ML18096B048
| ML18096B048 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/09/1992 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17349A929 | List: |
| References | |
| GL-89-04, GL-89-4, NUDOCS 9210210181 | |
| Download: ML18096B048 (14) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO INSERVICE TESTING PROGRAM RELIEF REQUESTS FOR PUMPS AND VALVES PUBLIC SERVICE ELECTRIC AND GAS COMPANY SALEM NUCLEAR GENERATING STATION STATION, UNITS 1 AND 2 DOCKET NOS. 50-272 AND 50-311
1.0 INTRODUCTION
The Code of Federal Regulations, 10 CFR 50.55a, requires that inservice testing (IST) of certain ASME Code Class I, 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 Sections
{a)(3)(i), (a)(3)(ii), or (g)(6)(i) of 10 CFR 50.55a.
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 is impractical for its facility.
NRC guidance contained in Generic Letter (GL) 89-04, "Guidance on Developing Acceptable Inservice Testing Programs," provided alternatives to the Code requirements determined acceptable to the staff.
- Pursuant to 10 CFR 50.55a, the Commission is authorized to grant relief from ASME Code requirements upon making the necessary findings.
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).
The IST Program in this SE covers the second IO-year IST interval which began June 30, 1987.
Public Service Electric and Gas Company (the licensee) submitted Revision 1 in a June 26, 1987, letter to the NRC.
Revision 2 of the Salem Nuclear Generating Station, Units 1 and 2, IST Program was included as of their response to GL 89-04, dated October 3, 1989.
Additional relief requests were included in submittals dated February 28, 1990, March 14, 1991, and May 16, 1991.
The licensee's program is based on the requirements of the 1983 Edition, with Summer 1983 Addenda, of the ASME Section XI Code.
- 2. 0 EVALUATION The licensee's IST Program requests for relief from the requirements of Section XI have been reviewed by the staff with the assistance of its contractor, Idaho National Engineering Laboratory {INEL}.
The Technical Evaluation Report {TER} provided as Attachment 2 is INEL's evaluation of the licensee's IST Program relief requests.
The staff has reviewed the TER and concurs with the evaluations and conclusions contained therein, except as noted below.
A summary of the relief request determinations is presented in the Table {Attachment 1). The granting of relief is based upon the fulfillment of any commitments made by the licensee in its basis for each relief request and the alternatives proposed.
The implementation of the IST Program is subject to inspection by NRC.
As requested in GL 89-04, the licensee performed a review of their IST Program and provided a response to each of the positions included in Attachment 1 of GL 89-04.
The results of the review and the status of conformance to the guidelines were described in Attachment 1 of the submittal dated October 3,
.1989.
A summary of the licensee's response to each item is as follows:
Positions 1 and 2 - Check Valve Flow Testing For valves which cannot be full flow tested under any plant condition, a periodic disassembly program has been established which conforms to the guidance provided in Position 2.
Position 3 - Check Valve Backflow Testing Backflow testing for all applicable check valves is performed within the guidelines of the Generic Letter using several different methods of verification.
Position 4 - Pressure Isolation Valve Testing All the pressure isolation valves in Technical Specifications are in the IST Program and are individually leakage tested.
Position 5 - Limiting Values of Full-Stroke Times for Power Operated Valves The licensee described the establishment of limiting values of stroke times based on a design basis or licensing value for each valve.
Procedure changes were to be complete by December 31, 1989.
Position 6 - Limiting Stroke Times for Rapid-Acting Valves Valves which stroke in less than 2 seconds will be assigned a limit of 2 seconds in accordance with GL 89-04, with the deviation listed in the IST Program for each applicable valve.
I Position 7 - BWR Scram Valves - Not Applicable to PWRs Position 8 - Technical Specifications Action Statement Start Times Salem Station is in compliance with this position. If pump test results are in the "required action range," the shift operators immediately declare the pump inoperable and enter the appropriate ACTION statement.
Operators have "design values" for determining valYe operability and entering ACTION statements.
Position 9 - Pump Testing Using Mini-Flow Return Lines All pump testing at Salem Station utilizing mini-flow return lines is conducted through instrumented flow lines. All affected pumps also receive a full flow test when plant conditions permit.
Relief has been requested for the emergency diesel generator engine-shaft-mounted positive displacement pumps for which testing per Section XI is not feasible.
