ML19274D665
| ML19274D665 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/14/1979 |
| From: | Stallings C VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7902210255 | |
| Download: ML19274D665 (32) | |
Text
.
e VINGINIA Ei.Ec rHIC AND POWEH COMI%NY HIcn n ow n. VI HOINI A 23261 February 14, 1979 Mr. Harold R. Denton, Director Serial No. 332A/111776 Of fice of Nuclear Reactor Regulation LQA/DWSJr:esh Attn:
Mr. A. Schwencer, Chief Operating Reactors Branch No. 1 Docket Nos.
50-280 Division of Operating Reactors30-281 U. S. Nuclear Regulatory Commission License Nos. DPR-32 Washington, DC 20555 DPR-37
Dear Mr. Denton:
AMENDMENT TO OPERATING LICENSES SURRY POWER STATION UNIT NOS. I AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE NO. 66 Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company hereby requests an am;ndment, in the form of changes to the Technical Speci-fications, to Operating License DPR-32 and DPR-37 for the Surry Power Station, Un i t Nos. I and 2, The proposed changeu are enclosed and have been designated as Cha.1ge No. 66, in accordance with Robert Reid's letter dated November 17,1976 and in accordance with the regulations contained in paragraph (g) of 50.55a, you will find an Attachment B which contains revised technical snecifications to meet the new Inser ' ice inspection and testing requirements for nuclear power plant components.
Jurther, Attachment A describes each of the changes on a page by page listing.
The enclosed changes have been reviewed and approved by the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Commi ttee.
It has been determined that this request does not involve an unreviewed safety question.
We have evaluated this request in accordance with the criteria speci-fled in 10 CFR 170.22. The amendment involves a single safety issue and the Staff should be able to determine that this request does not involve a signifi-cant hazards consideration. Accordingly, this request has been determined to be Class lil for Unit 1.
The duplicate revision for Unit 2 has been designated Class 1.
A check in the amount of $4,400 is attached in payment of the amendment fee.
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7 9 0 2 210 A55 g8
viuoisia necruic 4xu rom ru cour4xy To Mr. Harold R. Denton 2
Currently we plan to submit our program descriptions for inservice inspection and testing by May 15, 1979 Issuance of these specifications are required by August 22, 1979 for Unit No. I and January a, 1980 for Unit No. 2.
Very truly yours, 7
. h. h/
C. M. Stallings Vice President-Power Supply and Production Operations Attachments A.
Description and Evaluation of Changes B.
Change No. 66 C.
Check in amount of $4,400.00 cc:
Mr. James P. O'Reilly, Di rector Office of Inspection and Enforcement Region iI
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COMMONWEALTH T V IRGINI A
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CITY OF RICHMOND
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Before me, a Notary Public, in and for the City and Common-wealth aforesaid, today personally appeared C. M. stallings, whn being duly sworn, made oath and said (1) that he is Vice Presiden- 'r.:
Supply and Production Operations, of the Virginia Electric
.ower Company, (2) that he is duly authorized to execute and file the fore-going Amendment in behalf of that Company, and (3) that the statements in the Amendment are true to the best of his knowledge and belief.
yhandandnotarialsealthis/YNayof Given under g
gy Camatsba Exp'res I/. arch 5,1973 My Commission expires -
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ATTACHMENT A DESCRIPTION OF CHANGES Changes are being proposed in order to conform the Technical Specifications to the more restrictive requirements of the ASME Code Section XI which results from. e new NRC regulation 10 CFR 50.55a(g).
In order to avoid any conflict with the ASME Code Section XI, a standard reference approach is being adopted in accordance with NRC instructions. This will avoid future changes to the Technical Specifications resulting from ASME Code Section XI changes.
In the future only the descriptions of the inservice inspection and pump and valves testing programs need to be updated as code changes are made.
In accordance with 10 CFR 50.55a(g) and NRC instructions, three types of technical specification changes are being proposed. The three types of changes are:
(1) changes which are more restrictive than present technical specifica-tions in order to meet the code pursuant to 10 CFR 50 55a(g)(1); (2) changes which are less restrictive than present technical specifications but meet the code and are proposed pursuant to 10 CFR 50.55a(g)(6)(II); (3) changes which are less restrictive than the code and therefore an exception must be obtained pursuant to 10 CFR 50.55a(g)(6)(i).
