ML19345F859
| ML19345F859 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/13/1981 |
| From: | Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 084, 84, NUDOCS 8102190435 | |
| Download: ML19345F859 (38) | |
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YJBUINIA ELecrusc Ann Pownw CoxPAwy R xcuwoxx),VsBOINIA 20261 February 13, 1981 Mr. Harold R. Denton, Director Serial No. 084 Office of Nuclear Reactor Regulation N0/RMT:ms Attn: Mr. Robert A. Clark, Chief Docket No. 50-339 Operating Reactors Branch No. 3 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
Specification 4.0.5 of the Technical Specifications for North Anna Unit 2, requires ASME Code Class 1, 2 and 3 pumps and valves to be tested in accor-dance with Section XI of the ASME Boiler and Pressure Csde (1974 Edition with Addenda through the summer 1975) except where specific written relief has been granted by the Nuclear Regulatory Commission. North Anna Unit 2 was not, however, designed to meet the detailed inservice testing requirements of subsect ions IWP and IWV of ASME Code,Section XI. Therefore, pursuant to 10 CFR 50.55a, (g)(6)(i), we request the specific exceptions for the testing of pumps and valves as outlined in Attachments A and B.
On September 9-10, 1980 representatives from the Nuclear Regulatory Commission, EG&G and Virginia Electric and Power Company discussed the resubmittal of the Unit 2 IWV and IWP Programs for North Anna. The attached program incorporates all of the changes discussed and includes the following changes and additions.
i Changes:
l l 2-QS-11, 22/2-RS-20, 30 will be. exercised each refueling rather than each l cold shutdown and refueling. These valves are not accessible except during refueling outages.
2-RS-103, 113 will be ASME III Cat. , B/C rather than A/C. These valves are not subject to Type "C" testing by the North Anna Unit 2 Technical l Spe ci fications .
l CapegokE ; valves Are covered by Station Administrative Procedures, spscifically the Administrative Lock Log.
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Vinoasta EtzcTalC AMD Powra COMPANY TO Mr. Harold R. Denton Additions:
T V-IA-2 01 A, B - Ca t . A.
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2-IA-250 is a check valve in series with TV-IA-202A and B. This check valve is a Category A valve with TV-IA-202A, and TV-IA-202B will be a i Cat. B valve.
MOV-SW-215 A, B - Cat . B.
MOV-SW-102A, B - Cat. B.
I MO V-SW-106 A, B - Cat. B.
i 2-WT-437, 438, 4 39 - Cat. A.
2-WT-446, 447, 448 - Cat. A.
2-DA Cat. A, C.
i TV-DA-203 A - Cat . A.
T V-DA-203B - Ca t . B.
I Very truly yours, B. R. Sylvia Manager - Nuclear i Operations and Maintenance Attachments A. Requested Exceptions to the Inservice Testing Requirements I for Pumps as Set Forth In Subsection IWP to Section XI of the'ASME Code, 1974 Edition with Addenda through the summer of 1975, North Anna Unit 2.
1, B. Requested Exceptions to the Inservice Testing Requirements f for Valves as Set Forth In Subsection IWV to Section XI of l the ASME Code, 1974 Edition with Addenda through the summer of 1975, North Anna Unit 2.
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' ATTACHMENT A l
REQUESTED EXCEPTIONS TO THE INSERVICE TESTING REQUIREMENTS FOR PUMPS AS SET FORTH IN SUBSECTION IWP TO SECTION XI 0F THE ASME CODE
, 1974 EDITION WITH ADDENDA THROUGH THE SUMMER 1975 NORTH ANNA UNIT 2 1
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ATTACHMENT A.0 PAGEI 0F 4 t.
SYSTEM PROPER MARK RELIEF PUMP NAME CLASS RESISTANCE AP LUBE NUMBER, REQUESTED Pi Q V Tb REMARKS F - FIXED LEVEL OR V - VARIABLE ;
PRESSURE 2-CC-P-1A Component Cooling 3 V Yes M Rel. Rel. M M A Exception 1 Pump 2-CC-P-1B ' Component Cooling 3 V Yes M Rel. Rel. M M A Exception 1 Pun.p i
2-CH-P-1A Charging Pump 2 Note 1,2 Yes Rel. Rel. M M M A Exception 2 2-CH-P-1B Charging Pump 2 Note 1,2 Yes Rel. Rel, f4 M M A Exception 2 2-CH-P-lC Charging Pump 2 Note 1,2 Yes Rel. Rel. M M M A Exception 2 1-CH-P-2C Boric Acid Trans- 2 F Yes Rel. Rel. 10te 1 Rel. Rel. Rel. Exception 3 fer Pump a
1-CH-P-20 Boric Acid Trans- 2 F Yes Rel. Rel. 10te 1 Rel. Rel. Rel. Exception 3 fer Pump 2-CW-P-2A Screenwash Pump 3 F Yes Rel. Rel. late 1 M Rel. Note 3 ' Exception 4 (Circulating *
- Water)
ATTACHMENT A.0 PAGE 2 0F 4 SYSTEM PROPER PUMP NAME CLASS RESISTANCE Pj LUBE NM R. R QUESTED AP Q V Tb REMARKS F - FIXED LEVEL OF V - VARIABLE PRESSURE 1-FC-P-1B Spent Fuel Pit Pump 3 F Yes M M Note M M A NA
- 1, 4 2-FW-P-2 . Turbine Driven 3 F Yes M M Note M M A NA Auxiliary Feed Pump *
