Compr~osor (addition) (mi) Auziliar,r FeedYater Pump Tt.u-bine Drive~ ~: VI-6
-~
I PUMP AND VALVE PROGRAM EXTENT OF COVERAGE
Pump and Valve Testing Program
- a. Applicable Code: AS.ME B&PV Code, Section XI, l974 Edition through Summer '75 Addenda.
- b. Period of Applicability: 11/1/76 - 6/30/78.
- c. Pump Testing (1) Component Identification: Attachment 2, Table 1, lists the applicable pumps. Pumps not included were included as a part of the relief request previously transmitted in our March 1, 1977 letter~
(2) Measured Para.meters: These will include, typically, bearing temperature, vibration, suction head, flow and discharge pressure. From certain of these measurements, suction pressure and differ-ential pressure will be calculated as defined in the Palisades Plant Engineering Manual Procedure EM-09-04, Pumps. (3) Test Intervals: Testing will be performed monthly except during plant shutdown and 96 hours after return to service following replacement or repair affecting pump performance. The test fre-quency is to be increased if performance is determined marginal. (4) Complete details are contained in the Palisades Plant Engineering Manual, Procedure EM-09-04, Pumps.
- d. Valve Testing The valves covered were selected in accordance with the guidelines of Section XI, Subsection rilV and include all Classes l, 2* and 3 valves in the following classifications:
(1) Those valves required to operate following a LOCA, including containment penetration isolation valves. (2) Valves affording protection to a system or component, such as relief valves and rupture discs. (3) Boundary valves which prevent the unintentional release of radio-active fluids or gases to the water or atmosphere outside the containment and auxiliary buildings. (4) Additional valves not having a specific safety function but con-sidered important enough from a reactor or radiological safety standpoint to warrant special testing. (5) Complete details are contained in the Palisades Plant Engineering Manual Procedure EM-09-02, Valves. All remaining plant valves are considered installed for operating con-venience or maintenance and, therefor*e, are not included in this program .
(6.) Categories A
& B Exercise Test:
On a quarterly basis, all valves indicated "Category A or B"
- in Table 2 of Attachment 2 shall be exercised Wlless valve operation is not practical during plant operation. If valve operation is not practical, the following applies:
(a) Normally open valves, where practical without imposing undue risk to equipment or plant operation, shall be exercised by uartially closing and then reopening the valve. These valves shall then be full-stroke exercised during ~ cold shutdown. (b) Normally closed valves which cannot be opened during plant operation are identified in each individual test procedure. These valves shall be full-stroke exercised during each cold shutdown. (c) If frequent cold shutdowns occur, these valves need not be exercised more often than once every three months. (7) Category A Leak Test: During each refueling outage, but not less than once every two years, all Category A. valves identified in Table 2 of Attachment 2 shall be tested to determine seat leakage rates. (8) Category C Exercising Test: On a quarterly basis, check valves listed in Table 2 of Attach-
- ment 2 as Category C shall be exercised Wlless valve operation is not practical during plant operation. For normally open valves, if only limited operation is practical during plant operation, each valve shall be part-stroke exercised each quarter, and full-stroke exercised during each cold shutdown.
Normally closed valves which cannot be exercised during plant operation shall be identified in the individual valve test procedure and will be full-stroke exercised during each cold shutdown. In the case of frequent cold shutdowns, valves which cannot be exercised or which can only be part-stroke exercised during plant operation need not be full-stroke exercised more frequently than once every nine months. (9) Category C Set Point Test: All Category C safety and relief valves shall have their set points verified at least once in each five-year period. The valve tests shall be distributed over each 60-month period such that N/60 X 141 valves have been tested by the end of each re-fueling outage, where N = number of months from the start of the 60-month period to the end of each refueling outage and 141 is the total number of reliefs which are included in this program. (10) Categories D & E Valves:
. Categories D and E valves are listed in Table 2 of Attachment 2 for information only. There are no special testing requirements applicable to Palisades for these categories. The code-required position verifications are satisfied by Palisades Plant Opera-tions Department Checklists and Operating Procedures.