The specifics of each type of change and evaluation of each change is as follows:
1.
Changes More Restrictive Than_Present Technical Specifications The following are proposed changes necessary in order to conform Technical Specifications to an updated inservice inspection and testing program. See Attachment B for modified specification wording:
Page TS 4.0-1 (Specification 4.0.1) " Surveillance Requirements."
Specification modified into an outline form in order that it may be referenced.
- Page TS 4.0-1 (Specification 4.0.2) " Surveillance Time Interval."
Specification modified into an outilne form in order that it may be referenced.
Page TS 4.0-1 (Specification 4.0.3) " Inservice Testing." Specifica-tion added to incorporate standard reference to ASME Section XI re-quirements for inservice testing of pumps and valves.
In accordance with NRC recommendations, a reference approach has been adoptea in order to alleviate future Technical Specification changes.
Page TS 4.2-1 (Specification 4.2, applicability, objective, specifica-tions 4.2 A, B, C, D) "ASME Class 1, 2, and 3 canponent inspections and miscellaneous inspections." Specifications modified to incorporate
,tandard reference to ASME Section XI requirements for Inservice irspec-tion of Class 1, 2, and 3 components.
In accordance with NRC recommenda-tions, a reference approach has been adopted in order to alleviate future technical specification changes.
In addition, table 4.2-1 has been re-vised to include only the requirements for sensitized stainless steel piping. Miscellaneous requirements are included as Table 4.2-2.
Further-more, items 7.2 and 7 3 of the present table 4.2-1 have been deleted since they are no longer applicable.
Page 4.2-2 (Specification 4.2 Bases) "ASME Code Class 1, 2, and 3 components and miscellaneous inspections." Bases modified to explain that specifica-tions are founded on the code of Federal Regulations which requires adherence to the ASME Code Section XI.
In addition, miscellaneous requirements are included.
Page 4.3-1 (Specification 4.3) Applicability, objective, specifications 4.3 A, B, C, D) "ASME Code Class 1, 2, and 3 system pressure tests."
Specifica-tion modified to incorporate standard reference to ASME Section XI require-
, ments for inservice inspection of Class 1, 2, and 3 components.
In accordance with NRC recommendations, a reference approach has been adopted in order to alleviate future technical specification changes.
Augmented leakags test pressure requirements have been restated.
Page TS 4.3-2 (Specification 4.3 Bases) "ASME Code Class 1, 2, and 3 system pressure tests." Bases modified to explain that specification is founded on the code of Federal Regulations.
In addition augmented requirements are restated.
Page TS 4.5-1 (Specification 4.5. A.1) " Containment Spray Pumps."
Specification modified to incorporate standard reference to Specifica-tion 4.0 3 Pump must be tested to more restrictive code requirements.
Page TS 4.5-2 (Specification 4.5.B.2) " containment Spray Pumps."
Speci-fication mocified to incorporate standard reference to Specification 4.0 3 Pump must be tested to more restrictive code requirements.
Page TS 4.5-3 (Specification 4.5.B.3) " Weight Loaded Check Valve." Speci-fication modified to incorporate standard reference to Specification 4.0.3 Check valves must be tested to more restrictive code requirements.
Page TS 4.5-3 (Specification 4.5 B.4) " Spray Systems Motor Operated valves."
Specification modified to incorporate standard reference to Specification 4.0 3 Mo'.or operated valve must be tested to more restrictive code exe rc i s '.ng requi remen t.
Page TS 4.8-2 (Specification 4.8.8) " Auxiliary Feedwater System Acceptance Criteria." Specification modified to incorporate standard reference to Specificction 4.0 3 Pump and valves must be tested to more restrictive code requi rements.
. Page TS 4.11-2 (Specification 4.11.B (pumps)l) " Low Head Safety injection Pumps." Specification modified to incorporate standard references to Specification 4.0.3 Pumps must be tested to more restrictive code require-ments.
