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| 'that certain safety-related pumps and' valves meet the~ requirements of SectionLX.11 of the.American Society of Mechanical Engineers (ASME) Boiler and-Pressurei j Vessel Code 1 (hereafter "the Code"). In order lto meet the; requirements of thisk i | | 'that certain safety-related pumps and' valves meet the~ requirements of SectionLX.11 of the.American Society of Mechanical Engineers (ASME) Boiler and-Pressurei j Vessel Code 1 (hereafter "the Code"). In order lto meet the; requirements of thisk i |
| regulation, the Tennetsee Valley Authority.(TVA) has1 submitted to NRC:its firstJ ten-year Inservice . Testing -(IST) program lon pumps 'and: valves.for the .Sequoyahl Nuclear Plant, Units 1 and 2:in its letter dated March 3, 1982c The ISTl T program for Sequoyah was-revised in later submittals dated' November ~4, 1982, April 16, 1984, August 16, 1985. June 6,(1986, November 17, 1986, DecemberJ12,- | | regulation, the Tennetsee Valley Authority.(TVA) has1 submitted to NRC:its firstJ ten-year Inservice . Testing -(IST) program lon pumps 'and: valves.for the .Sequoyahl Nuclear Plant, Units 1 and 2:in its {{letter dated|date=March 3, 1982|text=letter dated March 3, 1982}}c The ISTl T program for Sequoyah was-revised in later submittals dated' November ~4, 1982, April 16, 1984, August 16, 1985. June 6,(1986, November 17, 1986, DecemberJ12,- |
| 1986, July 2,1987, and Au9ust 14',?1987, iIn these11etters, TVA requestedt relief from certain Code'Section XI requirements' for specific: pumps and valves-in the Sequoyah Units 1 and 2:IST program. :The staff:1ssued a:SafetyJEvaluationi (SE) concerning the Sequoyah.IST program on April. Sh1985L This SE addressed the relief requests-in the three'submittals. dated March 3',L1982 to Aprile16; 1984. , | | 1986, July 2,1987, and Au9ust 14',?1987, iIn these11etters, TVA requestedt relief from certain Code'Section XI requirements' for specific: pumps and valves-in the Sequoyah Units 1 and 2:IST program. :The staff:1ssued a:SafetyJEvaluationi (SE) concerning the Sequoyah.IST program on April. Sh1985L This SE addressed the relief requests-in the three'submittals. dated March 3',L1982 to Aprile16; 1984. , |
| Subsequently,TVAproposedfurtherprogramchangesinits.sixsubmittalsdsted; August 16', 1985 to August 14 1987. The staff was requested.to first' review the: | | Subsequently,TVAproposedfurtherprogramchangesinits.sixsubmittalsdsted; August 16', 1985 to August 14 1987. The staff was requested.to first' review the: |
Safety Evaluation Supporting 21 Relief Requests,W/Four Exceptions,From ASME Boiler & Pressure Vessel Code,Section Ix,Re Inservice Testing Program of Pumps & ValvesML20236F284 |
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Site: |
Sequoyah |
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Issue date: |
10/23/1987 |
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From: |
NRC OFFICE OF SPECIAL PROJECTS |
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Shared Package |
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ML20236F256 |
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References |
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NUDOCS 8711020081 |
Download: ML20236F284 (3) |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20138D2581997-04-28028 April 1997 Safety Evaluation Authorizing Licensee Proposed Alternative to Use 1989 Edition of ASME Boiler & Pressure Vessel Code, Section XI for Performance of Containment Repair & Replacement Activities Until 970909 ML20057F8441993-10-14014 October 1993 SER Granting Relief Giving Due Consideration to Burden Upon Licensee That Could Result If Requirements Imposed on Facility ML20057D5321993-09-28028 September 1993 SER Granting Licensee 921117 Relief Requests ISPT-2 & ISPT-3 Re Inservice Pressure Test Program ML20057D6351993-09-28028 September 1993 SER Granting Relief as Requested for Both ISPT-2 & ISPT-3 Per 10CFR50.55a(a)(3)(i) & 10CFR50.55a(g)(6)(i) ML20128K0221993-02-11011 February 1993 SE Accepting Util Justification for Break Exclusion of Main Steam Lines in Valve Vaults Provisionally Until End of Refueling Outages ML20128E9161993-01-0606 January 1993 SE Approving Request for Relief from ASME Requirements Re First 10-yr Interval ISI Plan ML20247K3321989-09-14014 September 1989 Safety Evaluation Accepting ATWS Mitigation Sys,Pending Tech Spec Issue Resolution ML20245E6951989-08-0303 August 1989 Safety Evaluation Supporting Inclusion of Alternate Repair Method to Detect