Mechanical Engineering Branch Sser Re Inservice Testing of Pumps & Valves.Program for Pumps & Valves AcceptableML20133Q023 |
Person / Time |
---|
Site: |
Comanche Peak |
---|
Issue date: |
08/06/1985 |
---|
From: |
NRC |
---|
To: |
|
---|
Shared Package |
---|
ML20133Q021 |
List: |
---|
References |
---|
NUDOCS 8508140578 |
Download: ML20133Q023 (4) |
|
|
---|
Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20210D8321999-07-23023 July 1999 Safety Evaluation Accepting Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20209H7661999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20196L0191999-07-0808 July 1999 Safety Evaluation Granting Request Relief B-6 (Rev 2),B-7 (Rev2),B-12,B-13,B-14 & C-9,pursuant to 10CFR50.55a(g)(6)(i).Technical Ltr Rept Also Encl ML20209G7501999-07-0808 July 1999 SER Finding That Licensee Individual Plant Exam of External Events Complete with Regard to Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given Design, Operation & History of Comanche Peak Steam Electric Station ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively ML20206Q0091999-05-14014 May 1999 Safety Evaluation Accepting GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Electric Station,Unit 1 ML20206H2061999-05-0606 May 1999 SER Accepting Exemption to App K Re Leading Edge Flowmeter for Plant,Units 1 & 2 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 ML20202D0101999-01-27027 January 1999 Safety Evaluation Supporting First 10-yr Interval ISI Program Plan Requests for Relief B-9,B-10 & B-11 for CPSES, Unit 1 ML20154B5741998-09-30030 September 1998 Safety Evaluation Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves. Licensee Has Established Acceptable Program ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20135B7911996-11-29029 November 1996 Safety Evaluation Approving Corporate Restructuring of TU to Facilitate Acquisition of Enserch Corp ML20128C1721993-01-29029 January 1993 Safety Evaluation Accepting First 10-yr Interval Inservice Testing Program for Pumps & Valves ML20198D3331992-05-0606 May 1992 Safety Evaluation Supporting Licensee Response to Generic Ltr 82-33 Concerning Implementation of Reg Guide 1.97,rev 2 ML20235U5631989-02-24024 February 1989 Safety Evaluation Concluding That Stated 10CFR70 License Conditions Should Be Incorporated Into 10CFR50 License ML20153C8171988-08-25025 August 1988 Safety Evaluation Supporting Corrections to Amends 9 & 8 to CPPR-126 & CPPR-127,respectively ML20236A5741987-10-13013 October 1987 Safety Evaluation Re Util 850502 Request to Eliminate Arbitrary Intermediate Pipe Breaks.Request Acceptable Provided Applicant Maintains Environ Qualification of safety-related Mechanical & Electrical Equipment ML20214X1801987-06-0808 June 1987 Safety Evaluation Supporting Modified Design Basis Documented in Amend 61 ML20214T7661987-05-28028 May 1987 Handwritten Sser on Allegation Re Qa/Qc Repair,Rework & Maint ML20214J7221986-08-15015 August 1986 SER on Tdi Diesel Generator Owners Group Findings & Recommendations Re Operability/Reliability of Tdi Emergency Diesel Generators ML20141P2181986-03-13013 March 1986 Evaluation Approving Use of ASME Code Cases N-397 & N-411. Applicant Must Investigate Root Cause by Considering Physical Mods Made to Piping Sys & Indicate Extent to Which Issues Resolved as Result of Revised Analyses Using Cases ML20210S8041986-02-18018 February 1986 Marked-up SER Re Rev 3 to Comanche Peak Response Team Program Plan ML20133H9021985-08-0606 August 1985 Sser of Qualifications & Training of Operators & Adequacy of Extant Training Programs to Maintain Operator Readiness. Training Programs Acceptable,Barring Major Problems ML20133Q0231985-08-0606 August 1985 Mechanical Engineering Branch Sser Re Inservice Testing of Pumps & Valves.Program for Pumps & Valves Acceptable ML20133Q0281985-07-12012 July 1985 SER Supporting Pump & Valve Inservice Testing Program ML20128L8791985-07-0101 July 1985 SER Re Conformance of post-accident Monitoring Design,Per Reg Guide 1.97,Rev 2 Re Emergency Response Capabilities. Neutron Flux Instrumentation Must Be Provided Before Fuel Loading ML20199G4531985-03-19019 March 1985 Partially Withheld marked-up Rev 5 to Sser Re Allegation AQ-91 Concerning