Page TS 4.11-2 (Specification 4.11.B (pump)2 & 3) " Acceptable levels of performance" and " Routine Operation of Charging Pumps." Specification deleted since 4.11.B(pump)1 as modified specifies testing requirements for Low Head Safety injection Pumps and Charging Pumps.
Page TS 4.11-3 (Specification 4.ll.B (valves)3) Specification modified to Spec. 4.0.3 Class 2 valves must be tested in accordance with code require-ments.
2.
Changes Less Restrictive Than Present Technical Specifications The following are proposed changes which are less restrictive than present technical specification, but meet the code. See Attachment B for modified specification wording:
Page TS 4.1-9 (Specification table 4.1-2A Item 4) " Pressurizer Safety Valves."
Specification modified to incorporate standard reference to Specification 4.0 3 since the updated program requires less frequent testing of safety valves.
Page TS 4.1-9 (Specification table 4.1-2A Item 5) " Main Steam Safety valves."
Specification modified to incorporate standard reference to Specification 4.0 3 since the updated program requires less frequent testing of safety valves.
Page TS 4.1-9 (Specification table 4.1-2A Item 13) " Main Steam Line Trip Valves." Specification modified to incorporate standard reference to Specification 4.0.3 since the updated program requires less frequent testing.
% Page TS 4.2-3 (Specification table 4.2-1) " Sensitized stainless steel piping." Inservice requirements for sensitized stainless steel piping has been revised. This will provide equivalent survelliance to that presently required for Surry, see the Initial Decision (pp. 6 and 7)
May 25, 1972.
Page TS 4.5-2 (Specification 4.5. A.5) " Spray System Motor Operated valves."
Specification modified to incorporate standard reference to Specification 4.0 3 since the updated program requires less frequent testing.
Page TS 4.7-1 (Specification 4.7.A and B) " Main Steam Line Trip Valves."
Specifications modified to incorporate standard reference to Specification 4.0.3 since the updated program requires less frequent testing.
Page TS 4.8-1 (Specification 4.8. A.1) " Auxiliary Feedwater Motor Driven Pumps."
Specification modified to incorporate standard reference to Soecifi-cation 4.0 3 since the updated program requires a test of less duration.
Page TS 4.8-1 (Specification 4.8.A.3) " Auxiliary Feedwater Pump Discharge Valves." Specification modified to incorporate standard reference to Spec.
h.0 3 since the updated program requires less frequent testing.
Page TS 4.11-3 (Specification 4.11.8 (valves)l) "RWST Outlest Valves."
Specificatlon modified to incorporate standard reference to Specification 4.0 3 since the updated program requires less frequent valve testing.
3 Requested Exceptions to the Code The following are proposed exception of the code. Approval of these exceptions would leave the teciinical specification as is.
See Attachment B for present wording of specification:
. Page TS 4.1-9 (Specification table 4.1-2A Item 14) " Service Water Valves to Recir. Spray Heat Exchangers." Specification remains as is since veri-fication of isolation time, which is required by the code on a quarterly basis, would unnecessarily introduce service water into the recirculation spray heat exchangers. These heat exchangers are normally maintained in a dry condition.
Page TS 4.5-1 (Specification 4.5. A.2) "Inside Recirculatica Spray Pumps."
Specification remains as is (except for frequency) since the containment sump is the suction reservoir for the inside recirc spray pumps and always remains in a dry condition. Containment inside recirculation spray pumps are designed to be run dry. Testing frequency decreased to once per quarter is consistent with manufacturer's recommendations.
Page TS 4.5-1 (Specification 4.5. A.3) "Outside Reci r. Spray Pumps."
Specification remat is as is since testing at other then shutoff conditions is impractical.
Page TS 4.5-2 (Specification 4.5. A.4) " Spray System Check Valves." Spect-fication remains as is since testing of check valves during normal operation is impractical and can possibly jeopardize containment Integrity.
Page TS 4.5-2 (Specification 4.5.B.1) "Inside Recirculation Spray Pump Acceptable Criteria." Specification remains as is since the containment sump is the suction reservoir for the inside containment recirculation spray pumps always remain in a dry condition.
Page TS 4.5-3 (Specification 4.5.B.7) "Outside Recir. Spray Pump."