Position 10 - Containment Isolation Valve Testing All containment isolation valves from the Appendix J Program are listed in the IST Program an Category A or A/C valves.
For containment isolation valves 6 inches or larger, the deviation from IWV-3427(b} has been listed in the IST Program as accepted by GL 89-04.
Position 11 - IST Program Scope A complete review of the IST Program resulted in the addition of several valves which had been previously overlooked.
Generic Letter 89-04 approved currently submitted (prior to April 3, 1989} IST Program relief requests for Salem Nuclear Generating Station, Units 1 and 2, except as modified to address the positions delineated in Attachment 1 of the generic letter (reference GL 89-04, "IST Program Approval"}. Jn Table 1, the relief requests so approved are noted as "Preapproved" and have not been further evaluated in the SE/TER.
Two relief requests are provisionally granted based on the guidance delineated in GL 89-04, related to Position 2, and are noted as such.
Certain relief requests, as listed in the attached Table, related to non-Code components outside the scope of 10 CFR 50.55a and were not further evaluated in the SE/TER.
For certain relief requests, interim relief is granted to provide the licensee a period of time to evaluate other methods to comply with the Code requirements.
One relief request is denied, in part, for the test frequency of stroking the reactor vessel head vent valves.
The requested relief for testing of valves 1SJ3 and 2SJ3 has been denied, as discussed below.
- The licensee should refer to the TER, Appendix A, for a discussion of IST Program anomalies identified during the review.
The licensee should resolve all items in accordance with the guidance therein.
The IST Program relief requests that are not denied are acceptable for implementation provided (1) the action items identified in Appendix A of the TER are addressed within 1 year of the date of this SE and (2) procedural or program changes covered in the action items are completed within 1 year of the date of this SE or by the end of the next refueling outage, whichever is later, or by the schedule specified in an individual action item.
The licensee should respond to the NRC within 1 year of the date of this SE describing actions taken, or to be taken, to address each of these items.
For the relief request which has been denied in part, the licensee's testing should comply with the applicable Section Xl requirements or GL 89-04 guidelines within 3 months of the receipt of this SE.
If the licensee has additional justification to address the reasons for the denial, a revised relief request should be submitted within 3 months of the date of this SE.
However, the September 27, 1983, NRC SE related to the reactor vessel head vent valves which is listed as the licensee's basis for testing ~uring refueling outages does not restrict testing during cold shutdown. This reference does not justify the requested extension of the test interval to refueling outages, but does justify testing during cold shutdown rather than quarterly, which does not require a relief request. Reference Anomaly 15 in Appendix A of the TER for further discussion related to cold shutdown justifications.
Anomaly 12 discusses the numbering system for relief requests.
Because each relief request has no identifying unique number, the comparison of Revision 2 of the IST Program to the revision prior to ~L 89-04 was difficult. If the licensee identifies any instances where relief requests were overlooked, these should be resubmitted, as they are in an indeterminate status. As noted in the anomaly, each relief request should have a unique identifying number.
Additionally, the licensee should include a discussion in the IST Program which clarifies the 10-year interval schedule for each unit, considering that the commercial operation dates are different {Unit 1 - 06/30/77, and Unit 2 -
10/13/81). Additional relief may be required if the licensee intends for the two units to be on concurrent intervals.
TER Section 3.6.1.l provides an evaluation of a relief request associated with the check valves from the refueling water storage tanks to the suction of the charging pumps, valve numbers 1SJ3 and 2SJ3.
An interim period to address performance of the testing during cold shutdowns is suggested in the TER evaluation and discussed in Anomaly 9 based on a hardship without a compensating increase in the level of quality and safety. However, the staff does not concur that sufficient justification was provided by the licensee that imposition of the testing during cold shutdowns is a hardship.
- ' -* Therefore, this request is denied.
The testing performed for these valves meets the test methods of the Code.
The relief request was related to the test frequency.
The licensee should perform the testing during cold shutdowns and document the justification for the test frequency in a cold shutdown justification. If the licensee believes that they have additional justification for extending the test frequency to refueling outages which was not included in the relief request, the revised relief request must be submitted within 90 days from the date of this SE.
3.0 CONCLUSION
The staff concludes 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), {g)(6)(i), or Generic Letter 89-04, 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 alternative testing being implemented, 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 the Table identifies the regulation or GL 89-04 guidance under which the requested relief is approved.
