ML17286A773
| ML17286A773 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 05/07/1991 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17286A772 | List: |
| References | |
| NUDOCS 9105230183 | |
| Download: ML17286A773 (10) | |
Text
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UNITED STATES NUCLEAR REGULATORY COIVIIVIISSION WASHINGTON, D.C. 20555
~ g~~~+~ SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE INSERVICE TESTING PPOGRAM AND RE UESTS FOR RELIEF WASHINGTON PUBLIC POWER SUPPLY SYSTEM NUCLEAR PROJECT NO.
2 DOCKET NO. 50-397
1.0 INTRODUCTION
The Code of Federal Regulations, 10 CFR 50.55a, requires that i nservice testing
( IST) of certain ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable
- addenda, except where specific written relief has been requested by the licensee and granted by the Commission pursuant to 10 CFR 50.55a(a)(3)(i), (a)(3)(ii), or (g)(6)(i).
In requesting relief, the licensee must demonstrate that:
(1) the proposed alternatives provide an acceptable level of quality and safety; (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety; or (3) conformance with certain requirements of the applicable Code edition and addenda is impractical for its facility.
The Code of Federal Regulations, 10 CFR 50.55a(a)(3)(i), (a)(3)(ii), and (g)(6)(i), authorizes the Commission to grant relief from these ASME Code requirements as it determines is authorized by law and wi 11 not endanger life or property or the common defense and security and is otherwise in the public interest giving due consideration to the burden upon the licensee that could result if the requirements were imposed on the facility.
The NRC staff's findings with respect to granting or not granting the relief requested as part of the licensee's IST Program are contained in this Safety Evaluation (SE) for Washington Public Power Supply System Nuclear Project No.
2 (WNP-2).
The IST program addressed in this evaluation covers the first ten-year inspec-tion interval from December 13, 1984 to December 13, 1994.
The licensee's program includes pump and valve IST program, Revision 3B, and is described in letter dated June 7,
1985, which superseded all previous submittals and as amended by letters dated December 20, 1985, October 12,
- 1987, and December 7, 1990.
The program is based on the requirements of Section XI of the ASME Code, 1980 Edition through the Winter 198l Addenda.
- 2. 0 EVALUATION The IST program and the requests for relief from the requirements of Section XI have been reviewed by the staff with the assistance of its contractor, EG&G, Idaho, Inc.
(EGSG).
In addition, EGSG and staff members met with licensee representatives on Apri 1 16 and 17,
- 1985, in a working session to discuss questions resulting from.the review.
The Technical Evaluation Report (TER),
provided as Enclosure 2, is EGSG's evaluation of the licensee's inservice testing program and relief requests.
The staff has reviewed the TER and 9i05230i83 9i0507 PDR ADOCK 05000397 P
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concurs with the evaluations and conclusions contained therein.
A summary of the pump and valve relief request determinations is presented in Table 1, provided as Attachment l.
The granting of relief is based upon the fulfillment of any commitments made by the licensee in its basis for each request and the alternative proposed testing.
Three relief requests were denied (TER Section 2.1.1; 3.2.1; and 3.8.1), six relief requests were granted with certain conditions (TER Section 2.1.2; 2.3.1; 2.4.1; 2.4.2; 3.1.2.1; and 3.1.6.1),
and five relief requests were granted on an interim basis (TER Section 2.1.5.1; 3.5.1.1; 3.9.2.1; 3.12.1.1; and 3.13.1.1).
The licensee should refer to the specific TER section for detailed discussion of these cases.
These denials and conditions are listed in the TER, Appendix B, which also lists other IST program anomalies identified during the review.
The licensee should resolve all the items listed in Appendix B in accordance with the staff guidance therein.
Items 3 and 12 in Appendix B shou ld be resolved within one year of receipt of this SE or the next refueling outage, whichever is longer.
As necessary, program/procedural changes covered by the remaining items in Appendix B should be made within six months of receipt of this SE.