microbiologically-induced Corrosion in Previously Granted Request for Relief from ASME Section XI Code Repair Requirements ML20247G8661989-07-21021 July 1989 Safety Evaluation Re Silicone Rubber Insulated Cables. Anaconda & Rockbestos Cables at Plant Environmentally Qualified for Intended Function at Plant & Use Acceptable for 40 Yrs ML20247B4891989-07-19019 July 1989 Safety Evaluation Supporting Util 890330 Request to Eliminate Dynamic Effects of Postulated Primary Loop Pipe Ruptures from Design Basis of Plant,Using leak-before- Break Technology as Permitted by Revised GDC 4 ML20246N0321989-07-11011 July 1989 Safety Evaluation Supporting Util Responses to Generic Ltr 83-28,Item 1.2, Post-Trip Review,Data & Info Capability ML20244D1771989-06-0909 June 1989 Safety Evaluation Re Generic Ltr 83-28,Items 2.1.1 & 2.1.2 NUREG-0612, Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley1989-05-26026 May 1989 Safety Evaluation Supporting Util Request to Delete Three Commitments in Response to NUREG-0612 Re Heavy Load Control on 5-ton Electric Monorail Hoist W/Integral Trolley & 4-ton Monorail Chain Hoist W/Geared Trolley ML20245A1301989-04-14014 April 1989 Safety Evaluation Re Shutdown Margin.Procedural,Hardware & Training Enhancements Implemented & Committed to by Util Will Provide Reasonable Assurance That Adequate Shutdown Margin Will Be Maintained at Plant ML20244D8821989-03-14014 March 1989 Safety Evaluation Supporting Procedural,Hardware & Training Enhancements Implemented & Committed to by Util to Provide Reasonable Assurance That Adequate Shutdown Margin Will Be Maintained at Plants ML20195J0891988-11-28028 November 1988 Safety Evaluation Accepting Program for Plant in Response to Items 4.2.1 & 4.2.2 of Generic Ltr 83-28 Re Reactor Trip Sys Reliability ML20205T1621988-11-0707 November 1988 Safety Evaluation Supporting Improvement Plan for Emergency Diesel Generators Transient Voltage Response ML20206G4531988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 15101, Floor Drains ML20206G3961988-11-0404 November 1988 SER Supporting Util Investigation of Employee Concerns as Described in Element Rept 308.03 ML20206G5341988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30114, Malfunction of Doors ML20206G4621988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 204.8(B), Communication & Interface Control ML20206G5291988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 301112, Sys 31 Not Operated Properly ML20206G5241988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30111, Valve Closure ML20206G5191988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30105, Questionable Design & Const Practices ML20206G5091988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23706, Gassing of Current Transformers ML20206G5021988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23504, Exposed HV Cable Routed W/O Raceway - Personnel Hazard ML20206G4571988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 15105-SQN, Flex Hose Connections ML20206G4971988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 23501, 480 Volt Power Receptacles Unsafe ML20206G4861988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 232.9(B), Freezing of Condensate Lines ML20206G4591988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 204.7(B), Vendor Documents Legibility & Dissemination Sys ML20206G4801988-11-0404 November 1988 SER Supporting Element Rept EN 232.2, Carbon Steel Vs Stainless Steel Drain Pipes ML20206G4721988-11-0404 November 1988 SER Supporting Employee Concern Element Rept 22912, Panel- to-Equipment Distances ML20206G4661988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 229.6(B), Lack of Valves in Sampling & Water Quality Sys ML20206G5431988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 30301, Difficulty in Obtaining Obsolete Equipment ML20206G6111988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31105, Alara ML20206G6161988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31106, Health Physics Facilities,Clothing & Protective Equipment ML20206G6211988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31204-SQN, Mgt & Personnel Issues ML20206G6321988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31208-SQN, Security at Plant Entrances ML20206G6371988-11-0404 November 1988 SER Supporting Employee Concern Element Rept OP 31201-SQN, Adequacy of Public Safety Svc (Pss) Officer Uniforms in Nuclear Plant Environ ML20206G4351988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 11101-SQN, Contact Between Dissimilar