- 1 2-FW-P-3A Motor Driven 3 , F Yes M M Note M M A NA Auxiliary Feed Pump *
- 1 2-FW-P-3B Motor Driven 3 F Yes M M Note M M A NA Auxiliary Feed Pump *
- 1 2-QS-P-1A Quench Spray Pump 3 F Yes M M Note M M A NA
- 1 2-QS-P-1B Quench Spray Pump 3 F Yes M M Note M M A 1A 1
2-RH-P-1A Residual Heat 2 F Yes ----- -----
Relief ----- --------- ---
Exception 5 '
Removal Pump * , **
2-RH-P-1B Residual Heat 2 F Yes ----------
Rejjef -------------------- Exception 5 Removal Pump
ATTACHMENT A.0 PAGE 3 0F 4 SYSTEM 'P'0PER MARK RELIEF PUMP NAME CLASS RESISTANCE AP LUBE REQUESTED Pi Q V Tb REMARKS NUMBER. F - FIXED LEVEL 0F V - VARIABLE PRESSURE 2-RS-P-1A Inside Recircula- 2 V Yes ------------
lelief ------------- Note Exception 6 tion Spray Pump 3 2-RS-P-1B ,
Inside Recircula- 2 V Yes ------------
2elief------ ------- Note Exception 6 tion Spray Pump 3 2-RS-P-2A Jutside Recircula- 2 F Yes ------------
lelief- - - - - - ------- Note Exception 7 tion Spray Pump 3 2-RS-P-2B Outside Recircula- 2 F Yes ------ ------
Relief----- --------
Note Exception 7 tion Spray Pump 3 2-SI-P-1A Low Head Safety 2 F Yes Rel. Rel. Note M Rel. Note Exception 8 Injection Pump *
- 1 3 2-SI-P-1B Low Head Safety 2 F Yes Rel. Rel. Note M Rel. Note Exception 8 Injection Pump *
- 1 3 2-SW-P-1A Service Water Pump 3 V Yes Rel. Rel. Rel . M Rel. Note Exception 9 3
2-SW-P-1B Service Water Pump 3 V Yes Rel. Rel. Rel . M Rel. Note Exception 9
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ATTACHMENT A.0 PAGE 4 0F 4 SYSTEM PROPER PUMP NAME CLASS RESISTANCE Pj AP LUBE N R, F - FIXED R U TED Q V Tb REMARKS LEVEL OF V - VARIABLE PRESSURE 2-SW-P-2 Screenwash Pump 3 F Yes Rel, Rel. Note M Rel. Note Exception 10 (Service Water) 1 3 2-SW-P Auxiliary Service 3 V Yes Rel Rel. Rel . M Rel. Note Exception 4 Water' Pump *
- 3 2-SW-P-5 Radiation Monitor- 3 F Yes -------
Relief ------------- ------
Exception 11 ing Sample Pump 2-SW-P-6 Radiation Monitor- 3 F Yes -------
Relief------- - - - - - - - - ------ Exception 11 ing Sample Pump 2-SW-P-7 Radiation Monitor- 3 F Yes ------- ------
Relief------ -------- ------
Exception 11 ing Sample Pump 2-SW-P-8 Radiation Monitor- 3 F Yes ------- ------
Relief l ------------- ------
Exception 11 ing Sample Pump 2-RS-P-3A Casing Cooling 3 F Yes M M Note M Rel. A Exception 12 '
Pump 1 2-RS-P-3B Casing Cooling 3 F Yes M M Note M Rel. A Exception 12 Pump *
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Attachment A.1 Page 1 of 3 EXCEPTIONS An exception is required to IWP-4210. Gage lines have not been provided with a suitable means to assure or determine the presence or absence of liquid when the presence or absence could produce a difference of more than 0.25% in the indicated value of the measured pressure.
Reference values and subsequent test values will all be taken with the gage lines as designed. Therefore, any error would be common to all values recorded and not affect the evaluation of the data.
- An exception is required to IWP-4110. Instrumentation included under this exception is only 1 4% accurate.
- 1. The accuracy of flow instrumentation at normal operating flows is about i 8%. This accuracy does not lend itself to satisfying the require-ments of Table IWP-2100-2 where the acceptable range is + 2% - 6%. In addition, varying flow rates interfere with normal plant operation since flows have been balanced to meet heat load requirements. Therefore, the AP and Q for each of these pumps will be recorded but not compared to reference values for head curve verification. Additionally, motor current will be recorded for comparison purposes.
- 2. Suction pressure instrumentation is not installed or required. These pumps are capable of producing greater than 2400 psig discharge pressure, while the suction pressure would nominally be 15 to 20 psig. The Volume Control Tank pressure will be recorded using Control Room indication to establish initial conditions for testing. This indication is about 4%
accurate.
- 3. Monitoring di:; charge pressure monthly is considered sufficient since these pumps provide the driving force to deliver boric acid to the charging pump suction and operator observation of boration and chemical analysis of boron concentration will indicate whether desired results have been achieved.
The Boric Acid Tanks serve as the head for these pumps. Tank level will be observed from the Control Room to establish initial conditions for testing. This indication is about 4% accurate. The pump is totally encased in insulation making Tb, V and Lubricant level or pressure impossible to measure or observe.