Speci-fication remains as is since testing at other shutoff condition is imprac-tical.
Page TS 4.11-3 (Specification 4.ll.B (valves) 2) " Accumulator Check Valves."
Specification remains as is since testing accumulator check valves during
. normal operation is impractical and could possibly Jeopardize system integrity.
ATTACHMENT B TS-li SECTION TITLE PAGE 3 15 CONTAI NMENT VACUUM SYSTEM TS 3 15-1 3 16 EMERGENCY POWER SYSTEM TS 3 16-1 3 17 LOOP STOP VALVE OPERATION TS 3 17-1 3 18 MOVABLE INCORE INSTRUMENTATION TS 3 18-1 3.19 MAIN CONTROL ROOM VENTILATION SYSTEM TS 3 19-1 3.20 SHOCK SUPPRESSORS (SNUBBERS)
TS 3.20-1 3.21 FIRE DETECTION AND SUPPRESSION SYSTEM TS 3.21-1 4.0 SURVEILLANCE REO.UIREMENTS TS 4.0-1 4.1 OPERATIONAL SAFETY REVIEW TS 4.1-1 4.2 ASME CODE CLASS 1,2,53 COMPONENT AND MISCELLANEOUS INSPECTIONS TS 4.2-1 4.3 ASME CODE CLASS 1,2,53 SYSTEM PRESSURE TESTS TS 4.3-1 4.4 CONTAINMENT TESTS TS 4.4-1 4.5 SPRAY SYSTEMS TESTS TS 4.5-1 4.6 EMERGENCY POWER SYSTEM PERIODIC TESTING TS 4.6-1 4.7 MAIN STEAM LINE TRIP VALVES TS 4.7-1 4.8 AUXILIARY FEEDWATER SYSTEM TS 4.8-1 4.9 EFFLUENT SAMPLlNG AND RADIATION MONITORING SYSTEM TS 4.9-1 4.10 REACTIVITY AN0MAllES TS 4.10-1 4.11 SAFETY INJECTION SYSTEM TESTS TS 4.11-1 4.12 VENTILATION FILTER TESTS TS 4.12-1 4.13 NONRADl0 LOGICAL ENVIRONMENTAL MONITORING PROGRAM TS 4.13-1 4.14 TEMPERATURE LIMITATIONS ON CONDENSER COOLING WATER DISCHARGE TS 4.14-1 4.15 AUGMENTED INSERVICE PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT TS 4.15-1
TS 4.0-!
4.0 SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance requirements provide for testing, calibrating, or inspecting those systems or components which are required to assure that operation of the units or the station will be as prescribed in the preceding sections.
4.0.2 Specified time intervals may be adjusted plus or minus 25 percent to accomodate normal test schedules.
4.0.3 inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with Section XI, of the ASME Boiler and Pressure Vessel Code and applicable Addends as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(1).
References FSAR Section 12.9 inservice inspection FSAR Section 14.1 Operational Safety Review
TABLE 4.1-2A HINIMUM FREQUENCY FOR EQUIPMENT TESTS FSAR Section Description Test Frequency Reference 1.
Control Rod Assemblies Rod drop times of all full length Each refueling shutdown or 7
rods at hot and cold conditions.
af ter disassembly or main-tenance requiring the breech of the Reactor Coolant System integrity 2.
Control Rod Assemblies Partial movement of all rods Every two weeks 7
3 Refueling Water Chemi-cal Addition Tank Functional Each refueling shutdown 6
4.
Pressurizer Safety Valves Setpoint See Specification 4.0 3 4
5 Main Steam Safety Valves Setpoint See Specification 4.0.3 10 6.
Containment isolation Trip
- Functional Each refueling shutdc in 5
7 Refueling System Interlocks
- Functional Prior to refueling 9.12 8.
Service Water System
- Functional Each refueling shutdown 99 9
Fire Protection Pump and Power Supply Functional Monthly 9.10 10.
Primary System Leakage
- Evaluate Daily 4
11.
Diesel Fuel Supply
- Fuel inventory 5 days / week 8.5 d
12.