Metals ML20206G4381988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 11202-SQN, Craft-Designed Hangers as Related to Const ML20206G4081988-11-0404 November 1988 SER Supporting Employee Concern Element Rept Co 10307-SQN, Uncoated Welds as Related to Const ML20206G3661988-11-0404 November 1988 SER Supporting Employee Concern Element Rept EN 21002, Inadequate Environ Qualification of Electrical & Instrumentation Control 1999-09-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212J6311999-10-0101 October 1999 SER Accepting Request for Relief from ASME Boiler & Pressure Vessel Code,Section Xi,Requirements for Certain Inservice Insp at Plant,Unit 1 ML20217G3721999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Sequoyah Nuclear Plant.With ML20212F0831999-09-23023 September 1999 Safety Evaluation Granting Relief from Certain Weld Insp at Sequoyah Nuclear Plant,Units 1 & 2 Pursuant to 10CFR50.55a(a)(3)(ii) for Second 10-year ISI Interval ML20212F4761999-09-23023 September 1999 Safety Evaluation Supporting Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively ML20212C4761999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Sequoyah Nuclear Plant.With ML20210L4361999-08-0202 August 1999 Cycle 9 12-Month SG Insp Rept ML20216E3781999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20210L4451999-07-31031 July 1999 Unit-2 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20210G6631999-07-28028 July 1999 Cycle 9 90-Day ISI Summary Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209H3831999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Sequoyah Nuclear Plant.With ML20211F9031999-06-30030 June 1999 Cycle 9 Refueling Outage ML20196J8521999-06-28028 June 1999 Safety Evaluation Authorizing Proposed Alternative to Use Iqis for Radiography Examinations as Provided for in ASME Section III,1992 Edition with 1993 Addenda,Pursuant to 10CFR50.55a(a)(3)(i) ML20195K2951999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20206Q8951999-05-0505 May 1999 Rev 0 to L36 990415 802, COLR for Sequoyah Unit 2 Cycle 10 ML20206R5031999-04-30030 April 1999 Monthly Operating Repts for April 1999 for Sequoyah Units 1 & 2.With ML20205P9811999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20204C3111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20205B6631999-02-28028 February 1999 Underground Storage Tank (Ust) Permanent Closure Rept, Sequoyah Nuclear Plant Security Backup DG Ust Sys ML20203H7381999-02-18018 February 1999 Safety Evaluation of Topical Rept BAW-2328, Blended U Lead Test Assembly Design Rept. Rept Acceptable Subj to Listed Conditions ML20211A2021999-01-31031 January 1999 Non-proprietary TR WCAP-15129, Depth-Based SG Tube Repair Criteria for Axial PWSCC Dented TSP Intersections ML20198S7301998-12-31031 December 1998 Cycle 10 Voltage-Based Repair Criteria 90-Day Rept ML20199G3641998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20197J5621998-12-0303 December 1998 Unit 1 Cycle 9 90-Day ISI Summary Rept ML20197K1161998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20195F8061998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Sequoyah Nuclear Plant.With ML20154H6091998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Sequoyah Nuclear Plant,Units 1 & 2.With ML20154H6251998-09-17017 September 1998 Rev 0 to Sequoyah Nuclear Plant Unit 1 Cycle 10 Colr ML20153B0881998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Sequoyah Nuclear Plant.With ML20239A0631998-08-27027 August 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Sequoyah Nuclear Plant,Units 1 & 2 ML20236Y2091998-08-0707 August 1998 Safety Evaluation Accepting Relief Requests RP-03,RP-05, RP-07,RV-05 & RV-06 & Denying RV-07 & RV-08 ML20237B5221998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Snp ML20237A4411998-07-31031 July 1998 Blended Uranium Lead Test Assembly Design Rept ML20236P6441998-07-10010 July 1998 LER 98-S01-00:on 980610,failure of Safeguard Sys Occurred for Which Compensatory Measures Were Not Satisfied within Required Time Period.Caused by Inadequate Security Procedure.Licensee Revised Procedure MI-134 ML20236R0051998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Sequoyah Nuclear Plant ML20249A8981998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Sequoyah Nuclear Plant,Units 1 & 2 ML20247L5141998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Sequoyah Nuclear Plant ML20217K4471998-04-27027 April 1998 Safety Evaluation Supporting Requests for Relief 1-ISI-2 (Part 1),2-ISI-2 (Part 2),1-ISI-5,2-ISI-5,1-ISI-6,1-ISI-7, 