During the review of the licensee's IST Program relief requests, the staff has identified certain misinterpretations or omissions *of 10 CFR 50.SSa and Section XI requirements.
The items are summarized in the TER, Appendix A.
Except for the partially denied relief request, and the denied request for 1SJ3 and 2SJ3, the IST Program relief requests for the Salem Nuclear Generating Station IST Program, Revision 2, are acceptable for implementation provided (1) the anomalies identified in Appendix A of the TER are addressed within 1 year of the date of this SE and (2) the changes and actions described in the action items of the TER are completed within I year of the date of this SE or by the end of the next refueling outage, whichever is later, or by the schedule specified in an individual action item.
Principal Contributor:
P. Campbell Date: October 9, 1992 Attachments:
- 1.
Summary of Relief Requests
- 2.
Technical Evaluation Report
Page No.
07/31/92 1
RELIEF REQUEST IDENTIFICATION Pump, Attachment 2 Letter dated 3-14-91, Page 3 of 9, Unit 1 Auxiliary Feedwater (AF) pumps:
11, 12, & 13 Pump, Attachment 2 Letter dated 3-14-91, Page 4 of 9, Unit 1 Boric Acid Transfer Pumps:
11 & 12 Pump, Attachment 2 Letter dated 3-14-91, Pages 5 & 6 of 9 Unit 1[2] Chilled Water pumps:
11 & 12[21 & 22]
Pump, Attachment 2 Letter dated 3~14-91, Page 7 of *9, Service Water Pumps:
21 thru 26 Valve, Attachment 2 Letter dated 3-14-91, Page 2 of 9 Valve, Attachment 2 Letter dated 3-14-91, Pa~es 8 & 9 of 9 Unit 1(2] Containment Sump Suction valves:
11 & 12SJ44 (21 & 22SJ44]
SALEM GENERATING STATION, UNITS 1 AND 2 SAFETY EVALUATION TABLE 1
SUMMARY
OF RELIEF REQUESTS TER SECTION XI SECTION REQUIREMENT
& SUBJECT App. A IWP-4110:
Instrument accuracy requirements App. A IWP-4110:
Instrument accuracy requirements 2.1.1.1 IWP-4110:
Instrument accuracy requirements 2.2.1.1 IWP-4110:
Instrument accuracy requirements 3.1.1.1 IWV-3512:
ALTERNATE METHOD OF TESTING Use existing flow instruments until more accurate instrumentation is installed on or
- before Dec. 31, 1991.
Use existing flow instruments until more accurate instrumentation is installed on or before May 31 ~
1991.
Use existin~ flow instrumenta i6n.
Use flow instrumentation located in the Unit 2 pipe tunnel for IST.
Maintenance Test supervisor will be ATTACHMENT 1 ACTION BY USN RC None. Relief not needed after -
12/31/91.
None. Relief not needed after 05/31/91.
Interim Relief Granted 10 CFR 50.SSa (a)(3)(i1), for one year or until the next refueling outage (RO).
Interim Relief Granted (a)( 3)(1 i), for one year or until the next RO.
Relief Granted (a)(l)(ii) supervisor qualified in qualification accordance with ANSI*
18.1-1971.
3.2.1.l IWV-3300:
Remote position Prov is i ona 1 Remote indication will be Relief Granted position verified once every (g)(6){ i) indication other RO.
verification
Page No.
07 /31/92 2
RELIEF REQUEST IDENTIFICATION Valve, Attachment 3 Letter dated 3-14-91, Pa~es 7 & 19 of 24 Unit 1[21 RCS Combined Injection check valves:
ll-14SJ56
[21-24SJ56]
Valve, Attachment 3 Letter dated 3-14-91, Pa~es 9 & 21 of 24 Un1t 1[2] RCS Hot Leg Injection valves:
ll-14SJ139
[21-24SJ139]
Valve, Attachment 3 Letter dated 3-14-91, Pa~es 10 & 22 of 24 Un1t 1(2] RCS Cold Leg Injection valves:
ll-14SJ144
[21-24SJ144]
Valve, Attachment 3 Letter dated 3-14-91, Pa~es 6 & 18 of i4 Unit 1[2] Accumu ator Oi schary*e check va 1 ves:
valves! -14SJ55
[21-24SJ55]
Valve, Attachment 3 Letter dated 3-14-91, Pa~es 2 & 14 of 24 Unit 1[2] RCP Thermal Barrier valves:
ll-14CC128
[21-24CC128]
Valve, Attachment 3 Letter dated 3-14-91, Pa~es 3 & 15 of 24 Unit 1[2] ECCS non-return valves:
1PR25[2PR25]
SALEM GENERATING STATION, UNITS 1 AND 2 SAFETY EVALUATION TABLE 1
SUMMARY
OF RELIEF REQUESTS TER SECTION XI SECTION REQUIREMENT
& SUBJECT 3.2.2.1 IWV-3521:
Test frequency 3.2.2.2 IWVm3521:
Test frequency 3.2.2.3 IWV-3521:
Test frequency 3.2.2.4 IWV-3521:
Test frequency 3.3.1.1 IWV-3521:
Test frequency ALTERNATE METHOD OF TESTING Full-stroke exercise these valves open each RO.