- 4. This pump takes s'uction from Lake Anna. The reservoir has a minimum level required by Technical Specifications. This indication, which is about 4% accurate, will be observed from the Control Room to establish initial conditions for testipg. Proper lubricant pressure or level cannot be observed since the bearings are in the main flow path.
Attachment A.1 Page 2 of 3
- 5. In accordance with Technical Specification 4.7.9.1, measured quantities will be obtained at least every 18 months. These pumps are not Engineered Safety Features pumps. Operability during extended use can be determined by monitoring reactor coolant system temperature. Due to location of Pi instrumentation, meaningful data can only be obtained with the pump in operation.
- 6. These pumps are run dry to verify operational readiness; therefore Pi AP, Q and Proper Lubricant Level or Pressure cannot be measured. Each pump is equipped with a sensor to detect pump rotation. In addition, a vibration alarm associated with each pump will alert Control Room personnel to excessive pump vibration.
- 7. These pumps will be run dry or wet to verify operational readiness.
Each will be observed to verify rotation. At least once per 18 months, each will be tested on its recirculation path when flow and discharge pressure will be observed. A vibration alarm associated with each pump will alert Control Room personnel to excessive pump vibration. Due to pump design, it is not possible to measure a suction pressure. Proper lubricant level or pressure is not required since bearings are in the main flow path.
- 8. These pumps take suction from the RWST for pump performance testing.
This tank has a minimum level required by Technical Specifications, which will be observed from the Control Room. This indication is about 4%
accurate. Proper lubricant level or pressure cannot be observed since bearings are in the main flow path.
- 9. The accuracy of flow instrumentation at normal operating flows is about + 8%. This accuracy does not lend itself to satisfying the require-ments of Table IWP-2100-2 where the acceptable range is + 2% - 6%. In addition, varying flow rates interfere with normal plant operation since flows have been balanced to meet heat load requirements. Therefore, the discharge pressure and Q for each pump will be recorded but not compared to reference values for head curve verification. These pumps take suction from the Service Water Reservoir, which has a minimum level required by Technical Specifications. This level indication, which is about 4%
accurate, will be observed from the Control Room to establish initial conditions for testing. Proper lubricant level or pressure cannot be observed since bearings are in the main flow path. Motor current will be recorded for comparison purposes.
, 10. This pump takes suction from the Service Water Reservoir, which has a minimum required level by Technical Specifications. This level indication, i' which is about 4% accurate, will be observed from the Control Room to establish initial co'nditions for testings. Proper lubricant level or .
pressure cannot be observed since bearings are in the main flow path. 1
Attachment A.1 Page 3 of 3
- 11. The flow paths of these pumps are normally dry. At least once per 18 months, each pump will be automatically started in conjunction with a test signal for Containment Depressurization Actuation. These pumps will be run dry monthly.
- 12. The bearing lubrication for these pumps is grease instead of oil.
The grease will be checked annually.
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Attachment A.2 Page 1 of 1
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a NOTES i
- 1. In a fixed resistance system, it is required to measure AP or Q, ,
! not both (IWP Table 3100-1).
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- 2. When these pumps are operated on recirculation flow, the system is i fixed resistance. When they are tested as the operating pump,
, the system is variable resistance.
t i 3. Reference is made to IWP 4310, which establishes exception to Tb for bearings within the main flow path.
1 4. Pump will be tested only when there is water in the spent fuel pit.
- 5. Symbols and abbreviations from Attachment A.0 are as follows:
M - Monthly A - Annually Rel - Relief Requested i
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ATTACHMENT B REQUESTED EXCEPTIONS TO THE INSERVICE TESTING REQUIREMENTS FOR VALVES AS SET FORTH IN SUBSECTION IWV TO SECTION XI 0F THE ASME CODE 1974 EDITION WITH ADDENDA THROUGH SUMMER 1975 NORTH ANNA UNIT 2 9
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Attachment B.0 Page 1 of 2 STATEMENT OF PARTICULARS A review of ASME Class 1, 2, 3 valves has been completed for the North Anna Unit 2 Systems. Attachment B.1 provides a taL 'lation of the valves that are subject to the testing requirements of ASME Boiler and Pressure Vessel Code,1974 edition, subsection IWV with addenda through summer 1975. The table identifies the valves to be tested, valve code classes, and valve category per IWV-2000. Relief from the testing requirements of ASME XI is requested when they are determined to be impractical. Specific information regarding the Code requirement determined to be impractical and alternate testing programs are noted in Attachment B.2.
Leak testing of containment isolation valves shall be performed in accordance with Appendix J of 10CFR50 in lieu of ASME XI subsection IWV.
There are no testable Category D valves in North Anna Unit 2 Systems. All Category E valves shall be tested in accordance with IWV-3700.
i Any inspection requirements identified as impractical during the course of the inspection period will be noted and included in the inspection program at the time of the next revision.
When one valve in a redundant safety related system is found inoperable during testing, non-redundant valves in the remaining train will not be cycled as procedures require but will be cycled after the first inoperable valve in the system is returned to service.
This valve testing program addresses all valves determined to be
- essential in the mitigation of the consequences of an accident. The program has been reviewed to assure that testing the valves at the intervals specified will not place the plant in an unsafe condition.
Where practical, valves will be cycled at 3 month test intervals.