Boric Acid Piping e-Heat Tracing Circuits
- 0perational Monthly 9.1 13 Main Steam Line Trip Isolation Time See Specification 4.0.3 10 l
14.
Service Water System Valves in Line Sup-plying Recirculation Spray lleat Exchangers Functional Each refueling 9.9 15.
Control Room Ventilation System
- Ability to maintain positive pressure for I hour using a
Page Coi,s i nued TABLE 4.1-2A MINIMUM FREQUENCY FOR EQUIPMENT TESTS FSAR Section Description Test Frequency Reference 15 Control Room Ventilation volume of air equivalent Each refueling Interval System to or less than that stored (approx. every 12-18 nos.)
9.13 in the bottled air supply
- See Specification 4.1.D U
T 5
TS 4.2-1 4.2 ASME CODE CLASS 1, 2, AND 3 COMPONENT AND MISCELLANEOUS INSPECTIONS Applicability Applies to inservice Inspection of ASME Code Class 1, 2, and 3 com-ponents and miscellaneous inspections.
Obj ect ives To provide assurance of the continued integrity of the ASME Code Class 1, 2, 3 and miscellaneous components.
Specifications A.
Inservice inspection of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as re-quired by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(I).
B.
Augmented inservice inspection of sensitized stainless steel piping shall be performeo in accordance with Table 4.2-1.
C.
The reactor vesse! !rradiation surveillance capsules shall be removed and examined, in accordance with Table 4.2-2 for mis-cellaneous inspections. The results of these examinations shall be used to update Figure 3.1-1 as rc-alred.
TS 4.2-2 BASIS The inspection programs for ASME Code Class 1, 2, and 3 components ensure that the structural Integrity of these components will be maintained at an accepta-ble level throughout the life of the plant.
Since each unit was designed and partially constructed without the benefit of Section XI of the ASME Boiler and Pressure Vessel Code, full compliance may not be feasible or practical.
How-ever, the inspection program was developed by adopting, insofar as practical, the principles and intent embodied in the Code.
Sensitized stainless steel piping is subject to augmented inspection to assure additional confidence in piping integrity.
The reactor vessel Irradiation surveillance program is included to determine the increase in RT as a result of fast neutron irradiation. The reactor NDT coolant system heatup and cooldown curves will be adjusted as necessary as re-quired by TS3.1B to assure compliance with the minimum temperature requirement of Appendix G to 10 CFR 50.
TABLE 4.2-1 SENSITIZED STAINLESS STEEL PIPING EXAMINATION EXAMINATION EX" RENT OF AREAS METHODS EXAMINATION FREQUENCY REMARKS ASME Class I Visual and 25% of the circumferential Every 40 months For the required Circumferential and longi-volumetric welds, including one foot visual inspection, tudinal pipe welds cnd of any longitudinal weld the piping will be branch pipe connection on either side of the butt pressurized by the welds larger than 4 inches weld.
procedure defined in diameter.
in Table 4.1-3 of technical specifi-cation 4.1 concern-ing flushing of sensitized stainless steel piping.
ASME Class I Vis ual 100% of the welds Every 40 months Same as above Circumferential and longi-tudinal pipe welds and branch pipe connections welds 4 inches in diameter and smaller.
ASME Class 1 Visual and 25% of the circumferential Every 40 months Same as above Socket welds and pipe surface welds and 25% of the pipe branch connections branch connection welded welds 4 inches in dia-
- joints, meter and smaller.
Containment and.Recircu-Visual and Visual examination will At least 25% of t'..a lation Spray Piping surface include 100% of the piping.
examinations shall have been completed by the Surface examination will expiration of one-third include 6 patches (each of the inspection interval
_4 9 inches square) evenly and at least 50% shall have distributed around each been completed by the expira-spray ring.
tion of two-thirds of the in-7 spection interval. The remain-ing required examinations shall be completed by the end of the inspection interval.
TABLE 4.2-1 (cont.)
SENSITIZED STAINLESS STEEL PIPING EXAMINATION EXAMINATION EXENT OF AREAS MET 110DS
_ EXAMINATION FREQUENCY RDfARKS Remaining sensitized Visual and Visual examination will Every two years stainless steel piping surface include 100% of the piping Surface examination will include a strip one inch wide and one foot long lo-cated on each piping bend.