- TABLE 1 PUMP TESTING REQUIREMENTS
- ASME TEST
~ CLASS PROCEDURE P7A, B, C, Service Water Pumps 3
- M0-16 P8A, B, Auxiliary.Feedw.ter Pumps 3 M0-24 P52A, B, C, Component Cooling Pumps 3 M0-18 P54, A, B, C, Containment Spray Pumps 2 M0-19 P5;A, B, C, Charging Pumps 2 M0-20 P56A, B, Boric Acid Pumps 2 M0-21 P66A, B, C, HP Safety InJ ection Pumps 2 M0-22
- P67A, B, LP Safety Injection Ptmt!>s 2 M0-23
- Based on ASME B&PV Section XI, 1974 edition, with Addenda through s75.
Includes those pumps important to Reactor sat'ety which transfer automaticalJ.y and restart on an emergency power supply under accident conditions
- e -
- Page
- l of .12 '"'
TABLE 2 TITLE: mSERVICE TESTING OF PLANT VALVES SEC Xl ASME SCHED PLMIT PROCEDURE VALVE CAT. SYSTEM/P&ID CODE jrREQ CLASE !EXERCISE LK TEST l?t.AINT. CONTAI?lMENT ISOLATION ** -. CV-0155
.cv-0120 A PMW M20l/H-7 ' P42 z Q/R Q0-5 S0-2 -
ev-0121 A A PCS PCS HZOl/F-7 P20 2 Q/R Q0-5 - M20l/F-7 P20 2 Q/P.. Q0-5 - cv-2oa*3 A eve M202/G-6 P44 2 Q/R Q0-5 - . CV-2009 A B. eve M202/G-6 P36 2 Q/R Q0-5 so-2 - CV-3001 CV-3002 ESS ESS M20:3/H-2 ,- - ?30 2 Q Q0-5 - - B M203/G-2. P3l 2 Q Q0-5 - MOV-301.S. HOV-3016 B B ESS
- ESS MZ04/D-2 M.104/D;,,.z
!':3.S;.,~
P35 l l Q Q
~
~*
CV-3029 B ESS
- M204/C-2.* P53 2. Q - -
CV-3030 . B ESS . H204/C-3
- P54 2 Q - -
SV-U824 B sws sws M208/B-5 PlJ 3 Q - - SV-0847 B M208/B-4 Pl2 3 Q - - CV-0911 A ccs M209/A-6 PlS. 2 Q/R. Q0-5 so-2 - CV-0910 ccs A H209/E-5 Pl4 2 Q/R Q0-5 S0-2 - CV-0940 A ccs M209/A-5 PlS 2 Q/R Q0-5 S0-2 - cv-1001 A ms M2l.0/G-7 ~37 2 Q/R QO-S so-z - cv-1002 CV-1004 A A RWS M2l.O/G-7 P47 2 Q/R Q0-:5 S0-2. - RWS M210/R-5 P4l 2 Q/R Q0-5 S0-2 - I C'"i-1064 CV-1036 A A
.RWS RWS MZlO/G-l M2l.0/E-l P25 P49 .
2 Q/R. Q0-5 so-z - 2 ~/R Q0-5 so-z - CV-10.37 A CV-1044 P.IJS M2.l0/E-l P67 2 Q/R. Q0-5. 50-2 - A RW°S M.210/E-2 P69 2 Q/R QO-S tS0-2 - CV-1007 A RYS M210/F-7 P47 2 ~/R Q0-5 so-2 CV-1038 A RWS
- M210/E-l P49 2 Q/R IQ0-5
~0-2 -
C:V-1045 A !RwS M2l0/E-Z P69 2 Q/R Q0-5 0-2 - CV-1065 A P.WS M2l0/G-l 1'25 I 2 Q/R ~o-s_ ~0-2 - ...
Page 2 of 12 TABLE 2 TITLE: INSERVICE TESTING OF PLANT VALVES SEC :;a ~ SCHED PLANT.PROCEDURE VALVE w. SYSTEM/P&ID ~ODE 1-"T.AC!C: FBEQ. EXERCISE IX TEST ~..AINT. CON'!ATIIMENT ISOL.\TIOM z ~co:ntd) cv-1101 A 3.WS M2ll/H-7 P46 2* Q/R Q0-5 so-2 - CV-1103 A. RWS M2ll/D-7 P52 2 Q/P. Q0-5 S0-2 -
.CV-1104 A :a.w5 M2ll/D-7 P52 2 Q/R qo...:s so-2 -
cv-1102 A R.!'15 M2ll/H-7 P46 2 Q/R Q0-5 so-2 - CV-12ll B C.\S M2ll/D-2 P65 2 Q Q0-5 - - CV-1501 . A VAS M2l.5/G-2 p33* 2 Q/P. Q0-5 so-2 *- CV-1503
- A . VAs Mll5/H':""2 P39 2* Q/R Q0-5 50"'!2 -
- CV-1502
~l-1806 CV-1808 CV.-1314 A.