- 3. 0 CONCLUSIONS Based on the review of the licensee's IST program relief requests, the staff concluded that the relief requests as evaluated and modified by this SE will provide reasonable assurance of the operational readiness of the pumps and valves to perform their safety related functions.
The staff has determined that granting relief, pursuant to 10 CFR 50.55a(a)(3)(i), (a)(3)(ii) and (g)(6)(i), is authorized by law and will not endanger life or property or the common defense and security and is otherwise in the public interest.
In making this determination the staff has considered the alternate testing being imple-
- mented, compliance resulting in a hardship without a compensating increase in
- safety, and the impracticality of performing the required testing considering the burden if the requirements were imposed.
The last column of Table 1
identifies the regulation under which the requested relief is granted.
During the review of the licensee s inservice testing program, the staff has identified certain misinterpretations or omissions of Code requirements.
These items. are summarized in the TER, Appendix B.
The IST program relief requests for WNP-2 provided by submittal dated June 7, 1985, with additional information provided by submittals dated December 20, 1985, October 12, 1987, and December 7, 1990, are acceptable for implementation provided that the actions on the TER Appendix B items are taken in accordance with the schedule set forth above in the last paragraph of Section 2.0.
Attachments:
l.
Table 1 - Summary of Relief Requests 2.
Technical Evaluation Report, EGG-NTA-8427 Principal Contributor:
A. Keller Date:
Nay,5, 1991
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ATTACHMENT 1 Page No.
02/06/91 WASHINGTON NUCLEAR.POWER STATION UNIT 2 SER TABLE 1
SUMMARY
OF RELIEF REQUESTS RELIEF REQUEST NUMBER TER SECTION SECTION XI, EQUIPMENT REQUIREMENT IDENTIFICATION
& SUBJECT ALTERNATE METHOD OF TESTING AGTION BY USNRC Gen RG-1 2.1.1.1 Various Various Approval of relief requests Submit IST program Relief Denied changes at a time interval decided on by the licensee.
Interim approval decided by licensee.
Pump RP-1 2.1.2.1 IWP-3100 Measure bearing vibration displacement All pumps in the Measure pump bearing Relief Granted IST program vibration in units With Provision of velocity.
(a)(3)(i)
RP-1 RP-1 RP-1 2.1.3.1 2.1.4.1 2.1.5.1 IWP-3100 Location of bearing vibration measurements IWP-4300 Measure bearing temperature OM-6 Vibration velocity acceptance criteria HPCS-P-1, 2,
LPCS-P-1, RHR-P-2A, B, C,
SW-P-1A & B,
& DO-P-IA, 1B, 2
All pumps in the IST program Fuel pool cooling pumps:FPC-1A and
-18 and Diesel fuel oil transfer pumps:DO-P-1A,
-18, and 2
Take measurements at Relief Granted the locations (g)(6)(i) specified in ON-6.
Measure pump bearing Relief Granted vibration velocity (a) (3) (i) instead of bearing temperature.
Use limits described Interim Relief in IST program.
Granted (a)(3)(ii) for one year or until the next refueling outage.
RP-2 2.2.1 IWP-3100 Measure inlet and differential pressure SLC-P-lA and 1B Measure pump discharge pressure and flow rate.
Relief Granted (a)(3)(i)
RP-3 2.3.1 IWP-3100 Measure inlet and differential pressure SW-P-1A and 1B, Verify spray pond Relief Granted and HPCS-P-2 level and pump With Provision discharge pressure.
(a)(3)(i)
Page No.
2 02/06/91 MASHINGTON NUCLEAR POWER STATION UNIT 2 SER TABLE 1
SUMMARY
OF RELIEF REQUESTS RELIEF REQUEST NUMBER TER SECTION XI EQUIPHENT SECTION REQUI REHENT IDENTIFICATION 5 SUBJECT
, ALTERNATE METHOD OF TESTING ACTION BY USNRC RP-4 RP-5 Deleted 2.4.1 IMP-4600 DO-P-1A, IB, 8
2 Calculate pump flow Relief Granted Measure flow rate based on day With Provision rate tank rate of level (g)(6)(i) change.