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Attachment B.0 Page 2 of 2 System Abbreviation System Name BD Steam Generator Blowdown CC Component Cooling CVCS Chemical and Volume Control System CV Containment Vacuum DA Containment Sump Drains DG Primary Drains FW Feedwater HV Habitability and Ventilation IA Instrument Air LM Leakage Monitoring MS Main Steam QS Quench Spray RC Reactor Coolant RH Residual Heat Removal RM Radiation Monitoring RS Recirculation Spray SI Safety Injection SS Sampling SW Service Water VG Vent Gas WT Steam Generator Wet Layup O
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ATTACHMENT B.1
! PAGE 1 OF 19 SYSTEM: BD, CC ASME ASME TEST FREEQUENCY
- RELIEF REMARKS PT FUNCTION III XI REQUESTED I VALVE CAT- CAT
- EXERCISE LEAKAGE Containment Steam II B No Every 3 Each Refuel- NA TV-BD-200 ing AcB,C,D,E,F Generator Blowdown Isolation Months
! Valves CCW Throttling Valve of RHR III B No Every 3 NA NA MOV-CC-200A Months M0V-CC-200B .
Heat Exchangers i
Yes Cold Each Note 1 i TV-CC-200A,B,C Containment Air Recirculation - A Refueling 205A,B,C Coils Isolation Valves Shutdown A Yes Cold Each Note 2 TV-CC-201A, B RCP's Thermal Barrier III Refueling Containment Isolation Valves Shutdown ,
RCP's, UBIO, LBLO and Stator A Yes Cold Each Note 2 TV-CC-202A, B III Refueling Cooler Containment Isolation Shutdown
- Co D,E,F Valves TV-CC-203A, B RHR HX Return Line III A Na Every 3 Each NA Months Refueling 1 Containment Isolation Valves RCP's UBLO, LBLO and Stator A Yes Cold Each Note 2 TV-CC-204A, B, C III Refueling
! Cooler Containment Iso'.a.' ion Shutdown Valves C No Note 3 NA Note 3 RV-CC-228A, B RHR HX Relief Valve III
ATTACHMENT B.1 PAGE 2 0F 19 SYSTEM: CC, CVCS ASME ASME TEST FREEQUENCY RELIEF ^
FilNCTION III XI REQUESTED VALVE CAT. CAT. EXERCISE LEAKAGE 2-CC-10, 27 CC Pump Discharge III C No Every 3 NA NA Check Valves Months 2-CC-37 Unit 1/ Unit 2 Common Header III C No Each Re- NA NA .
Check Valve fueling 2-CC-78, 115, 152 RCP's UBLO, LBLO and Stator III AC Yes Each Each Note 4 Cooler Inlet Check Valves Refueling Refueling 2-CC-194, 199 RHR HX Inlet Check Valves III AC Yes Each E,1ch Note 4 Refueling Refueling s
Containment Recirc Air Cooler II AC Yes Each Each Note 4 2-CC-276 Isolation Check Valves Refueling Refueling 2-CC-289 2-CC-302 Aux RCS Charging Control Valve -
A Yes Every Each Note 27 FCV-2160 Refueling Refueling HCV-2200A, B, C Hand Control Letdown Valves II A No Every 3 Each NA Months Refueling No Every 3 Each NA HCV-2142 Letdown from RHR II A Months Refueling
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ATIAClit-iffiT B.1 PAGE 4 Of 19 SYSTEM: CVCS ASME ASME TEST FREEQUEf4CY REMARKS PT FUNCTION Ill XI R STED CAT. CAT. EXERCISE LEArAGE VALVE Emergency Boration Valve 11 B Yes Cold fiA Note 7 MOV-2350 Shutdown 1
Charging Pump Recirculation !! B Yes Each flA Note 24 MOV-2373
- Ileader Isolation Valve Refueling Reactor Coolant Pump Seal Wtr. 11 A Yes Each Each flote 8 MOV-2380 2381 Return Containment Isolation Refueling Refueling Valves RV-2203 Letdown lleader Relief Valve 11 AC No Note 3 Each Note 3 Refueling RV-2209 Letdown lleader Relief Valve 11 C No Note 3 NA Note 3 RV-2257 Volume Control Tank Relief 11 C No Note 3 NA Note 3 Valve TV-2204 Letdown lleader Containment !! A Yes Each Each flote 9 Isclation Valve Refueling Refueling l-C11-118, 113 Boric Acid Transfer Pump 11 C No Every 3 NA NA Discharge Check Valve Months
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ATTACHMENT B.1 i' PAGE 6 0F 19 1
SYSTEM: DA, DG, FW ASME ASME TEST FREEQUENCY RELIEF REMARKS PT FUNCTION III XI REQUESTED VALVE CAT. CAT. EXERCISE LEAKAGE 4
TV-DA-203A Post Accident Sample System -
A No Every 3 Each 1A Return Line Isolation Valve f1onths Refueling Post Accident Sample System - B No Every 3 NA NA TV-DA-203B -
Return Line Trip Valve Months 2-DA-7, 9 Primary Drain Transfer Line II AE Yes NA Each Note 30 Isolation Valve Refueling 4
Post Accident Sample System A,C Yes Each Each Note 28 2-DA-49 4
Return Line Check Valve Refueling Refueling TV-DG-200A, B Primary Drains Transfer -
A No Every 3 Each NA Pump Containment Isolation Months Refueling Trip Valves Auxiliary Feedwater Pump III B Yes Each NA Note 10 HCV-FW-200C Admission Valve to Steam Refueling Generator Auxiliary Feedwater Pump III B Yes Each NA Note 10 MOV-FW-200B, D Admission Valves to Steam Refueling Generators B Yes Every 3 NA Note 31 PCV-FW-259A, B AFW Control Valve III Months
ATTACHMENT 8.1 PAGE 7 0F 19 SYSTEM: FW,HV,IA ASME ASME TEST FREEQUENCY III XI ^
FUNCTION CAT. CAT.