A A A VAS VAS VAS VAS M2l..S/G-3 M2l8/E-3 M2lS/D-l 11218/D-2 P38 P4 Pl P68 2 Q/R. 2 O}R 2 Q/R 2 Q/R Q0-5 Q0-5 Q0-5 Q0-5 so-z so-2 S0-2 S0-2.* CV-1803 A VAS M2l8/F-3 P4- 2 Q/P. Q0-5 S0-2 -* CV-1805 A VAS M218/'E-3 P4 2 Q/R Q0-5 so-2 - CV-1807 A VAS M2l8/'Z-l Pl 2 Q/R Q0-5 so-2 - CV-1813 A VAS MZ18/E-2 P68 z Q/R Q0-5 . so-2 - I CV-191.l A PCS M2l9/E-7 P40. 2* Q/R Q0-5 S0-2 - CV-1910 A PCS M219/F.-7 1'40 2 Q/R Q0-5 so-z - CV-0939 A scs M221/G-2 ?ll 2 Q/R. QO-S' S0-2 . - CV-1358 A MGS M222/R-5 P26 2 Q/R Q0-5 S0-2 - I! cv.:..0733 A. MSS M22-0/D-7 P55 2 Q/R Q0-5 - CV-0771. A MSS H.226/G-7 PS 2 ~/R Q0-5 - CV-0770 A MSS M226/F~7 P6 2 [Q/R Q0-5 - CV-0739 A MSS MZZ6/E-8 Pl6 , 2 ~/R Q0-5 -
- cv-01,a
- V-0767
.A A
MSS
. s M226/:r-a M226/F-8 PS P6 l
2 2 Q/R Q/R qo-s qo-s ...
Page*3 of 12 TABLE 2 TITLE: INSERVICE TESTING OF PLA.."'IT VALVES . SEC XI ASME scm:n PLANT PROCEDURE VALVE . f'!AT. SYSTEM/P&:ID. CODE raEQ CLASS EXERCISE LK TEST MAn*rl'. BOUNDA.-it'? VALVES
?-!OV-2087 B eve M202/E-6 2. Q - -
MOV-2169 B eve 11202/D-2 2 Q - - MCV-2170 B eve HZ02/D-3. 2 Q. - - MOV-2140 B eve M202/C-5 z Q - - CV-2l.30 B eve MZ02/E-Z 2. Q - - CV-2155 B eve M20Z/D-5 2 Q .- - ev-2136 B eve MZOZ/E-3 2 Q - . MQV.;.3009- B ESS M203/E-3 .l Q Q0-5 _, MOV-3064 B ESS M203/C-3 . l Q Q0-5 - - l-!OV-3010 B
- ESS 11203/B-3 . l Q Q0-5 - -
MOV-3007 B ESS M203/F-3 l. Q Q0-5 - -
}!CV-3062 B ESS MZOJ/A-3 l Q Q0-5 - -
MOV-3008 B ESS M203/E-3 l Q Q0-5. - - MOV-3011 B ESS MZOJ/C-3 l Q Q0-5 - - MOV-3066 . MOV-3012 B ESS M203/D-3 l Q Q0-5 - -. B ESS M203/B-3 l Q Q0-5 - - MOV-3068 B ESS M203/E-3 l Q Q0-5 - - MOV-3014 B ESS M203/A-3 l Q Q0-5 - CV-3042 B ESS M203/D-7 l Q - CV-3046 B ESS M203/D-6 l Q I MOV-3013 3 ESS M203/B-3 l Q. Q0-5 - - CV-3069 B ESS ?1203/C-8 3 Q CV-3047 B ESS MZ03/D-5 J. Q CV-3038 B ESS M203/D-4 l Q CV-0501 CV-0510
*B B
MSS MSS M205/R-8 M205/F..-7 2 2 Q Q . -
Page 4 o~ 12
~LE 2 TITLE: INSERVICE TESTING OF PLANT VALVES SEC XI ASME,SCHED PLAlIT PROCEDURE VALVE CAT. SYSTEM/P&ID CODE FREQ EXERCISE tK TEST MAINT.