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TABLE 4.2-2 HISCELLANEOUS INSPECTIONS Required Required Extent of Examination Tentative inspec-Examination Examination Planned During First tion D'tring item No.
Areas Methods 5-Year Interval 10-Year interval Remarks I
Haterials Dosimetry
- Capsule I shall be Capsules shall be Capsule 4 Irradiation removed and examined removed and exam-shall be ex-at the first region ined after 10 years amined after replacement. Capsule 20 years.
2 shall be examined Capsules 5-8 after 5 years.
are extra cap-sules for ccm-plementary or duplicate test-ing.
- Pending NRC approval of proposed Tech Spec Change 74 application dated 12/15/78.
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TS 4.3-1 4.3 ASME CODE CLASS 1, 2, AND 3 SYSTEM PRESSURE TESTS App;icability Applies to requirements for ASME Code Class 1, 2, and 3 System Pres-sure Tests.
in this context, closed is defined as the state of sys-tem integrity which permits pressurization and subsequent normal operation after the system has been opened.
Objective To specify requirements for ASME Code Class 1, 2, and 3 System Pres-sure Tests following normal operation, modification, or repair. The pressure-temperature limits for Reactor Coolant System tests will be in accordance with Figure 3.1-1.
' Specification A.
Inservice inspection, which includes system pressure testing, of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boller and Pressure Vessel Code and applicable addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).
B.
Each time the Reactor Coolant System is closed, the system will be leak tested at a test pressure of not less than the nominal operating pressure +100 psi in conformance with NDT requiremeiits.
TS 4.3-2 BASIS System pressure testing is performed in order to insure integrity of the sys-tem.
For normal opening the integrity of the system, in terms of strength, is unchanged.
If, for example, the Reactor Coolant System does not leak at the nominal operating pressure plus 100 psi, it will be assumed leaktight for normal operation.
The testing is based on 10 CFR 50.55a ano performed pursuant to Section XI of the ASME Code for inservice inspection of Class 1, 2, and 3 components.
TS 4.5-1 4.5 SPRAY SYSTEMS TESTS Apolicability Applied to the testing of the Spray Systems.
Objective To verify that the Spray Systems will respond promptly and perform their design function, if required.
Specification A.
Test and Frequencies 1.*
The containment spray numps shall be tested pursuant to Specification 4.0.3 2.*
All Inside containment recirculation spray pumps shall be dry tested at least once per quarter.
3.*
The recirculation pray pumps outside the containment shall be flow-tested by determining the shutoff head of the pump once per month.
4.
The weight loaded check valves within the containment in the various subsystems shall be tested by pressurizing the pump discharge lines with air at least once each re-fueling period. Verification of seat.ing the check valves shall be accomplished by applying a vacuum upstream of the valves.
TS 4.5-2 5.*
All motor operated valves in the containment spray and recirculation spray flow path shall be tested pursuant to Specification 4.0 3 6.
The containment spray nozzles and containment recircula-tion spray nozzles shall be demonstrated operable at least once per five years coinciding with the closest re-fueling outage, by performing an air or smoke flow test and verifying each spray nozzle is unobstructed.
7.*
The spray nozzles in the refueling water storage tank shall be checked for proper functioning at least monthly.
- During periods of extended reactor shutdown the monthly testing requirement may be waived af ter the first month of shutdown provided the component is tested prior to reactor startup.
B.
Acceptance Criteria 1.
A dry-test of a recirculation spray pump shall be considered satisfactory if the motor and pump shaft rotates, starts on signal, and the ammeter readings for the motor are compcrable to the original dry test ammeter reedings.
2.
A flow-test of a containment spray pump shall be considered satisfactory pursuant to Specification 4.0 3 In addition, a check will be made to determine that no particulate mater *-
al from the refueling water storage tank clogs the test spray nozzles located in the refueling water storage tank.
~
TS 4.5-3 3
The test of each of the weight loaded check valves shall be considered satisfactory pursuant to Speci-fication 4.0.3 4.