ACTION BY USNRC Provisional Relief Granted (g)(6}(i)
Full-stroke exercise Relief Granted these valves open each RO.
(g)(6)(i)
Full-stroke exercise Relief Granted these valves open each RO.
(g)(6)( i)
Full-stroke exercise Provisional Relief these valves open Granted (g)(6)(i) each RO.
Exercise these Relief Granted valves closed each (g)(6)(i)
RO.
3.4.1.1 IWV-3520:
Part-stroke exercise Provisional Relief Test method
~uarterlb Granted (g)(6)(i) and frequency isassem ie inspect GL 89-04, and leak rate test Position 2 at RO.
Page No.
07/31/92 3
RELIEF REQUEST IDENTIFICATION SALEM GENERATING STATION, UNITS 1 AND 2 SAFETY EVALUATION TABLE 1
SUMMARY
OF RELIEF REQUESTS TER SECTION XI SECTION REQUIREMENT
& SUBJECT ALTERNATE METHOD OF TESTING ACTION BY USN RC Valve, Attachment 3 3.5.1.1 IWV-3410 and Exercise valves Relief Denied for test frequency, Interim Relief Granted (a)(3)(ii), for stroke time and position verification.
Letter dated 3-14-91, Pa~es 4 & 16 of 24 Un1t 1[2] Reactor Vessel Head Vent valves:
1RC40 thru 1RC43
[2RC40 thru 2RC43]
Valve, Attachment 3 Letter dated 3-14-91, Pages 5 & 17 of 24 Unit 1[21 CVCS Suction from Rwsr valves:
1SJ3[2SJ3]
Valve, Attachment 3 Letter dated 3-14-91, Pages 8 & 20 of 24 Unit 1[2] RWST to RHR Suction check valves:
1SJ70[2SJ70]
Valve, Attachment 3 Letter dated 3-14-91, Pages 11 & 23 of 24 Unit 1[2] Turbine Backflow check valves:
11 & 13SW5
[21 & 23SWS]
Valve, Attachment 3 Letter dated 3-14-91, Pa~es 12 & 24 of 24 Un1t 1[2] Nuclear to Conventional Header check valves:
12 & 14SW5
[22 & 24SW5]
3300:
during RO, no Test alternate proposed frequency and for position remote verification.
position indication verification 3.6.1.1 IWV-3521:
Test frequency Full flow exercise open during RO and radiograph to verify closure.
Relief Denied, Refer to SE, Section 2.0.
3.7.1.1 IWV-3521:
Test frequency Full-stroke exercise Relief Granted these valves each (g}(6)(i)
RO.
3.8.1.1 IWV-3520:
Sample disassemble Provisional Relief Test method and inspect one Granted (g)(6)(i) and frequency valve from shutdown GL 89-04, Unit every RO.
Position 2 3.8.1.2 IWV-3520:
Part-stroke exercise Provisional Relief Test method quarterly and *ample Granted (g)(6)(i) and frequency disassemble and inspect a valve from the shutdown unit every RO.
Rev. 2, dated 10/03/89, N/A Unit 1(2] Fuel Oil Engine Driven Booster IWP-3000:
Monitor discharge Measure test pressure monthly.
parameters Components covered are not ASHE Code Class.
Pumps:
11, 12, & 13
[21, 22, & 23]
Request not evaluated in SE/TER.
Page No.