,..,. i\~J::
I BOIDIDARY VALVES (Contd) C:V-0736A. B FHS H207/F.-8 2 Q - - CV-[J737A B :ws M207/F.-8 2 Q - - CV-0878 B S"..;s M208/C-3 3 Q - - CV-0625- B sws M208/C 3 Q - - CV-0938 B ccs MZ09/G-3 3 Q - - CV-0950 . :B ccs M209/C-5 3. Q - -
- CV-0913 CV-0937 CV-1049 CV-1051.
B B B B ccs ccs' B.t*1S Rt~S M209/D-3 M209/G-3 M2l0/B-3 M2l0/A-3 3 Q 3 Q D* Q D* Q CV-lll3 A B.WS M2ll/H-S .3 Q/R - CV-1123 B RWS M211/R-3 3 Q - - CV-1359 B sws M2J.3/F.-8 3 Q - ~
TlTLE: INSERVICE TESTnIG OF PLANT VALVES VALVE lsEC XJ CAT. SYSTEM/P&ID
!f\SME SCBED PLA!IT PROCEDURE CODE !FREQ EXERCISE I
I.K TEST MA.INT. CLAS~ REI.In' VALVES ; LN-1039 c PCS 1-f.2 Ol / G-4 *1 F*
-* - H-PCS-ll RV-1040 c PCS M20l/G-4 l F - - M-PCS-11 RV-1041 c PCS M20l/G-3 l F - - M-PCS-ll R.V-2006 c eve M202/G-8 2 F - -
R.V-2013 c eve M-202/H-4 2 F - .. R.V-2079 c eve M202 E-6 z F - - R.V-2080 c eve .M202/E-6 2 F - .- R.V~2090 RV-2092 c c eve
- eve Hl02/C-!i M202/C-7 2 F 2' F
- :311 R.V-2096 c eve M20Z/'B-6 .2 F - - M-<:VC-Z RV-2098 C. eve M202/B-7 2 F - - M-CVC-2 RV-llOZ c eve M2.02/A.-6 2 F - - M-CVC.:-2 KV-2104 c eve M202/A-7 2 F - - M-CVC-2 RV-2203 c eve M202/F-6 2. F - -
ltV-2230 c eve MZOZ/D-3 2. F - -
?.V-2231, c eve M202/C-2 2 F - -
RV-2232 c eve M202/C-3. 2 F - - RV-2233 c eve M202/C-3 2 F - - RV-2234 c eve M202/D-3 2 F - - RV-2235 c eve M202/D-2 2 F - - RV-223.S c eve
- 11202/D-4 2 ...
i:- RV-2237 c eve M202/D-4 z F - - B.V-2238 c eve M202/D-4 2 F - - RV-2239 e eve M202/D-5 2 F - - RV-2240 RV-2255 RV-3113 c c c eve eve ESS M202/D-5 M202/D-6 M203/F-7 2 2 2
.F F
.F
Page 6 of 12
- TABLE 2 i
TITLE: INSERVICE TESTING OF PLANT VALVES I I SEC XI IASME SCHED PLANT PROCEDURE i VALVE t:AT. SYSTEM/P&:ID :CODE FREQ :
~s EXERCISE LK TEST ~.AINT.