A test of a motor operated valve shall be considered satisfactory pursuant to Specification 4.0.3 5
The test of the containment spray nozzles and recircula-tion spray nozzle shall be considered satisfactory if flow through each nozzle can be verified.
6.
The test of the spray nozzles in the refueling water storage tank shall be considered satisfactory if the monitored flow rate to the nozzles, when compared to the previously established flow rate obtained wi th the new nozzles, indicates no appreciable reduction in flow rate.
7 The test of the outside recirculation spray pump shall be considered satisfactory if the pump starts and the measured shutoff head of the pump is that specified on the head curve within instrument accuracy.
TS 4.5-4 BASIS The flow testing of each containment spray pump is performed by opening the normally closed valve in the containment spray pump recirculation line returning water to the refueling water storage tank.
The containment spray pump is operated and a quantity of water recirculated to the refueling water storage tank. The discharge to the tank is divided into two fractions, one for the major portion of the recirculation flow and the other to pass a small quantity of water through test nozzles which are identical with those used in the containment spray headers. The purpose of the recirculation throught the test nozzles is to assure that there is no particulate material in the refueling water storage tank small enough to pass through pump suction strainers and large enough to clog spray nozzles.
Due to the physical arrangement of the recirculation spray pumps inside the containment, it is impractical to flow-test them periodically. These pumps are cable of being operated dry for 60 sec. and it can be determined that the pump shafts are turning by rotation sensors which indicate in the Main Control Room. Motor current is indicated on an ammeter in the Control Room, and will be compared with readings recorded during preoperational tests to ascertain that no degradation of pump operation has occurred. The recirculation spray pumps outside the containment have the capability of being dry-run and flow-tested. The flow-test of an outside recirculation spray pump is performed by closing the suction line valve and the isolation valve between the purp discharge and the containment penetration. This allows the pump casing to be filled with water and the pump to recirculate water through a test line from the pump dis-charge to the pump casing.
4.5-5 With system flush conducted to remove particulate matter prior to the installa-tion of spray nozzles and with corrosion resistant nozzles and piping, it is not considered credible that a significant number of nozzles would plug during the life of the unit to reduce the effectiveness of the subsystems; therefore, provisions to air test the noz'zles every five years coinciding with the closest refueling outage is sufficient to indicate that plugging of the nozzles has not occurred.
The spray nozzles in the refueling water storage tank provide means to ensure that there is no particulate matter in the refueling water storage tank and the Containment Spray Subsystems which could plug o-cause deterioration of the spray nozzles. The nozzles in the tank are identical to those used on the con-tainment spray headers.
The monthly flow test of the containment spray pumps and recirculation to the refueling water storage will indicate any plugging of the nozzles by a reduction of flow through the nozzles.
R(.?e ren ces FSAR Section 6 3.1 Containment Spray Pumps FSAR Section 6.3.1 Recirculation Spray Pumps
TS 4.7-1 4.7 MAIN STEAM LINE TRIP VALVES Applicability Applies to periodic testing of the main steam line trip valves.
Objective To verify the ability of the main steam line trip valves to close upon signal.
Specification A.
Tests and Frequencies 1.
Each main steam trip valve shall be tested pursuant to Speci fication 4.0.3 B.
Acceptance Criteria 1.
When tested pursuant to Specification 4.0 3, a full closure test of main steam trip valves shall be considered satisfac-tory if the valve closed fully in 5 sec. or less.
2.
A partial closure inservic r of a main steam trip valve shall be considered satisfactor y !f the valve can be stroked at least 3 degrees from its fu.1 open position.
TS 4.7-2 BASIS The main steam trip valves serve to limit an excessive Reactor Coolant System cooldown rate and resultant reactivity insertion following a main steam line break accident. A closure time of 5 sec was selected since this is the closure time assumed in the safety evaluation. The inservice testing of partial valve stroke of 3 degrees is sufficient to verify the freedom of the valve disc to function as required. A limit switch in the test circuit prevents the valve disc from entering the flow stream and slam-ming the valve shut during inservice testing.
TS 4.8-1 4.8 AUXILIARY FEEDWATER SYSTEM Applicability Applies to periodic testing requirements of the Auxiliary Feedwater System.