07/31/92 4
RELIEF REQUEST IDENTIFICATION Rev. 2, dated 10/03/89, Unit 1[2] Fuel Oil Transfer Pumps:
11 & 12
[21 & 22]
Rev. 2, dated I0/03/89, Unit I[2] lube Oil Engine Driven Pumps:
11, 12, & I3
[2I, 22, & 23]
Rev. 2, dated 10/03/89, Unit I[2] Lube Oil Pre-Circ Pumps:
[2A, 28, & 2C]
Rev. 2, dated I0/03/89, Unit I~21 AF valves:
I3AF4[ 3 F4]
Rev. 2, dated I0/03/89, Unit I~21 AF valves:
I3AF8[ 3 F8]
Rev. 2, dated I0/03/89, Unit I~2i AF valves:
ll-I3A 5
[21-23AF53]
Rev. 2, dated I0/03/89, Unit I AF valve:
1AF71 SALEM GENERATING STATION, UNITS 1 AND 2 SAFETY EVALUATION TABLE 1
SUMMARY
OF RELIEF REQUESTS TER SECTION XI SECTION REQUIREMENT
& SUBJECT N/A IWP-3000:
Measure test parameters N/A IWP-3000:
Measure test parameters N/A IWP-3000:
Measure test parameters N/A IWV-352I:
Test frequency N/A IWV-352I:
Test frequency N/A IWV-3521:
Test frequency N/A IWV-3520:
Test method and frequency ALTERNATE METHOD OF TESTING ACTION BY USN RC Measure inlet and Components covered discharge pressure, are not ASME Code vibration, calculate Class.
fl ow rate.
Request not evaluated in SE/TER.
- Monitor discharge Components covered pressure monthly.
are not ASME Code Class.
Request not evaluated in_
SE/TER.
Measure vibration.
Components cGvered Measure lube oil are not ASME Code heaser pressure and Class.
oil temperature for Request not proper pump evaluated in operation.
SE/TER.
Part-stroke exercise Preapproved
~uarterly, GL 89-04, ull-stroke exercise request not each RO.
evaluated in SE/TER.
Full-stroke exercise Preapproved each RO.
GL 89-04, request not evaluated in SE/TER.
Manually full -stroke PreaBproved exercise each RO.
Gl 8 -04, request not evaluated in SE/TER.
Manually full-stroke PreaGproved exercise each RO.
GL 8 -04, request not evaluated in SE/TER.
Page No.
07/31/92 e
e 5
RELIEF REQUEST IDENTIFICATION Rev. 2, dated 10/03/89, Unit 1 AF valve:
1AF72 Rev. 2, dated 10/03/89, Unit 1~2] AF valves:
ll-14A 921
[21-24AF921]
Rev. 2, dated 10/03/89, Unit 1[2] Control Air (CA! valves:
11 12CA360
[21 & 22CA360]
Rev. 2, dated 10/03/89, Unit 1 Component Cooling (CC) valves:
1CC118[2CC118]
Rev. 2, dated 10/03/89, Unit lf21 CC valves:
1CC119 2CC119]
Rev: 2, dated 10/03/89, Unit 1(2] CC valves:
ll-14CC128
[21-24CC128]
Rev. 2, dated 10/03/89, Unit 1[2] CC valves:
1CC131 & 1CC136
[2CC131 & 2CC136]
SALEM GENERATING STATION, UNITS 1 AND 2 SAFETY EVALUATION TABLE 1
SUMMARY
OF RELIEF REQUESTS TER SECTION XI SECTION REQUIREMENT
& SUBJECT N/A IWV-3520:
Test method and frequency N/A IWV-3521:
Test frequency N/A IWV-3521:
Test frequency N/A IWV-3410:
Test frequency N/A IWV-3521:
Test frequency N/A IWV-3521:
Test frequency N/A IWV-3521:
Test frequency ALTERNATE METHOD OF TESTING ACTION BY USN RC Manually full-stroke Preapproved exercise each RO.
GL 89-04, request not evaluated in SE/TER.
Full-stroke exercise Preapproved each RO.
GL 89-04, request not evaluated in SE/TER.
Full-stroke exercise Preapproved each RO.
GL 89-04, request not.-
evaluated in~
SE/TER.
Exercise during cold Preapproved shutdown (CS) with GL 89-04, RCPs secured and request not each RO.
evaluated in SE/TER.
Full-stroke exercise Preapproved during CS with RCPs GL 89-04, secured and each RO. request not evaluated in SE/TER.