RELIEF VALVES ~Contd) RV-3128 c ESS M203/F-6 z -. - -- I RV-3143 c ESS M203/F-5 z F - - .. ! RV-3158 c ESS M203/F-4 z F - - I RV-3161 c ESS M203/D-7 3 F - - I I R.V-3161- c ESS MZ03/D-l z F - - I RV-3165 c ESS MZ03/F-l z F - -* RV-3264 .. c ESS M203/F-l z = - - I RV-0401 c ESS M204/D-l l ]" RV-0438 c ESS M204/R-l 3 F - - RV-3164 c ESS MZ04/E-Z 2 F - - RV-0457 c ESS M204/H-2 3 F - - I RV-3267 c ESS M204/B-5 *2 F - - R.V-3266 .. c_. ESS MZ04/C-6 2 F - . - RV-0402 c ESS M204/G-7 2 F - - RV-0403 c ESS MZ04/D-7 2 F - - R.V-0521 c MSS M205/C-8 3 - I
'I I
RV-0602 c MSS M206/G-8
- F - - I II I
RV-0606 c MSS M206/G-5
- F - -. i I
I RV-0701 c MSS M207/H-7 2 F - - M-i.'!SS-14 ' RV-0702 c MSS M207/F..-7 2 F - - 'M-i.'!SS-ll; I RV-0703 c MSS MZ07/H-8 2 F - - IM-i.'!SS-lL RV-0704 c MSS M207/"S.-8 2 F - - M-~S-1~
- a.v-0705 c 1-4'..SS M207/H-8 2 F - - ~-:..'!SS-14
- - M-MSS-1.4 RV-0706 c MSS M207/H-8 2 F RV-0707 c MSS * 't-f.207 /R-7 2 F - - ~-:.'!S S-14 RV-0708 c MSS M207/H-7 z F - - ~-MSS-ll.:. -RV*0709 c MSS
- M207/R-7 z "! - - !-~.SS-lL.,
. *'I j
e e Pag~ 7 o~ 14'- TABLE 2 TITLE: INSERVICE TESTING OF PLANT VAJ.}lES SEC ::a ~MES CEED PLAi.'lT PROCEDURE VALVE CAT. SYSTEM/P&ID CODE FREQ
~CISE LK TES'J ?-4'.AINT.
CT.Ass RELIEF-VALVES (Contd) RV-0710 c MSS '!-!207/H-7 2 F - - l-!~!SS-14. RV-0711 c MSS M207/E-7 2 F - - a-MSS-14 RV-0712 c HSS M207 /'E.-7 2 F - - '1:!-HSS=l4 RV-0713 c MSS M207/H-8 2 F - - M-.'1SS-14 RV-0714 c - MSS M207/H-8 2 F - - M--..'!SS-14 R.V-0715 c MSS MZ07/H-8 z F - - M-~SS-14 RV-0716 c l1SS M207/R-8 2 F - - M-l-!SS-14 RV-0717 RV-0718 R.V-0719 c
*c c
l1SS MSS MSS M207/H-8 M207/F.-8 H:l.07/H-7 2
. 2.
2 F F F. M-..4 H-:."!SS-14
- M-¥.SS-14 RV-0720 c ?1SS H207 /H-7 2 F - - M-MSS-14 RV-0721. c HSS "f:{..207 /H-7 2 F - - M-:.'fSS-14 RV-0722 c !.-!SS H207/F.-7 2 F - - M-MSS-14 RV-0723 c MSS M207/H.-8 2 F - -* M-MSS-14 R.V-0724 c MSS M207/R-8 2 F - - M-HSS-14 RV-0783 c HSS 11207/B-8 3 F - -
RV-0915 c ccs MZ09/G-l 3 F - - RV-0939 c ccs 11209/F-6 3 F - . - RV-0954 c ccs M209/R-5 3 F - - R.V-0955 c ccs M209/G-5 3 F - - RV-0936 c ccs M209!G-6. 3 F - - RV-1008 c RWS M210/C-7 3 F - - RV-1068 c RWS M.210/R:..6 3 F - - E.V-1069 c RWS MZlO/G-8 3 F - - RV-1.lll B.V-1114 RV-lll.5 c c c RWS RWS RwS MZll/G-6 M211/G-5 M211/'F-5 3 3 .F 3 F F
Pa.ge 8 o:f 12
- TABLE 2 TITLE: INSERVICE TESTING OF PLANT VALVES SEC XI ASME SCHED PLANT PROCEDURE VALVE CAT. *SYSTEM/P&ID CODE rnEQ ~CISE LlC TES'I ~.A.INT.