RP-6 2.4.2 IMP-3100 Measure inlet pressure DO-P-1A, 1B, 5 2 Determine pump Relief Granted suction pressure With Provision from tank level (g)(6)(i) prior to pump start.
Valve RV-1 3.1.1.1 IMV-3417(a)
Stroke time and trending Corrective action Rapid-acting solenoid operated valves Assign maximum limiting stroke time of two seconds.
Upon exceeding this limit perform corrective action.
Relief Granted (g)(6)(i)
GL 89-04, Position 6
RV-2 RV-3 RV-3 3.4.1.1 3.9.1.1 3.9.1.2 IWV-3521 Test SLC-V-6 and 7
frequency IWV-3521 Test CIA-V-21, 31A, frequency and 31B IWV-3521 CIA-V-40M, N, Exercising P,
R, S, U, and procedure and V
frequency Full-stroke exercise every 18 months.
Verify closure during Appendix J testing.
Verify valve operability by accumulator pressurization and pressure decay test once every two years.
Relief Granted (g)(6)(i)
Relief Granted (g)(6)(i)
Relief Granted (g)(6)(i)
RV-4 3.1.2.1 IMV-3420 Valve leak rate test WNP-2 containment isolation valves Leak test to Appendix J, MNP-2 Tech.
Specs.,
and WNP-2 FSAR using non-fixed target leak rate values.
Relief Granted With Provision (g)(6)(i)
GL 89-04, Position 10
1 Page No.
02/06/91 WASHINGTON NUCLEAR POWER STATION UNIT 2 SER TABLE 1
SUMMARY
OF RELIEF REQUESTS RELIEF REQUEST NUMBER TER SECTION SECTION XI EQUIPMENT REQUIREMENT IDENTIFICATION 5 SUBJECT ALTERNATE METHOD OF TESTING ACTION BY USNRC RV-4 3.1.3. 1 IWV-3427(b)
Various Dual Take corrective Relief Granted Corrective function valves, action when leakage (g)(6)(i) action PIVs and CIVs exceeds technical specification limit for PIVS.
RV-3 Deleted 3.10.1.1 IMV-3426 and 3427 Analysis of leakage rates and corrective action I
CVB-V-IA-H, J-N,. Full-stroke exercise Relief Granted P,
Q, R,
S, and once every 18 (g)(6)(i)
T months.
RV-7 3.9.1.3 IWV-3424 CIA-V-40M, N, P, Verify operational Relief Granted Analysis of R, S, U,
and V
readiness in groups (a)(3)(i) leakage rates based on accumulator decay tests.
RV-B RV-9 3.3.1.1 3.1.4.1 IMV-3521 Test frequency IMV-3522 Test frequency RHR-V-209 RCIC-V-65, 66, LPCS-V-6, HPCS-V-5, RHR-V-41A, B, C, 5 50A 5 SOB Relief Granted (g)(6)(i)
Full-stroke exercise Relief Granted at refueling (g)(6)(i) outages.
Exercise at cold shutdown when de-inerted and during refueling outages.
RV-10 RV-11 Deleted 3.11.1.1 IWV-3521 Test frequency PI-EFCX-72f,
- 72e, and TIP-V-6 Exercise during cold Relief Granted shutdowns when (g)(6)(i)
.de-inerted and during refueling outages.
RV-12 3.12.1.1 IMV-3413 DO-V-40A and B
Stroke time measurements Verify proper system Interim response.
Relief Granted (g)(6)(i) for one year or until next refueling outage
Page No.