Inadequate Training of Personnel.Related Info Encl ML20215K6461985-03-15015 March 1985 Partially Deleted Draft Sser Providing Results of Staff Evaluation & Resolution of Approx 400 Technical Concerns & Allegations in Mechanical & Piping Area Re Constr Practices at Plant ML20199G6201985-03-13013 March 1985 Partially Withheld marked-up Rev 4 to Sser Re Allegation AQ-98 Concerning Extensive Delays in Repair of safety-related Matl ML20199G7751985-01-22022 January 1985 Partially Withheld marked-up Rev 1 to Sser Re Allegation AQ-41 Concerning Sandblasted Pipe Sections Which Removed Heat Markings Used for Traceability.Related Info Encl ML20206U9251984-12-19019 December 1984 Partially Withheld Rev 1 to Sser Re Allegation AE-17, Alleging Field Run Conduit,Drywall & Lighting Installed Above Ceiling Panels in Control Room Classified as Nonseismic ML20206U6351984-12-19019 December 1984 Partially Withheld Rev 1 to Sser Re Allegations AQC-13, AQC-14,AQC-15,AC-18 & AC-40,alleging Unauthorized & Undocumented Holes Drilled Through Reinforcing Steel ML20206U9351984-12-19019 December 1984 Partially Withheld Draft 7 to Sser Re Allegation AC-41 Concerning Poor Workmanship in Use of Elastic Joint Filler Matl Between Seismic Category I Structures.Related Documentation Encl ML20199G6301984-11-0101 November 1984 Partially Withheld marked-up Rev 3 to Sser Re Allegation AQ-131 Concerning Electrical Boxes That Were Shipped to Facility in Damaged Condition or Were Damaged & Repaired by Unauthorized Personnel.Related Info Encl ML20199G6141984-10-0505 October 1984 Partially Withheld marked-up Rev 2 to Sser Re Allegation AQ-88 Concerning safety-related Work Performed by Illegal Aliens ML20199G6241984-10-0202 October 1984 Partially Withheld marked-up Draft 4 to Sser Re Allegation A-130 Concerning Valve Disc Numbers on Repair Travelers That Differ from Code Data Rept ML20202B9301983-08-10010 August 1983 SER Supporting Generic Westinghouse Mod for Reactor Trip Sys Automatic Actuation Using Shunt Coil Trip Attachments W/ Listed exceptions.Plant-specific Design Info Required for Westinghouse Plants Incorporating Shunt Trip Mod Encl 1999-09-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E8021999-10-0707 October 1999 CPSES Unit 1 Cycle 8 Colr ML20217G4151999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Cpses,Units 1 & 2 ML20212F7671999-09-24024 September 1999 SER Granting Relief Request C-4 Pursuant to 10CFR50.55a(g)(6)(i) for Unit 2,during First 10-year ISI Interval & Relief Requests B-15,B-16 & B-17 Pursuant to 10CFR50.55a(g)(6)(i) ML20216J5701999-09-16016 September 1999 Rev 2 to CPSES Unit 2 Cycle 5 Colr TXX-9920, Monthly Operating Repts for Aug 1999 for Cpses.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Cpses.With ML20211M2981999-08-0606 August 1999 Rev 1 to CPSES Fuel Storage Licensing Rept, CPSES Credit for Soluble Boron & Expansion of Spent Fuel Storage Capacity, Consisting of Revised Title Page and 4-1 ML20210U4081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Cpses,Units 1 & 2 ML20210D8321999-07-23023 July 1999 Safety Evaluation Accepting Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20209H7661999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 ML20209H2721999-07-0909 July 1999 2RF04 Containment ISI Summary Rept First Interval,First Period,First Outage ML20209H2631999-07-0909 July 1999 2RF04 ISI Summary Rept First Interval,Second Period,Second Outage ML20209G7501999-07-0808 July 1999 SER Finding That Licensee Individual Plant Exam of External Events Complete with Regard to Info Requested by Suppl 4 to GL 88-20 & That IPEEE Results Reasonable Given Design, Operation & History of Comanche Peak Steam Electric Station ML20196L0191999-07-0808 July 1999 Safety Evaluation Granting Request Relief B-6 (Rev 2),B-7 (Rev2),B-12,B-13,B-14 & C-9,pursuant to 10CFR50.55a(g)(6)(i).Technical Ltr Rept Also Encl ML20210J9391999-06-30030 June 1999 CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20209G0801999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Cpses,Units 1 & 2 ML20196J0621999-06-29029 June 1999 Safety Evaluation Supporting Proposed Changes to Emergency Plan Re Licenses NPF-87 & NPF-89 Respectively ML20195G5141999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Comanche