CLASS RELIEF VALVES (Contd) .. RV-lll9 c RwS M2ll/G-3 3 F - - R.V-ll20 c RWS M2ll/G-4 3 F - - RV-1121 c RWS M2ll/G-4 3 F - - R.V-ll.60 c 1U1S M2ll/G-2 3 F - *- RV-1161 c RWS M2ll/G:-2 3 F - - .. RV-1162 c lU.J'S M2ll/G-l 3 F - - RV-1163 c RWS M2ll/E-5 3 F - - RV-ll64 c R'WS M2ll/E-5 3 F RV-1478 c; EPS Mzl4/~2 3 F - .. - RV-1479 c EPS M214/F-5 3 F - - RV-1430 C* EPS M214/F-4 3 :E - -
- RV-1476 c EPS M2l.4/H-4 3 F - -
P~-2107 c scs M22l/G-3 3 F. - - R'T/-2101 c scs M22l/R-6 3 F - - 1: RV-2ll2 c scs M22l/R-6 3 F - - . h RV-2103 c scs M22l/li-5 3 F - - 'I I RV-2105 c scs M22l/G-6 3 F - - :1 RV-2106 c scs M221/G-5 3 F - -. RV-2111. c scs M22l/G-6 3 F - - RV-2108 c scs M221/E-6 3 F - - RV-2109 c S1iP
- M22l/D-7 3 F B.V2402 c MGS *M224/B-6 3 F - - '
RV-2404. c MGS M224/B-5 3 F - - I I I
Page* 9 ~f* 12 *t TABLE. 2 TITLE: INSERVICE TESTnm OF PLANT VALVES SEC XI ASME 3CHED PLANT PROCEDURE VALVE CAT. SYSTEM/P&ID CODE raEQ CLASS E:XERCISE LK TEST i-f..AINT. REI.IEE VALVES . (Cont:c!) RV.;_0441 c CAS MZ25/G-8 2 -. - - c - RV-3030A c CAS M225/G-6 2 F - RV-3030:B CAS M225/G-6 2 F - - RV-3031A c C.AS M22S/H-6 2 'F - - RV-303l.E c CAS M225/H-6 2 F - - RV-30Z9A c
.. c CAS 11225/G-3 . 2 F - -
RV-3029B CAS M225/G-3 2 F - - RV-3057.A. .c
. CAS M225/R-3 2 F - -
RV-30573 c CAs- M225/R-:I z F
....i::
RV-04.39 c CAS M225/G-l 2* - - RV-6003 c MSS M226/G-7
- F - -
RV-0004 c HSS M226/G-6
- F - -
P.v.:..sou c Rt;s M650/E-8 3 F - - RV-5015 c ruv-s M650/E-5 3 F - - RV-5021 c RWS M650/E-6 3 F - - RV-5009 c RtvS M650/C-6 3 F - - R.V-5010 c RWS M650/C-6 3 F - - R.V-5020 c RWS M650/D-6 3 F - -. RV'-5019 c RWS M650/A-5 3 F - - RV-5006 c RWS 1.-!650/:C::-2 - 3 : - - I RV-5013 c RYS M650/A-6 3 F - - RV-5105 c RWS M65l/G-2 3 F - - RV-5116 c Rt~S M65l/A-8 3 F - - R.V-5ll7 c IU;S }f..651/A-8 3 F RV-5138 c RWS M65l/E-5 3 F - - RV-5139. c RtlS M65l/A-7 3 F* - -
~ ... - ..... **--
Page 10 of 12 TABLE 2 TITLE: INSERVICE TESTING OF PI.ANT VALVES SEC :a lASME SCHED PLANT PROCEDURE VALVE CAT. SYSTEM/P&ID CODE !FREQ
!EXERCISE IX TEST! ?A.Amr.