Full-stroke exercise Preapproved each RO.
GL 89-04, request not evaluated in SE/TER.
Full-stroke exercise Preapproved during CS with RCPs GL 89-04, secured and each RO. request not evaluated in SE/TER.
Page No.
07 /31/92 6
RELIEF REQUEST IDENTIFICATION Rev. 2, dated 10/03/89, Unit lf2l CC valves:
1CC186 2CC186]
Rev. 2, dated 10/03/89, Unit 1(2] CC valves:
1CC187 & 1CC190
[2CC187 & 2CC190]
Rev. 2, dated 10/03/89, Unit lf 21 CC valves:
1CC208 2CC208]
SALEM GENERATING STATION, UNITS 1 AND 2 SAFETY EVALUATION TABLE 1
SUMMARY
OF RELIEF REQUESTS TER SECTION XI SECTION REQUIREMENT
& SUBJECT N/A IWV-3521:
Test frequency N/A IWV-3521:
Test frequency N/A IWV-3521:
Test frequency ALTERNATE METHOD OF TESTING ACTION BY USN RC Full-stroke exercise Preapproved open during CS with GL 89-04, RCPs secured and request not each RO.*
evaluated in SE/TER.
Exercise during CS Pre approved with RCPs secured GL 89-04, and each RO.
request not evaluated in SE/TER.
Full-stroke exercise PreaGproved open duri nV CS.
GL 8 -04, Exercise c osed request not
-~
during each RO.
evaluated in
- SE/TER.
Rev. 2, dated 10/03/89, N/A IWV-3521:
Full-.stroke exercise Preapproved each RO.
GL 89-04, Unit 1 Containment Spray Test (CS! valves:
frequency request not 11 12CS4 evaluated in (21 & 22CS4]
SE/TER.
Rev. 2, dated 10/03/89, N/A IWV-3521:
Full-stroke exercise Preapproved Unit 1(2]. CS valves:
Test each RO.
GL 89-04, 11 & 12CS48 frequency request not (21 & 22CS48]
evaluated in SE/TER.
Rev. 2, dated 10/03/89, N/A IWV-3521:
Part-stroke exercise Preapproved Unit 1A2l CV valves:
Test quarterly and during GL 89-04, 1CV47 CV52 frequency CS, full-stroke request not
[2CV47 & 2CV52]
exercise each RO.
evaluated in SE/TER.
Rev. 2, dated 10/03/89, N/A IWV-3521:
Full-stroke exercise Preagproved Unit lf 21 CV valves:
Test open duriny CS,-
GL 8 -049 1CV296 2CV296]
frequency exercise c osed each request not RO.
evaluated in SE/TER.
Page No.
07 /31/92 7
RELIEF REQUEST IDENTIFICATION Rev. 2, dated 10/03/89, Unit 1[2] Diesel Engine Auxiliary ~DA~ valves:
1DA36A, 36,
36C
[2DA36A, 368, & 36C]
Rev. 2, dated 10/03/89, Unit 1[2j DA valves:
- 1DA70A, OB, & 70C
[2DA70A, 70B, & 70C]
Rev. 2, dated 10/03/89, Unit lf 2~ Residual Heat Remova RH) valves:
11 & 12RH8
[21 & 22RH8]
Rev. 2, dated 10/03/89, Unit 1[2] RH valves:
13 & 14RH27
[23 & 24RH27]
Rev. 2, dated 10/03/89, Unit 1[2] Station Air (SA) valves:
1SA119[2SA119]
Rev. 2, dated 10/03/89, Unit 1[2] Safety Injection (SJ) valves:
1SJ3
[2SJ3]
Rev. 2, dated 10/03/89, Unit 1~2j SJ valves:
ll-14S 1
[21-24SJ17]
SALEM GENERATING STATION, UNITS 1 AND 2 SAFETY EVALUATION TABLE 1
SUMMARY
OF RELIEF REQUESTS TER SECTION XI SECTION REQUIREMENT
& SUBJECT N/A IWV-3522:
Test method N/A IWV-3510:
Test method and frequency N/A IWV-3521:
Test frequency N/A IWV-3521:
Test frequency N/A IWV-3521:
Test frequency N/A IWV-3521:
Test frequency N/A IWV-3521:
Test frequency ALTERNATE METHOD OF TESTING ACTION BY USN RC Monitor lube oil Preapproved temperature and flow GL 89-04, for verification of request not opening.
evaluated in SE/TER.