2-ISI-7,ISPT-02,ISPT-04,ISPT-06,ISPT-07,ISPT-8,ISPT-01 & ISPT-05 ML20217E2221998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Sequoyah Nuclear Plant ML20248L2611998-02-28028 February 1998 Monthly Operating Repts for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2571998-01-31031 January 1998 Cycle 9 Voltage-Based Repair Criteria 90-Day Rept ML20202J7911998-01-31031 January 1998 Monthly Operating Repts for Jan 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199J2441998-01-29029 January 1998 Snp Unit 2 Cycle Refueling Outage Oct 1997 ML20199F8531998-01-13013 January 1998 ASME Section XI Inservice Insp Summary Rept for Snp Unit 2 Refueling Outage Cycle 8 ML20199A2931997-12-31031 December 1997 Revised Monthly Operating Rept for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20198M1481997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20197J1011997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Sequoyah Nuclear Plant,Units 1 & 2 ML20199C2951997-11-13013 November 1997 LER 97-S01-00:on 971017,vandalism of Electrical Cables Was Observed.Caused by Vandalism.Repaired Damaged Cables, Interviewed Personnel Having Potential for Being in Area at Time Damage Occurred & Walkdowns ML20199C7201997-10-31031 October 1997 Monthly Operating Repts for Oct 1997 for Sequoyah Nuclear Plant L-97-215, SG Secondary Side Loose Object Safety Evaluation1997-10-23023 October 1997 SG Secondary Side Loose Object Safety Evaluation 1999-09-30
[Table view] |
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. UNITED STATES NUCLEAR REGULATORY COMMISSION j
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0 SAFETY: EVALUATION BY-THE4 0FFICE OF'SPECIAL' PROJECTS. ,
]q
- RELATINGETORELIEF'FROMTHEASME'BOIi.ER'ANDLPRESSUREVESSELCODE, ,
LSECTION XI,-RULES FOR' INSERVICE INSPECTION OFI .
y.
NUCLEAR POWER PLANT COMPONENTS -' DIVISION I"t
, TENNESSEE VALLEY' AUTHORITY SEQUOYAH NUCLEAR PLANT,:UNITSL1 AND 2 q DOCKET N05.J 50-327 AND 50-328.
1.0 INTRODUCTION
q Section 50.55a', " Codes and. Standards", of 10 CFR Pa' r t?50 requires, in 'part.- '
~
'that certain safety-related pumps and' valves meet the~ requirements of SectionLX.11 of the.American Society of Mechanical Engineers (ASME) Boiler and-Pressurei j Vessel Code 1 (hereafter "the Code"). In order lto meet the; requirements of thisk i
regulation, the Tennetsee Valley Authority.(TVA) has1 submitted to NRC:its firstJ ten-year Inservice . Testing -(IST) program lon pumps 'and: valves.for the .Sequoyahl Nuclear Plant, Units 1 and 2:in its letter dated March 3, 1982c The ISTl T program for Sequoyah was-revised in later submittals dated' November ~4, 1982, April 16, 1984, August 16, 1985. June 6,(1986, November 17, 1986, DecemberJ12,-
1986, July 2,1987, and Au9ust 14',?1987, iIn these11etters, TVA requestedt relief from certain Code'Section XI requirements' for specific: pumps and valves-in the Sequoyah Units 1 and 2:IST program. :The staff:1ssued a:SafetyJEvaluationi (SE) concerning the Sequoyah.IST program on April. Sh1985L This SE addressed the relief requests-in the three'submittals. dated March 3',L1982 to Aprile16; 1984. ,
Subsequently,TVAproposedfurtherprogramchangesinits.sixsubmittalsdsted; August 16', 1985 to August 14 1987. The staff was requested.to first' review the:
priority items requested by TVA to support the Sequoyah Unit 2 restart. This
SE is, therefore, limited to 21 relief. requests!from the ASME- Code, Section1XI,: >
that have been identified by TVA as needingl resolution prior to restartLof. the:
Sequoyah plant. TVA has made other relief requests and proposed program.
revisions in addition to the 21 addressed herein, sand these are currently under; review'. These non-restart relief requests will be' addressed in a later.
evaluation.,
Regulation 10'CFR 50.55a(g)(6)(1) authorizes the. Commission to grait relikf fromi-these requirements upon making the necessary. findings; . This SE contains1NRC;
- staff findings with respect to granting or not granting reliefs submitted!asl ,
,part of the licensee's IST program. .
~ '
y 2.0 EVALUATION-L The staff'has reviewed.the 21 relief requests' considered to require resolution) j before the plant is restarted. The results 'of the: review are provided belowL ,
8711020081 8710236 ,
?
_pDR.-ADOCK 05000327-
, ?Dn
- a The NRC consultant, Oak Ridge National Laboratory, has reviewed the licensee's -
21 relief requests and prepared the attached Technical Evaluation Report (TER).
The staff has reviewed the evaluation and concurs in its bases and findings.