CLAS:: RELIEF VAI.VES (Contd) RV-5140 c R1:lS M551/E-2 3 ... R.V-5141 c RWS M651/E-4 3 F - - RV-5106 c RWS M65l/F-2 3 F - - RV-74 c RWS Radwa.st:e Evap M59A 3 F - - RV-75 c RWS Radwast:e Evap H59A 3 F - - R.V-74 c. Rt1S Rad"traste Evap M59B 3 F - - P..V-75 c RWS Radwaste Evap H59B 3 F ... -
- *R.V-5203 RV-5204 RV-5206 c
c c D~l uws uws M65Z/F-7 _ M652/'B-6 M652/C-6 3 3 3 F F I R.V-5208A c m~-r . ~..652/E-6 3 F - - R.V-5208'B c D:W.'1 M652/E-6 3 F - - R.V-9001 c R.WS M657/G-6 3 F - - - RV-1053 c RWS M657/D-6 3 F - - RV-9002 c Rt~S M657/E-3 3 F - -
e e ,. Page' ll oT 12
.*~
TABLE 2 TITLE: INSERVICE TESTDrG OF PLANT VALVES SEC XI ASME SCRED PLANT PROCEDURE VALVE ~- SYSTEM/P&ID CODE FREQ EXERCISE IX TEST }1'-UNT. CLAS~ CHECK VALVES ** 701.553 .<\.C PMW 11201/G-7 :P42 2 Q/R so-2. - 310lES. BC ESS M203/C-8 l Q R0-33 - - 3ll6'ES
~
BC ESS M20.3/B-8 1 Q R0-33 - - 3l31ES BC ESS M203/E-8 l Q RC-33 - - 3l46ES BC ESS l-!ZOJ/A-8. l Q R0-33 - . JlOZES ESS M.203/D-7 R0-33 -* - BC l Q Jlli"ES BC ESS M203/D-0 l "Q R0-33 -
.313ZES . BC ESS M203/D-5 l Q R0-33 - ... ~
Jl4n:s BC ESS M103/D-4 l* Q R0-33 - - 09l0CC AC ccs M209/E-5 ?14 2 Q/R sa-z - l~ N276Y 11 AC Rt;s MZl.O/G-7 PS7 2 Q/R S0-2 -
.3 ?t238MZR AC RWS MllO/H-5
- P4l 2 Q/R S0-2 -
3"N238}!2!t AC RWS M2l0/E-l P67 2 Q/R so-z - I I 4"-257 AC VAS M215/E:-3 P39 2 Q/R so-z - r l~lf-223 AC scs M.221/G-Z Pll 2. O}R so-z - 1'0-223 AC MGS M222/R-5 P26 z Q/'B. S0-2 r
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Page 12 of 12
- TABLE 2 TITLE: INSERVICE TESTING OF PLANT VALVES SEC XI ASME 3CHED PLANT PROCEDURE VALVE. CAT. SYSTEM/P&ID ~~~... rnEQ EXERCISE LK TES'I MADIT.
RUP'rnRE DISCS R!!D-0162 D PCS ~1201/G-o RD-76 D RWS Rad7aste Evap. M.59A 3 ~;one RD-76 D RWS Radwaste Evap. ~.59B 3 Nena CATEGORY E VALVES 3234E5 E :ESS M204/G-8 1'33 2 N'one 3235£5 E ESS M204/G-7 P33 Z ~;one
- 3237ES l2ZCA 4 1"'2 9~..zlJR E
E ESS VAS M204/G-7 M2l2/B-2 MllS/E-2 P3.3 PlO P4 2 2 None. No-ca 4M29¥..2DR E VAS M218/E-2 P4 2 None ll8SFP E SFP MZll/C-3 P72 2 None ll7S!P E SFP M22l/C-3 P72 2 None l20SF? E SFP M22l/C-3 P64 2 N'ci:e 121.srP E Sn' M22l/C-3 P64 2 None P-l E N/A. PZ7 P-2 E N/A P27 2 None P-3 E N/A. P27 Z None 604V.~ E !l/A P27 2 ~one 605VA E N/A P27 , 2 None
"' Qual.it** Grou~ D Or unclassed valves.
Pressu' 0 vi** full. system functional d/p per Teoh. Spol. Cat:ego1:Y A V~ lves ~thin these groups tested a.t Cor.t:~ent "Penetratio l I.UT 0
LEGEND TESTING REQUIREMENTS Q Quarterly Operating Q/R Quarter Operating & During Refueling outages F Five Yea.rs
The Palisades Pwnp & Valve Testing Program for the 20-month interval beginning June 30, 1978 is summarized below: I. Applicable Code: .ASME J?&PV Code, Section XI, 1974 edition with addenda through summer 1975. II. Period of Applicability:
- 6/30/78 through February 28, 1980.
III. PUMP TEST PROGRAi"i The Palisades Inservice Pw:!lp Test Program is summarized in Table I. This Table includes the pump's name and number, safety class, P&ID, procedure used to test the pump, and ti1e parameters measured. All pumps tested under this program are tested monthly, except during cold shutdown, when they are tested within one week after plant startup. Pump testing is performed per the above referenced code, with the follow-ing exceptions:
- l. Plant system designs do not include -provisions for measuring the suction pressures of any of the pumps included in this prog:::;*am (as required by Table IWP 3100-1 of reference 3). Suction pressures will be calculated, as applicable, by taking the differences between each pump suction and its associated expansion tank level, plus expansion tank pressure.