RfQUESTED VALVE EXERCISE IIAKAGE RV-FW-200 Turbine Auxiliary Feedwater III C No Note 3 NA Note 3 Pump Discharge Relief Valve 2-FW-62, 94, Main Feedwater Check Valve II C No Each NA Note 11 126 .
at Penetration Refueling 2-FW-70, 102 Auxiliary Feedwater Header II C No Every 3 NA Note 12 134 Check Valves at Main Feedwater Months Header 2-FW-150, 156, Auxiliary Feedwater Pumps III C No Every 3 NA Note 12 167, 172, Discharge and Recirculation Months 185, 192 Check Valves 4 2-FW-95, 129, Auxiliary Feedwater Header III C No Every 3 NA Note 12 279 Check Valves Months MOV-HV-200A, B, Containment Purge and Exhaust -
A Yes Cold Each Note 17 C, D Isolation Valves Shutdown Refueling MOV-Hi-201, 202 TV-IA-2GlA, B Containment Instrument Air II A No Every 3 Each NA Supply Months Refueling TV-IA-202A Containment Instrument Air II A No Every 3 Each NA 2-IA-250 Return Months Refueling
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ATTACilMENT B.1 1
PAGE 10 0F 19 SYSTEM: RC, RM, RS ASME ASME TEST FREEQUENCY FUNCTION III XI ^
VALVE CAT. CAT.
RfQUETED EXERCISE LEAKAGE TV-RM-200A, B, Containment Radiation -
A No Every 3 Each NA C, D Monitoring Isolation Trip Months Refueling Valvos MOV-RS-2'00A, B . Casing Cooling Pump Discharge II A No Every 3 Each NA 201A, B Valves Months Refueling M0V-RS-255A, B Outside Recirculation Spray II B Yes Each NA Note 10 Pump Suction Valves Refueling M0V-RS-256A, B Outside Recirculation Spray II B Yes Each NA Note 10 Pump Discharge Valves Refueling 2-RS-20, 30 Outside Recirculation Spray II AC Yes Each Each Note 14 Pump Discharge and Containment Refueling Refueling Isolation Check Valves 2-RS-103, 118 Casing Cooling Pump Discharge II BC Yes Each NA Note 15 Check Valves to Outside Refueling .
Recirculation Pumps 2-RC-162 Per Relief Valve PG Water I AC Yes Each Each Note 28 Supply, Containment Isolation Refueling Refueling Check Valve l
SV-2551A, B, C Pressurizer Safety Valves I C No Note 3 NA Note 3 l
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ATTACliMENT B.1 PAGE 11 0F 16 SYSTEM: RC, Ril, SI ASME ASME TEST FREEQUENCY FUNCTION III XI "^
R U TED VALVE CAT. CAT. LEAKAGE EXERCISE 2-RC-143, 145 Containment Isolation Valves I AE Yes NA Each Note 30 for Pressurizer Pressure Refueling Dead Weight Tester HCV-2758 RilR llX flow Control Valve II B No Every 3 NA NA Months FCV-2605 RilR liX Bypass Control Valve II B No Every 3 NA NA Months MOV-2700 RHR System Isolation Valves I A Yes Cold Each Note 16 2701 Shutdown Refueling 2720A, B 3 RV-2721A, B Ri1R System Relief Valves II C No Note 3 NA Note 3 2-Ril-7, 15 RilR Pump Discharge Check Valves II C No Cold NA Note 16 Shutdown 2-Ril-37, 38 RiiR Containmen Isolation II SE Yes NA Each Note 30
! Valves Refueling i
llCV-2936 Accumulator Tank Purge Control II ; Yes Cold Each Note 36 Valve Shutdown Refueling
ATTACHMENT B.1 PAGE 12 0F 19 SYSTEM: si ASME ASME RELIEF TEST FREEQUENCY XI REMARKS PT FUNCTION III REQUESTED VALVE CAT. CAT. LEAKAGE EXERCISE MOV-2860A, B Low Head Safety Injection Pump II B No Every 3 NA NA Suction From Containment Sump Months M0V-2862A, B .
Low Head Safety Injection Pump II B No Every 3 NA NA Suction From the Refueling Months Water Storage Tank MOV-2863A Low Head Safety Injection to II B No Every 3 NA NA Charging Pump Suction Months Low Head Safety Injection to II B Yes Cold NA Note 5 MOV-2863B Charging Pump Suction Shutdown MOV-2864A, B LHSI Pump Cold Leg Discharge II B Yes Cold NA Note 10 Stop Valves Shutdown MOV-2865A, B, C Accumulator Outlet Valves II B Yes . Cold NA Note 19 Shutdown MOV-2867A, B Boron Injection Tank Inlet II B No Every 3 NA NA Valves Months MOV-2867C, D Boron Injection Tank Outlet II A No Every 3 Each NA Valves Months Refueling
ATTACHMENT B.1 PAGE 13 0F 19 SYSTEM: SI ASME ASMF TEST FREEQUENCY RELIEF REMARKS PT FUNCTION III an REQUESTED VALVE CAT. CAT.