Peak Steam Electric Station,Units 1 & 2.With ML20216E0711999-05-21021 May 1999 1999 Graded Exercise - Comanche Peak Steam Electric Station ML20206Q0091999-05-14014 May 1999 Safety Evaluation Accepting GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Comanche Peak Electric Station,Unit 1 ML20206H2061999-05-0606 May 1999 SER Accepting Exemption to App K Re Leading Edge Flowmeter for Plant,Units 1 & 2 ML20196L2241999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Cpses,Units 1 & 2 ML20205R5701999-04-14014 April 1999 Rev 6 to ER-ME-067, TU Electric Engineering Rept,Evaluation of Thermo-Lag Fire Barrier Sys ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20205J7831999-04-0101 April 1999 Rev 0 to ERX-99-001, CPSES Unit 2 Cycle 5 Colr ML20205N3101999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Cpses,Units 1 & 2 ML20204H6371999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Comanche Peak Units 1 & 2 ML20205N1481999-02-28028 February 1999 Corrected Monthly Operating Rept for Feb 1999 for CPSES, Units 1 & 2 ML20203A4881999-02-0303 February 1999 Safety Evaluation Granting Requests for Relief B-3 - B-6,C-2 & C-3 for Plant,Unit 2 ML20210J9201999-02-0101 February 1999 CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802- 990201 ML20202D0101999-01-27027 January 1999 Safety Evaluation Supporting First 10-yr Interval ISI Program Plan Requests for Relief B-9,B-10 & B-11 for CPSES, Unit 1 ML20199E9961998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Cpses,Units 1 & 2 ML20207D6091998-12-31031 December 1998 1998 Annual Operating Rept for Cpses,Units 1 & 2. with ML20197K2371998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Cpses,Units 1 & 2 ML20195F3161998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Cpses,Units 1 & 2 ML20154M8841998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Cpses,Units 1 & 2 ML20154B5741998-09-30030 September 1998 Safety Evaluation Re Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Motor-Operated Valves. Licensee Has Established Acceptable Program ML20151W0361998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Cpses,Units 1 & 2. with ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C4061998-08-14014 August 1998 Safety Evaluation Supporting Request to Implement Risk Informed IST Program ML20237C6721998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Cpses,Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236R0711998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Cpses,Units 1 & 2 ML20249B2581998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Cpses,Units 1 & 2 ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20247G3241998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Cpses,Units 1 & 2 ML20216B8661998-04-0101 April 1998 Rev 0 to ERX-98-001, CPSES Unit 1 Cycle 7 Colr ML20216J3061998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Cpses,Units 1 & 2 ML20216J1861998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Comanche Peak Steam Electric Station ML20197A6951998-02-24024 February 1998 Inservice Insp Summary Rept,First Interval,Second Period, First Outage ML20199J5391998-02-0202 February 1998 CPSES Commitment Matl Change Evaluation Rept 0002 for 960202-970801 1999-09-30
[Table view] |
Text
_. _ _ _ _ _ . _ . _ _ _ _ ___
. c Docket No. 50-445 ENCLOSURE MECHANICAL ENGINEERING BRANCH SUPPLEMENT TO SAFETY EVALUATION REPORT SECTION 3.9.6 FOR COMANCHE PEAK, UNIT NO. 1 3.9.6 In-Service Testing (IST) of Pumps and Valves In supplement No. 1 to NUREG-0797 the staff granted interim relief pending review of the IST program for pumps and valves. That review is now completed.
A detailed safety evaluation, which includes endorsement as well as other comments, is forwarded as an enclosure to this SER section. The contents of the enclosure are summarized below.
By a letter dated October 27, 1983 the applicant forwarded an IST program "or pumps and valves for staff review and acceptance. That submittal, along with the evaluations and comments contained in the enclosure to this SER section constitutes the IST program for pumps and valves for Comanche Peak, Unit 1.
The IST program should not be modified without the approval of the NRC.