Objective To verify the operability of the auxiliary steam generator feedwater pumps and their ability to respond properly when required.
Specification A.
Tests and Frequency 1.*
Each motor driven auxiliary steam generator feedwater pump shall be tested pursuant to Specification
'..u.
2.*
The turbine driven auxiliary steam generator feedwater pump shall be flow tested for at least 15 minutes on a monthly basis to demonstrate its operability.
3.*
The auxiliary steam generator feedwater pump discharge valves shall be exercised pursuant to Specification 4.0.3
- During periods of extended reactor shutdown the monthly testing requirement may be waived provided the component is tested prior to startup.
TS 4.8-2 F,
Acceptance Cri teria These tests shall be considered satisfactory pursuant to Specifi-cation 4.0.3 and the turbine driven auxiliary feedwater pumps operated properly.
BASIS On a monthly basis the auxiliary steam generator feedwater pumps will be tested to demonstrate their operability by recirculation to the 110,000 Gallon Conden-sate Storage Tank.
The capacity of any one of the three feedwater pumps in conjunction with the water inventory of the steam generators is capable of maintaining the plant in a safe condition and sufficient to cool the unit down.
Proper functioning of the steam turbine admission valve and the ability of the feedwater pumps to start will demonstrate the integrity of the system.
Verification of correct operation can be made both from instrumentation within the Main Control Room and direct visual observation of the pumps.
References FSAR Section 10.3 1 Main Steam System FSAR Section 10.3.2 Auxiliary Steam System
TS 4.11-1 4.11 SAFETY INJECTION SYSTEM TESTS Applicability Applies to operational testing of the Safety injection System.
Obj ect ive To verify that the Safety injection System will respond promptly and perform its design functions, if required.
Specification A.
Safety injection System 1.
System tests shall be performed during reactor shutdowns for refueling. The test stia11 be performed in accordance with the following procedure:
With the Reactor Coolant System pressure less than or equal 0
to 450 psig and temperature less than or equal to 350 F, a test safety injection signal will be applied to initiate operation of the system. The charging and low head safety injection pumps are immobilized for this test.
2.
The test will be considered satisfactory if control board indi-cation and/or visual observations indicate that all the appro-priate components have received the safety injection signal in
TS 4.11-2 the proper sequence. That is, the appropriate pump breakers shall have opened and closed, and all valves, required to establish a safety injection flow path to the Reactor Coolant System and to isolate other systems from this flow path, shall have completed their stroke.
B.
Component Tests Pumps 1.
The low head safety injection pumps and charging pumps shall be tested pursuant to Specification 4.0.3 During periods of extended reactor shutdown the monthly testing requirement may be waived provided the component is tested prior to reactor startup.
Valves 1.
The refueling water storage tank outlet valves shall be tested pursuant to Specification 4.0.3 2.
The accumulator check valves shall be checked for operaSility during each refueling shutdown.
3 All vai,es required to operate on a safety injection signal shall be tested pursuant to Specification 4.0.3
pr TS 4.11-3 i
BASIS Co.aplete system tests cannot be performed when the reactor is operating be-cause a safety injection signal causes containment isolation. The method of assuring operability of these systems is therefore to combine systems tests to be performed during refueling shutdowns, with more frequent component tests, which can be performed during reactor operation.
The systems tests demonstrate proper automatic operation of the Safety injection System. With the pumps blocked from starting, a test signal is applied to initiate automatic action and verification is made that the componente receive the safety injection signal in the proper sequence. The test demonctrates the operation of the valves, pump circuit breakers, and automatic circuitry.
During reactor operation, the Instrumentation which is depended on to initiate safety injection is checked periodically and the initiating circuits are tested in accordance with Specification 4.1.
In addition, the active components (pump and valves) are to be tested pursuant to Specification 4.0.3 to check the opera-tion of the starting circuits and to verify that the pumps are in satisfactory running order. Other systems that are also important to the emergency cooling function are the accumulators and the Containment Depressurization System. The accumulators are a passive safeguard.
In accordance with Specification 4.1 the water volume and pressure in the accumulators are checked periodically.
Reference FSAR Section 6.2 Safety injection System