MOV-2836 High Head Safety Injection Off II AE Yes Cold Each Note 18 MOV-2869A, B Charging Header Shutdown Refueling MOV-28855,B,C,, LHSI Pump Recirc. Stop Valves II B No Every 3 NA NA D Months MOV-2890A, B Low Head Safety Injection to II AE Yes Cold Each Note 20 Refueling Hot Legs Shutdown MOV-2890C, D Low Head Safety Injection II A Yes Cold Each Note 20
- to Cold Legs Shutdown Refueling Low Head Safety Injection Pump II C No Note 3 NA Note 3 RV-2845A, B, C Discharge Relief Valves Boron Injection Tank Relief II C No Note 3 NA Note 3 RV-285'iB Valve ;.
A No Every 3 Each NA TV-2842 Accumulator Test Line Contain- -
Months Refueling 2859 ment Isolation Trip Valves TV-SI-200 . Accumulator Nitorgen Purge Con- -
A No Every 3 Each NA ment Isolation Trip Valve Months Refueling
ATTACHMENT B.1 PAGE 14 0F 19 SYSTEM: SI ASME ASME TEST FREEQUENCY FUNCTION III XI "^
CAT.
R QUE ED VALVE CAT. EXERCISE LEAKAGE TV-SI-201 Accumulator to Waste Gas System -
A No Every 3 Each NA Containment Isolation Valves Months Refueling TV-2884A, B, C Boron Injection Tank Recirc. II B No Every 3 NA NA Trip Valves Months 2-SI-1, 21 Low Head Safety Inject',on Pump II C Yes Each NA Note 21 Check Valves From Containment Refueling Sump 2-51-9, 32 Low Head Safety Injection Pump II C Yes Each NA Note 35 Discharge Check Valves Refueling 2-SI-18 Refueling Water Storage Tank II C Yes Cold NA Note 7 To Charging Pump Suction Check Shutdown Valve 2-SI-19 Low Head Safety Injection Pump II C Yes Each NA Note 35 Check Valse From Refueling Refueling Water Storage Tank 2-SI-6, 29 Low Head Safety Injection Pump II C No Every 3 NA NA ,
Seal Water Supply Check Valve Months 2-51-12, 35 Low Head Safety Injection Pump II C No Every 3 NA NA Recirculation Check Valves Months
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- ATTACHMENT B.1 PAGE 15 0F 19
! SYSTEM: SI ASME ASME TEST FREEQUENCY FUNCTION III XI "^
CAT. CAT. R QUE ED i VALVE EXERCISE LEAKAGE 2-SI-47 Accumulator Make Up Manual II AE Ves NA Each Note 30 Isolation Valve Refueling 2-SI-70 . Boron Injection Tank Recircu- II C a No Every 3 NA NA
.lation Check Valve -
Months 2-SI-85, 93, 107, High Head Safety Injectica AC Yes Each Each Note 22 119 Cold Legs Containment Iso., Refueling Refueling Check Valves 2-51-90, 98, 104 High Head Safety Injection to I C Yes Each NA Note 22 Cold Legs Refueling 2
2-SI-91, 105, 99 Low Head Safety Injection to I AC Yes Each Each Note 23 Cold Legs Containment Isolation Refueling Refueling Check Valves 2-SI-92, 100, 106 Cold Leg Safety Injection I AC Yes Each Each Note 22 Admission Check Valves Refueling Refueling 2-SI-113, 118 lot Leg Safety Injection I C Yes Each NA Note 22 ,
125 idmission Check Valves Refueling 2-SI-112, 117, Low Head Safety Injection to I C Yes Each NA Note 23
- 124 Hot Legs Refueling
ATTACHMENT B.1 -
PAGE 16 0F 19 SYSTEM: SI, SS ASME ASME TEST FREEQUENCY FUNCTION III XI "^
CAT. R QUE TED VALVE CAT. EXERCISE LEAKAGE 2-51-126, 128 Low Head Safety Injection to II AC Yes Each Each Note 23 Hot Legs Containment Isolation Refueling Refueling Check Valves 2-SI-136, 132 Accumulator Makeup and Nitrogen II AC Yes Each Each Note 28 Supply Check Valves Refueling Refueling 2-SI-151, 153, Accumulator Discharge Check I AC Yes Each Each Note 25 168, 170, Valves Refueling Refueling 185, 187 RV-2858A, B, C Accumulator Relief Valves I C No Note 3 NA Note 3 TV-SS-200A, B Pressurizer Liquid Space Sample I A No Every 3 Each NA Line Containment Isolation Months Refueling Valves TV-SS-201A, B Pressurizer Vapor Space Sample I A No Every 3 Each NA Line Containment Isolation Months Refueling Valves TV-SS-202A, B Primary Coolant Cold Leg I A No Every 3 Each NA Sample Line Containment Isola- Months Refueling i
tion TV-SS-203 RHR System Sample Line II A No Every 3 Each NA TV-SS-207, A, b Containment Isolation Months Refueling
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ATTACHMENT B.1 PAGE 17 0F 19 1
SYSTEM: SS, SW ASME ASME TEST FREEQUENCY RELIEF REMARKS PT
- FUNCTION III XI REQUESTED CAT- CAT- EXERCISE LEAKAGE VALVE A No Every 3 Each NA 4 TV-SS-204A, B Pressurizer Relief Tank Gas -
Months Refueling i Space Sample Line Containment Isolation Primary Coolant Hot Leg Sample I A No Every 3 Each NA TV-SS-206A, B Refueling l Months 2
Line Containment Isolation Valves i
Steam Generator Sample Line II A No Every 3 Each NA 4 TV-SS-212A, B Refueling Months Containment Isolation Valves Yes Each NA Note 26 MOV-SW-201A,B,C,D Recirculation Spray HX III B i 9 MOV-SW-205A,B C,0 Isolation Valves MOV-SW-100A, B Service Water to Spray Array B No Every 3 NA NA Stop Valves Months MOV-SW-200A, B Auxiliary Service Water Dump III B No Every 3 NA NA MOV-SW-ll5A, B Discharge Stop Valves Months MOV-SW-215A, B MOV-SW-217 l
Unit 1 Recirc. Spray Heat B No Every 3 NA NA MOV-SW-102A, B Exchangers Cross Lonnect Valves Months MOV-SW-106A, B MOV-SW-202A, B Jnit 2 Recirc. Spray Heat B No Every 3 NA NA MOV-SW-206A, B Exchangers Cross Connect Valves Months
ATTACHMENT BI .