The staff concludes that the applicant's pump and valves test program is acceptable and meets the requirements of 10 CFR Part 50, Appendix A, General
- .- Design Criteria 37, 40, 43, 46, 54, and $50.55a(g). This conclusion is based on the applicant having provided a test program to ensure that safety-related pumps and valves will be in a state of operational readiness to perform neces-sary safety. functions throughout the life of the plant, this program includes
' baseline preservice testing and periodic inservice testing. The program pro-vides for both functional testing of the components in the operating state and for visual inspection for leaks and other signs of distress. Applicant has also formulated his inservice test program to include all safety related Code Class 1,12, and 3 pumps and valves and to include those pumps anc valves which are not Code Class 1, 2, and 3 but are considered to be safety related.
9508140578 850006 1 PDR ADOCK 05000445 A PDR
The following relief requests were denied for the reasons summarized below.
(Relief request numbers, where noted, are from the applicants submittal of October 27, 1983. Section numbers are those stated in the enclosure.)
In section 3.2.1.1, permission was denied to commence cold shutdown testing within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of reaching cold shutdown only if the shutdown period is scheduled to be longer than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Normally, cold shutdown testing is required to begin within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of achieving cold shutdown, regardless of the length of the outage. No basis was provided by the applicant and thus relief was deni'ed.
In section 3.2.4, relief request V-1 was denied to ignore the provisions of ASME Code paragraph IWV-3426 and 3427 regarding analysis of leakage rates and corrective action respectively. Adequate corrective actions and controls for reducing excessive leakage are not contained in 10CFR50 Appendix J for individual valves as the applicant has stated.
In section 3.4.2.1, relief request 6.2 was denied to exercise valves 1POV-455A and 456 only every 18 months. No basis was provided by the applicant. -
- In section 3.6.1.1, relief request 13.1 was denied to part stroke exercise valves 1 CT-142 and 145 every 5 years. Partial disassembly of the valves at refueling outages is required as a substitute procedure.
In section 3.6.2.1, relief request 13.2 was denied to not test valves 1CT-148 and 149. Partial disassembly'of the valves at refueling outages is required as a substitute procedure.
In section 3.7.1.2, relief request 15.12 was denied to exercise valves 1-8811A and B only at refueling outages because the facilities exist to stroke-exercise these valves quarterly.
In section 3.7.1.3, relief request 15.4 was denied to not exercise test valves t
1-8956 A, B, C and D. Partial disassembly of the valves at refueling outages
[
is required as a substitute procedure.
l 2
i _ _ _ _ . _ . _ _ _ _ __ ___ , _
e a In section 3.7.1.5, relief request 15.6 was denied to stroke-exercise valves 1-8818 A, B, C and 0 at refueling outages because exercising can be accomplished at cold shutdowns.
In section 3.7.1.6, relief request 15.4 was denied to not exercise test valves 1-8948 A, B, C and D. These valves can be part-stroke exercised at cold shutdown and full-stroke exercised at refueling outages.
In section 3.2.3.1 the applicant proposed that stroke time for rapid acting valves be a maximum of 5 seconds. The staff requirement is 2 seconds.
The applicant has omitted a number of valves from the IST program as outlined in Appendix C, Item 1 of the enclosure as well as in Appendix E Items 3., 4.,
and 7. of the enclosure. These valves must be included in the program. All safety related pumps and valves must be included in the IST program, whether they are tested or not.
The applicant has categorized pressure isolation valves as listed in section 3.1.7 as Category A or AC to meet the staff requirements. The allowable leakage rate must be specified not to exceed 1/2gpm per nominal inch of valve size up to Sgpm maximum for each valve as will be stated in the Technical Specifications.
The applicant has categorized a number of containment isolation valves other than A or A/C as would normally be required of valves whose seat leakage is limited. (See item 2 of Appendix C of the enclosure). Explanations and/or relief requests are required for the valves listed.
\
The NRC staff finds that it is impractical within the limitations of the l Comanche Peak plant design, geometry, and accessibility for the applicant to !
meet certain requirements of Subsection IWP and IW of Section XI of the ASME Code. Imposing these requirements would result in hardships or unusual difficulties without a compensating increase in the level of quality or safety.
3
Therefore, pursuant to 10CFR50.55a, the relief requested from the pump and valve testing requirements of 10CFR50.55a(g)(2) and 10CFR50.55a(g)(4)(1) is discussed in detail in the enclosure and is granted as noted in the enclosure or denied, as applicable for the initial 120 month period of the IST program.
With these stipulations, the NRC staff finds the Commanche Peak Unit 1 IST pro-
. gram for pumps and valves acceptable and in conformance with the Commission's regulations.
E
- _ . .-, _ _. _ . . . ___ - . . _ _ _ . _ _ _ _ . _ _ _ _ . , , , _ , ,, _