ML17285B357

Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions.

ML17285B357
Person / Time
Site:	Columbia
Issue date:	06/28/1990
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-90-04, GL-90-4, GO2-90-113, TAC-75993, NUDOCS 9007050192
Download: ML17285B357 (23)

Text

ACCELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9007050192 DOC.DATE: 90/06/28 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Responds to Generic Ltr 90-04 re status of implementation of GSIs.

DISTRIBUTION CODE A018D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Generic Ltr 90-04 re Status of Licensee Implementation of Generic Saf NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 SAMWORTH, R 2 2 INTERNAL: CROCKER,L 9H3 1 1 ECC ON,K10D4 1 1 NUDOCS-ABSTRACT 1 1 G 2IZE 01 1 1 SCHOLL,R 13E4 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDI TOTAL NUMBER OF COPIES REQUIRED: LTTR 11 ENCL 11

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 June 28, 1990 G02-90-113 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 RESPONSE TO GENERIC LETTER 90-04 REGARDING STATUS OF IMPLEMENTATION OF GENERIC SAFETY ISSUES (TAC NO. 75993)

Reference:

Generic Letter 90-04, "Request for Information on the Status of Licensee Implementation of Generic Safety Issues Resolved with Imposition of Requirements or Corrective Actions", dated April 25, 1990 In the reference we were requested to review and provide documentation of the current implementation status of Generic Safety Issues (GSIs) identified in the reference. This was to be completed by June 29, 1990.

Our response to this request is the attached marked up copy of the table included with the reference (Attachment 1 of this response) and the list of notes for this marked up table (Attachment 2).

As noted in Attachment 1, implementation is complete for all of the applicable GSIs with the exception of the following:

51/L913, Reliability of Open-Cycle Service Mater Systems (response to GL 89-13 remains to be completed).

75/L003, Vendor Interface for Safety-Related Components (GL 90-03 under review).

Page Two RESPONSE TO GENERIC LETTER 90-04

~ 75/B093, .Reactor Trip System Reliability (NRC issuance of surveillance intervals, Technical Specification change required).

~ 67.3.3/A017, Improved 'Accident Monitoring (NRC issuance of Wide Range Neutron Monitor Technical Specification change required).

Very truly yours, G. C..Sorensen, Manager Regulatory Programs AGH/bk Attachments cc: JB Martin - NRC RV NS Reynolds - BCP8R PL Eng - NRC DL Williams - BPA/399 NRC Site Inspector - 901A

FACILITY NAME:

DOCKET NO.:

LICENSEE:

STATUS OF LICENSEE IHPLEHENTATION OF GENERIC SAFETY ISSUES

'RESOLVED WITH IMPOSITION OF RE UIREHENTS OR CORRECTIVE ACTIONS GS I/ HPA No. TITLE APPLICABILITY STATUS* COMMEN 40 (B065) Safety Concerns Associated With All BWRs Pipe Breaks In The BWR Scram System 41 (B058) BWR Scram Discharge Volume Systems All BWRs 43 (8107) Reliability Of Air Systems All Plants 51 (L913) Improving the Reliability of All Plants I (See Attachment 2 for Open-Cycle Service Water Systems schedule and cxxments) 67.3.3 (A017) Improved Accident Monitoring All Plants I (See Attachment 2 for schedule and coaments) 75"* (8076) Item 1.1 - Post-Trip Review All Plants ***

C (Program Description and Procedure) 75 (8085) Item 1.2 - Post-Trip Review- All Plants Data and Information Capability "Please follow attached guidance for completing this column.

""The 16 items listed for GSI 75 all relate to actions derived from the generic implications of Salem ATWS events. Item numbers correspond to Generic Letter 83-28 action item numbers.

• • • See Attachment 2 for coments

NNP-2 ATTACHMENT l 50-397 Supply System GSI/ MPA No. TITLE APPLICABILITY STATUS* COMMENTS 75 (8077) Item 2. 1 - Equipment Classi- Al 1 Plants fication and Vendor Interface (Reactor Trip System Components) 75 (8086) Item 2.2. 1 - Equipment Classifi- All Plants cation for Safety-Related Components 75 (L003) Item 2.2.2 - Vendor Interface Al 1 Pl ants E (See Attachment 2 for for Safety-Related Components schedule and coaaents) 75 (8078) Items 3.1.1 8 3.l.2 - Post- Al 1 P 1 ants Maintenance Testing (Reactor Trip System Components) 75 (8079) Item 3. 1.3 - Post-Maintenance All Plants Testing-Changes to Test Require- 4 ments (Reactor Trip System Components) 75 (8087) Items 3.2.1 8 3.2.2 - Post- All Plants Maintenance Testing (All Other Safety-Related Components) 75 (8088) Item 3.2.3 - Post-Maintenance All Plants Testing-Changes to Test Require-ments (All Other Safety-Related Components) 75 (8080) Item 4. 1 - Reactor Trip System Al 1 Plants N/A Reliability (Vendor-Related Modifications)