None.
Components covered are not ASHE Code Class.
Request not evaluated in SE/TER.
Part-stroke exercise Preapproved
- quarterly and during GL 89-04,
-~
cold shutdowns, and request not.
full-stroke exercise evaluated in each RO.
SE/TER.
Full-stroke exercise Preapproved each RO.
GL 89-04, request not evaluated in SE/TER.
Full-stroke exercise Preapproved each RO.
GL 89-04, request not evaluated in SE/TER.
Full-stroke exercise PreaGproved o~en and verify GL 8 -04, c osure each RO.
request not evaluated in SE/TER.
Part-stroke exercise Preapproved during CS and GL 89-04, full-stroke exercise request not each RO.
evaluated in SE/TER.
8 Page No.
07 /31/92 SALEM GENERATING STATION, UNITS 1 AND 2 SAFETY EVALUATION TABLE 1
SUMMARY
OF RELIEF REQUESTS RELIEF REQUEST IDENTIFICATION TER SECTION XI SECTION REQUIREMENT
& SUBJECT Rev. 2, dated 10/03/89, N/A Unit 1[2] SJ valves:
1SJ31[2SJ31]
Rev. 2, dated 10/03/89, N/A Unit lr21 SJ valves:
11 & 12SJ34
[21 & 22SJ34]
Rev. 2, dated 10/03/89, N/A Unit 1(2] SJ valves:
ll-14SJ43
[21-24SJ43]
Rev. 2, dated 10/03/89, N/A Unit 1[2] SJ valves:
1SJ150
[2SJ150]
Rev. 2, dated 10/03/89, N/A Unit 1[2] SJ valves:
ll-14.SJ156
[21-24SJ156]
IWV-3521:
Test frequency IWV-3521:
Test frequency IWV-3521:
Test frequency IWV-3521:
. Test frequency IWV-3521:
Test frequency ALTERNATE METHOD OF TESTING ACTION BY USN RC Part-stroke exercise Preapproved quarterly and GL 89-04, full-stroke exercise request not each RO.
evaluated in SE/TER.
Full-stroke exercise Preapproved each RO.
GL 89-04, request not evaluated in SE/TER.
Part-stroke exercise Preapproved -
during cold GL 89-04, shutdowns, request not :
full-stroke exercise evaluated in each RO.
SE/TER.
Full-stroke exercise Preapproved each RO.
GL 89-04, request not evaluated in SE/TER.
Full-stroke exercise Preapproved each RO.
GL 89-04, request not evaluated in SE/TER.
Rev. 2, dated 10/03/89, 3.8.1.3 Unit 1(2] SW valves:
IWV-3520:
Part-stroke exercise Interim Relief Granted 11 & 12SW79
[21 & 22SW79]
Rev. 2, dated 10/03/89, App. A Unit 1[2] Ventillation Containment (VC) valves:
lVCl & 1VC4
[2VC1 & 2VC4]
Test method quarterly. Inspect and frequency the valves during cold shutdowns.
Full-stroke exercise will not be done.
(g){6)( i), with provisions, for one year or until the next RO.
IWV-3410:
Test frequency The valves will be Preapproved tested when they are GL 89-04, operated, at no request not specific frequency.
evaluated in SE/TER.
Page No.
07/31/92 9
RELIEF REQUEST IDENTIFICATION SALEM GENERATING STATION, UNITS 1 AND 2 SAFETY EVALUATION TABLE 1
SUMMARY
OF RELIEF REQUESTS TER SECTION XI SECTION REQUIREMENT
& SUBJECT ALTERNATE METHOD OF TESTING ACTION BY USN RC Rev. 2, dated 10/03/89, App. A Unit 1[2] VC valves:
IWV-3410 &
The valves will be
-3420:
tested per Technical Preapproved GL 89-04, request not evaluated in SE/TER.
1VC2 & 1VC3
[2VC2 & 2VC3]
Test method Specifications (TS) and frequency at no specific frequency.
Rev. 2, dated 10/03/89, App. A IWV-3420:
Unit 1[2] VC valves:
Test method 1VC6[2VC6]
The valves will be Preapproved leak tested in the GL 89-04, opposite direction request not (to functional evaluated in direction). The test SE/TER.
frequency will be per TS.