4 02/06/91 WASHINGTON NUCLEAR POWER STATION UNIT 2 SER TABLE 1 SUHHARY OF RELIEF REQUESTS RELIEF REQUEST NUMBER TER SECTION XI EQUIPHENT SECTION RE QUIREHENT IDENTIFICATION 5 SUBJECT ALTERNATE HETHOD OF TESTING ACTION'Y USNRC RV-13 3.6.1.1 IMV-341) and 3413 Test frequency and stroke time measurements ADS valves HS-RV-3D, 4A, 4B, 4C, 4D, 5B, and 5C Full-stroke exercise each 18 months in accordance with WNP-2 technical specifications.
Relief Granted (g)(6)(i)
RV-14 RV-15 3.7.1.1 3.1.5.1 IMV-3521 Test frequency Instrument line excess flow check valves IWV-3413 CRD-V-10, 11, Stroke time
- 180, and 181 measurements Heasure the stroke time for these valves in pairs.
Full-stroke exercise in accordance with Technical Specifications each 18 months.
Relief Granted (g)(6)(i)
Relief Granted (g)(6)(i)
RV-16 RV-17 3.1.6.1 IMV-3521 Test frequency RHR-V-84A, B, C, HPCS-V-7, and LPCS-V-33 3.2.1. 1 IMV-3522 RCIC-V-111 Test method and 112 Exercise both valves open quarterly and verify one series valve shuts, and that both shut at refueling.
Full-stroke open quarterly and verify that one valve of the series shuts and operate stop-check valve manually.
Relief Denied Relief Granted With Provision (g)(6)(i)
RV-18 3.6.2.1 IWV-3521 Test frequency HS-V-37 and
~ Full-stroke exercise 38A-H, J-N, P,
at cold shutdowns R, S, U, and V
when de-inerted and refueling outages.
Relief Granted (g)(6)(i)
RV-19 3.8.1.1 IMV-3413 Stroke time'ethod
. HY-V-17A, B, 18A, B, 19A, B, 20A, B, 33A, B,
- 34A, B) 35A, B, 36A, and B
Measure only the Relief Denied stroke time of the slowest valve in each group of four.
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-Page No.
5 02/06/91 WASHINGTOA NUCLEAR POWER STATION UNIT 2 SER TABLE 1
SUMMARY
OF RELIEF REQUESTS RELIEF TER SECTION XI EQUIPHENT REQUEST SECTION REQUIREMENT IDENTIFICATION NUMBER 5 SUBJECT ALTERNATE METHOD OF TESTING ACTION BY USNRC RV-20 RV-21 3.1.1.2 3.5.1.1 IWV-3417(a)
Stroke time trending IMV-3413 Stroke time measurement All power operated valves in the IST program SM-V-214, 215,
- 216, and 217 Establish fixed acceptance values based on valve baseline stroke times.
Verify operation quarterly by observing valve actuator.
Take no stroke time measurements.
Relief Granted (a)(3)(i)
Interim Relief Granted
{g)(6)(i) for 1 year or until the next refueling outage.
RV-22 3.13.1.1 IMV-3413 Stroke time measurement SM-TCV-llA, 11B, Verify proper system
- 15A, and 15B response or valve stem position.
Interim Relief Granted (g) (6) (i) for one year or until next refueling outage.
RV-23
).14.1.1 IMV-3413 Stroke time measurement PSR-VX-73-1, 77A1, 77A3, 80-1, 82-1, 82-7, 83-1, 84-1, and 88-1 These valves are all rapid acting valves, operate in <2 secs.
Time slowest in the group.
Relief Granted (a)(3)(i)
RV-24 3.9.2.1 IMV-3413 Stroke time measurement CIA-SPV-lA to 15A and CIA-SPV-1B to 19B Test per IMV-3410 with the exception of IWV-3413.
Interim Relief Granted (g)(6)(i) for one year or until next refueling outage.
RV-25 3.1.7.1 IMV-3412 and Valves that can Test during cold
-3522 be tested only shutdowns at the Test during cold frequency descr ibed frequency shutdowns in the IST program.
Relief Granted a)(3)(ii) only or valves that can be tested during any cold shutdown.
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