The granting of relief is based upon the fulfillment of any commitments nade by the licensee in its basis for each relief request and the alternate proposed '
testing.
Relief has been granted from the testing requirements which the staff has ;
determined to be impractical to perform, would not compromise the safety of the plant, and where testing if implemented, would result in undue hardship, and by determination that the relief requests were evaluated in accordance with 10 CFR 50.55a(g)(6)(1).
Of the 21 relief reouests reviewed the following were determined to be accept-able: i
- 1. Diesel Fuel Oil Transfer Pumps (pressure measurement).
- 2. Trending of leak rate and corrective action for containment isolation valves.
- 3. Corrective action for valves failing exercising tests, l
- 4. Testing of valves previously out of service.
- 5. Normal charging line check valve 62-543.
- 6. RCP seal injection check valves62-560 -561, -562, -563. !
- 7. RCS check valve 68-559 to pressurizer relief tank.
- 8. RV head vent valves FSV-68-396 and -397. .f
- 9. Post-accident sampling system valves FSV-250, -251 -287, -288, -307,
-309, -310, -317. -318 -319. -325, -341.
l
- 10. Maximum allowable stroke time for power-operated valves.
l 11. Parallel UHI and SIS check valves.
l
- 12. Containment pressure transmitter isolation valves FSV-30-134, and -135.
l 13. Testing of safety and relief valves,
- 14. Pump in-service test procedure.
- 15. Test equipment - accuracy and range.
- 16. 10-Minute Minimum Time Requirement.
- 17. Correlation Procedure Certification.
l The staff has determined that one relief request, the pressurizer auxiliary spray line check valve 62-661 and the power-operated auxiliary spray valve 62-84, does not fall within the scope defined in IVW-1100 of Section XI of the i I
Code and need not be included in the Sequoyah Nuclear Plant IST Program. -
The following relief requests have been judged not to contain adequate justi-fication for relief from Code requirements:
- 1. Diesel Fuel Oil Transfer Pumps (bearing temperature measurement).
- 2. Three-percent criteria.
- 3. Stabilization of Valve Body Temperature when testing at room ambient conditions.
The following are clarifications of the attached TER: (1) relief request 2, page 3, the Code permissible leakage rate is 5.2 times greater than the TVA I
9 4
permissible leakage rate for the containment isolation valves; (2) relief . ,
request 6,.page 8, the valve number 68-543 is a typographical error and_ sho'uld be 62-543 and the contractor's evaluation statement that "the. licensee's pro-posed testing meets the requirements of the Code" means that the. proposed testing .
meets the requirements.of IWV-3522 of the Code; (3). relief requests 9 ~and 10, pages 12 and 13, the contractor's statement.that the. licensee's proposal
" appears to meet the intent of IWV-3300" means the proposal meets the intent of IWV-3300; (4) relief request 12 . page 16, the "and. full stroke exercised" in the Code Requirement is a typographical error and should. read "or full <-
stroke exercised"; (5) relief request 12, page 16, the SIS /RHR accumulator primary. check valves cannot be full stroke exercised; and (6) relief' request 12, page 16, the 4 primary and 2 secondary UHI check valves' are part. stroked .
during~ each cold shutdown and the 4 primary UHI check valves are manually full.
stroked each refueling outage af ter the spool pieces are removed.
Based on the staff. review of the attached TER, regarding 21 relief requests for l the restart of Sequoyah Nuclear Plant Units 1 and 2, the staff concludes that ,
the licensee's requests for relief from certain-specific requirements of.
Section XI of the ASME Code are acceptable with the exceptions as noted above.
The licensee is required to comply with the IST program defined' above in . i accordance with the relief granted as discussed in the enclosed TER.
Review of the overall IST program is continuing. based upon the submitted l l information. Any additional program changes such as revisions or additional H l relief requests or deletion of any components from the IST program should be l
! submitted for staff review and should not be implemented prior to review and approval by the staff.
3.0 CONCLUSION
Based on the considerations discussed above, the staff concludes (1) that relief may be granted pursuant to paragraph 10 CFR 50.55a(g)(6)(1) based on our finding.
that certain requirements of Section XI of the ASME Boiler and Pressure Vessel Code are impractical, and (2) that granting relief where the Code requirements: !
are impractical is authorized by law and will not endanger life or property, or the common defense and security, and is otherwise in the public interest considering the burden that could result if they were imposed on-the facility.
ACKNOWLEDGEMENT Principal Contributor: J. Lombardo, J. Donohew Dated: October 23, 1987 t
l i
4
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