PAGE 18 0F 19 SYSTEM: SW ASME ASME TEST FREEQUENCY RELIEF REMARKS PT FUNCTION III XI REQUESTED VALVE CAT. CAT. EXERCISE LEAKAGE MOV-SW-203A,B,C,0 Recirculation Spray HX III A Yes Each Each Note 10 MOV-SW-204A,B,C,0 Containment Isolation Valves Refueling Refueling MOV-SW-208A, B Component Cooling HX Isolation III B No Every 3 NA NA
. Valves Months RV-SW-200A,B,C,D Recirculation Spray HX Relief III C No Note 3 NA Note 3 Valves RV-SW-201A, B Component Cooling HX Relief III C No Note 3 NA Note 3 Valves 2-SW-24 Auxiliary Service Water Pump III C No Every 3 NA NA Discharge Check Valve Months 2-SW-68, 70 Service Water to Recirculation III C Yes Each NA Note 26 Spray HX Check Valves Refueling 2-SW-74, 84, 94, Recirculation Spray HX Inlet III AC Yes Each Each Note 26 104 Containment Isolation Check Refueling Refueling Valves a
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Attachment B.2 Page 1 of 5 NOTES
- 1. Closing of these valves during I;wer operations would seriously impair the heat removal capabilfly of the containment ventilation system. These valves are vital for continued power operations.
As an alternative, they will be cycled each cold shutdown.
- 2. Component cooling water flow to the reactor coolant pumps is required at all times the pumps are in operation. Failure of one of these valves in a closed position during cycling would result in a loss of the cooling flow to the pump. Power operated valves in these systems will be cycled at each cold shutdown and refueling when the reactor coolant pumps are secured. Verification of check valves operation to the open position will be performed each time coolant flow is reestablished after each refueling.
- 3. The frequency and quantity of relief valves subject to test at each
.efueling outage will be in accordance with IWV-3500. RV-2203 will be exercised in accorda. ice with the frequency in l'AV-3500.
- 4. These check valves renain in a normally open position with component cooling flow. The only method for verifying these valves closed is during the refueling octage leak rate test.
- 5. Exercising this valve during power operation would require the charg-ing pump suctions to be aligned with the refueling water storage tank. This would cause a sudden increase in RCS boron inventory. It will be exercised during cold shutdown when the RCS is borated to shutdown conditions.
- 6. Failure of these valves in a closed position during exercising would cause a loss of charging flow and could result in an inability to maintain reactor coolant inventory. These valves will be exercised when the charging system is not in use during cold shutdown and refueling outages.
- 7. Exercising this valve during operation could cause a sudden increase in RCS boron inventory. It shall be exercised at cold shutdown when the RCS is already borated to shutdown conditions.
- 8. To protect pump seals, flow to them is required at all times during power operation. Exercising of these valves will be performed during cold shutdown and refueling outages when the risk of equip-ment damage is* eliminated by securing the pumps.
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Attachment B.2 Page 2 of 5
- 9. This valve cannot be exercised when the charging and letdown systems are in operation due to the high risk of overpressurization of the i RCS. It will be exercised at cold shutdown and refueling outages when the charging and letdown systems are secured.
- 10. These valves are in the position required to fulfill their function.
Exercising this valve will not improve its operational readiness.
Exercising this valve may actually decrease system reliability if the valve fails in a nonconservative position. As an alternate, it will be exercised at cold shutdown and refueling outages.
- 11. Closure of mainsteam or feedwater valves during normal operations would result in turbine and reactor trips. These valves are closed during the process of shutdown and reopened during plant start-up.
Operation of these valves will be verified when entering or leaving cold shutdown.
- 12. 2-FW-70, 2-FW-156 and 2-FW-279 cannot be exercised during cold shutdown, because steam is not available to operate the turbine driven auxiliary feedwater pump.
- 13. Closure of these valves during power operation will result in a Reactor Trip. As an alternative, they will be cycled each cold shutdown, but not more than once every 92 days.