- 2. Plant system designs do n:ot include provisions of measuring differ-ential pressures of any pumps included in this program. Th~refore, where applicable, differential pressure will be calculated by taking the difference between the discharge .pressure and the suction pres~ure calculated in (l) above.
- 3. The design of the service water pumps does not permit the measurement of bearing temperatures or monitoring of pump lubrication since the pump is submerged in water.
- 4. The design of' the charging pumps does not perinit measurement of bear-ing temperatures since the bearings are inaccessible unless the pumps are disassembled, and crankcase oil temperature is not. representative of' "oearing temperatu.T'es because of the installed oil coolers.
- 5. The design of t.he concerntrated Boric add pumps does not permit direct measurement of bearing temperatures. A representative temper-ature \1ill be obtained by measuring the surface contact temperatures of the bee.ring housings. Since there are no installed oil coolers, these tem:peratw:*es are responsive to oil temperatures which are, in turn, responsive to bearing temperatures.
- 6. If a result of' a pum9 test falls in the required action range) an evaluation of the deviation will be completed to determine if' trie pwap is capable of fulfillinf, its function. Only after it is <letermincd that the oumo is tm.::.ble to fulfill its function will corrective action be taken ;ts d~scr:i.1.Jed in Artj_cle HIT' 3230( c) of the above Code.
. 2
- IV. VALVE TEST PROGHAM The Palisades Inservice ,Valve Test Program is summarized in Table II.
Table includes the following: The
-Valve Number
-Safety Class
-P&ID Coordinate Location
-Valve ASME Section XI Category
-Valve Size
-Type
-Actuator Type
-Normal Position
-Safety Position
-Active or Passive
-Test Requirements (frequency)
-Relief Requested?
-Testing Alternatives
-Test Procedure The valves included in the Valve Test Program were selected in accordance with the NRC letter dated January 13, 1978 and the following guidelines.
1.) Those valves which are required to function to safely shutdown the Plant, in the event of an accident. 2.) Those valves which are required to operate to mitigate the consequences of an accident. 3.) Those valves which are required to i"'uncti on to prevent the uninten-tional release of radioactive fluids or gases to the outside atmosphere. 4.) Valves affording a safety related overpressurization function. All remaining valves are considered installed for operating convenience of maintenance, and are therefore not included in the Valve Test Program. The valves included in Table II are tested per the req_uirem.ents of the above referenced code, with the following exceptions: 1.) The following normally open valves will be tested during cold shutdown but not more often than once eve~ three months:
- a. CV 0910, 0910 CC, CV 9011, and CV 901.i.o: Component Cooling Containment Isola ti on Valves. Cycliri...::s these valves during opera-tion would result in the interruption of cooling water flow to the primary coolant pump seals and let down heat exchanger. This may result in damage to the pwnp seals, which would place the Plant in an unsafe mode of operation *
- b. MOV 2087 (Volume Control Tank discharge) and C'f 2009 (Letdown Containment Isolation V":l.lve): Cycling of these valves duri:ng operation would isolate letdown flow, which is an wmorrnal mode of ope:ration.
PUMP AND VAI..VE PROGRAM EXTENT OF COVERAGE
TABLE l.
- INSERVICE PUMP TEST PROGRAM
SUMMARY
INSERVICE TESTING OF PUMPq AND VALVES EXTENT OF COVERAGE
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".,;.:~***-=*** *1 Final Set point PERFdR'.fED BY:
D2.te I Calibration Equipment I Gauge S/N I Cal. Due Date R1NARKS: I! DR Numb0.r (If req_rd) Reviewed For Completeness. DR prepared i f as-found setpoint out of required toler~:mce. Haint. Supervisor Date Fon*T2.!"C. *c0:.t;Jlet0.d de.to. sheet e.nd DR (If applic2ble) to Tech:1ical S:..:p2rintendcr t. II 1
,. Evalu~tcc! :Ln accordance with E}f-09-02.
" Tech. Supt. /Proj . Eng. D.'.lte Evaluation Rer:1~rk.s: (Include further action required inc:ll!cling ?'fa numbers):
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