- 14. It is not possible to verify that these normally closed check valves open without initiation of spray through the upper containment header or by visual observation inside the containment. These valves shall be exercised during refueling outages as per the technical i specification requirements for weight loaded check valves.
- 15. It is impractical to exercise this check valve during power operation per IWV-3520. Opening the test valve would break containment vacuum.
The check valves shall be exercised at refueling outages.
- 16. Operation of RHR System Valves during power operations would subject the RHR System to full RCS pressure. Valves in the RHR System will be exercised each time the RHR System is put into operation during the cooldown and shutdown of the reactor coolant system. These valves will be leak tested in accordance with technical specifications.
- 17. Opening their valves during power operation would break containment vacuum and violate containment integrity. Their valves shall be exercised each ' cold shutdown, but not more than once every 92 hours0.00106 days <br />0.0256 hours <br />1.521164e-4 weeks <br />3.5006e-5 months <br />.
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. , 1 Attachment B.2 Page 3 of 5
- 18. These normally closed valves are directly attached to the charging pump discharge header. During operation or cold shutdown the charging system must be in operation. If these valves were opened during these periods, uncontrolled flow to the reactor coolant system may cause overpressurization. As an alternate, these valves shall be cycled at refueling outages and at cold shutdown when the charging pumps can be secured.
- 19. These normally opened valves are in the required position for an accident and are rcquired by Technical Specifications to remain open during power operations. They are closed in the normal process of shutdown to cold conditions and reopened during subsequent heat up.
- 20. These valves are in their required safety position with power to their operators removed during power operations. As an alternative, they will be cycled every cold shutdown, but not more than once per 92 days.
- 21. These normally closed check valves cannot be exercised during plant operation or cold shutdown. No connections exist downstream of the check valve to input flow or pressure which could promote movement of the disc away from the seat. A test connection is required between the isolation valve and the check valves but cannot be installed.
The isolation valve and check valve are butt welded together with no spool piece between them to provide a place for the test connection.
As an alternate test, the check valve bonnet shall be removed at refueling outages and the disc shall be exercised mechanically to verify free movement without binding.
- 22. The only way to verify that these normally closed check valves open is by initiating flow, using the charging pumps, into the reactor coolant system hot and cold legs. If charging flow was directed to the reactor coolant system in this manner it could cause overpressurization during cold shutdown or provide a loss in charging flow-control during operation. As an alternate, these check valves shall be exercised open during refueling outages.
- 23. The only way to verify that these normally closed check valves can open is by initiating flow, using the low head safety injection pumps, into the reactor coolant system hot and cold legs. During operation or cold shutdown, reactor coolant system pressure will be higher than the low head pump discharge pressure precluding flow into the vessel., As an alternate, these valves shall be exercised open at refueling outages.
24 This valve cannot be exercised without possible damage to the charging pumps.' It will be exercised with the charging pumps secured at, cold shutdown and refueling outages.
- O Attachment B.2 Page 4 of 5
- 25. To exercise this normally closed check valve would require the simulation of a loss of coolant accident, i.e. low RCS pressure. The valve shall be verified operable by initiating accumulator injection to the RCS with the vessel head removed during each refueling outage.
2-SI-170 and 2-51-187 will be exercised when the RHR System is in service during cold shutdown.
- 26. A commitment has been made to the ACRS prohibiting the introduction of service water into the Recirc. Spray Heat Exchangers without subsequent drying by a compressed air purge through the heat exchanger.
Exercising this valve will be accomplished at refueling outages when service water flow will be sent through the heat exchangers and air drying may be acccmplished.
- 27. Valves FCV-2160 and 2-CH-332 cannot be exercised during power operation or cold shutdown. FCV-2160 is normally closed and its accident position is closed (containment isolation function). The only method for verifying 2-CH-332 closed is during the refueling leak rate test.
- 28. Tiiese valves cannot be exercised during power operation or cold shutdown. The only method a /ailable to verify that these valves close is during the refuelf rg leak rate test.
- 29. TV-CV-200 is normally closed and its accident position is closed.
The valve will be exercised during refueling outages when establish-ing containment vacuum.
- 30. These are manual valves and will not be exercised because they are in their accident position (closed).
- 31. PCV-FW-259A, B will be exercised quarterly but will not be timed.
Stroke time is not important because these are modulating valves.
l l 32. These valves will be tested during power operation. These valves cannot be tested during cold shutdown or refueling because steam is not available to run the turbine driven auxiliary feedwater-pump.
- 33. This is the governor valve for the steam driven auxiliary feed pump. This valve is normally open and will be exercised but not timed every 18 months during the overspeed trip test.
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Attachment B.2 Page 5 of 5 34, 2-MS-19, 58 and 98 are located in a high temperature area that would be hazardous to enter during power operation. These valves will be exercised closed during cold shutdown and refueling outages.
- 35. These valves cannot be exercised during power operation because the discharge pressure of the low head S.I. pumps cannot overcome RCS pressure. These valves will be exercised during refueling outages and the reactor vessel head is removed to provide enough volume to accomodate the large flow rate. 2-51-19 will be partially stroked during the monthly pump test.
- 36. HCV-2936 is in its safety position and will be exercised during cold shutdown and refueling outages.
- 37. These are manual valves and they are in their intended safety position (closed). They will be exercised during refueling when the wet layup system is placed in operation.
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