ATTACHMENT 1 NNP 2 50-397 Supply System GSI/ HPA Ho. APPLICABILITY STATUS* COHHEHTS 75 (B081) Items 4. 2 ~ 1 8 4. 2. 2 - Reac tor All PWRs N/A Trip System Rel iabil i ty-Haintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (B082) Item 4.3 - Reactor Trip System All M and B&W N/A Reliability - Oesign Hodifications Plants (Automatic Actuation of Shunt Trip Attachment for Mestinghouse and 88M Plants) 75 (B090) Item 4.3 " Reactor Trip System Al l W & 88W N/A Reliability - Tech Spec Changes Plants (Automatic Actuation of Shunt Trip Attachment For Westinghouse and B8M Plants) 75 (8091) I tern 4. 4 - Reac tor Tri p Sys tern All D8W Plants. N/A Reliability (Improvements in Haintenance and Test Procedures for B&W Plants)

1 WNP-2 50-397 System'TTACHMENT Sugply 4

GSI/ HPA No. TITLE APPLICABILITY STATUS" COHHENTS 75 (8092) Item 4.5 ~ 1 - Reactor Trip System All Plants Reliability-Diverse Trip Features (System Functional Testing) 75 (8093) Items 4.5.2 & 4.5.3 - Reactor Trip All Plants ***

System Reliability - Test Alterna- I tives and Intervals (System Functional Testing) 86 (B084) Long Range Plan for Oealing Al 1 BWRs with Stress Corrosion Cracking in BWR Piping 93 (8098) Steam Binding of Auxiliary All PWRs N/A Feedwater Pumps 99 (L817) RCS/RHR Suction Line Valve All PWRs N/A Inter lock on PWRs 124 Auxiliary Feedwater System AN0-182, Rancho Rel iabi i ty 1 Seco, Prairie N/A Island 182, Crystal River-3 Ft. Calhoun A"13 (8017) Snubber Operability Assurance- All Plants "Hydraulic Snubbers

ATTACHMENT 1 NNP-2 50-397 Supply System GS I/ HPA No. ) T ITLE APPLICABILITY STATUS* COMMENTS A-13 (B022) Snubber Operab'ility Assurance-All Plants Hechanical Snubbers A-16 (D012) Steam Effects on BWR Core Oyster Creek N/A Spray Distribution 8 NHP-1 A-35 (B023) Adequacy of Offsite Power Al 1 Plants Systems Behavior of BWR Hark III All BWR Hark III N/A Containments Plants B-36 Develop Design, Testing and All Plants with N/A Haintenance Criteria for OL Applications Atmosphere Cleanup System After 4/1/80 Air Filtration and Adsorption Units for Engineered Safety Features Systems and for Normal Ventilation Systems 8-63 (8045) Isolation of Low Pressure Al 1 Plants ***

Systems Connected to the Reactor Coolant System Pressure Boundary

ATTACHMENT 2 NOTES FOR GL 90-04 RESPONSE

~GSI MPA Comment 40/8065 In Reference 1) below the NRC presented this concern to the Supply System for WNP-2. Our responses were provided in References 2) through 5).

In Supplement 3 to the WNP-2 SER for the OL (NUREG-0892) on page 4-4 it is stated that the staff concludes that the Supply System had adequately addressed the concerns of the May 1981 AEOD report titled, "Safety Concerns Associated with a Pipe Break in the BWR Scram System". This is the AEOD report that GSI No. 40 references (through the April 10, 1981 Generic Letter [GL 81-20]) as the document defining the concerns to be resolved. Reference 6) provided additional information subsequent to the issuance of SER Supplement 3. We do not see that it changes the conclusions reached in the SER supplement.

All actions necessary to resolve the concern for the effects of pipe breaks in the WNP-2 Scram System have been implemented.

References

1) Letter, RL Tedesco (NRC) to RL Ferguson (SS), "Safety Concerns Associated with Pipe Breaks in the BWR Scram System", dated April 24, 1981.

2) Letter, G02-82-27, GD Bouchey to A Schwencer, "Responses to Request for Information", dated January 13, 1982.

3) Letter, G02-82-395, GD Bouchey to A Schwencer, "NUREG-0803",

dated April 22, 1982.

4) Letter, G02-82-975, GD Bouchey to A Schwencer, "Response to NRC guestion 010.066, NUREG-0803", dated December 9, 1982.

5) Letter, G02-83-091, GD Bouchey to A. Schwencer, "Response to NRC guestion 010.066, NUREG-803", dated February 3, 1983.

6) Letter, G02-83-1042, GC Sorensen to A Schwencer, "Generic Safety Evaluation Report BWR Scram Discharge System, Dated December 1, 1980", dated November ll, 1983.

41/B058 In the WNP-2 SER'dated March 1982, it is stated on Page 7-6 that modifications to the WNP-2 design satisfies the concern identified by the staff relating to scram discharge volume level sensing. No changes remain to be implemented.

43/B107 In the references below the Supply System responded to GL 88-14 for WNP-2. The September 15, 1989 letter did identify six potential enhancements that were to be evaluated for possible implementation.

As we do not believe any of these enhancements are required for resolution of the concerns raised in GL 88-14, we consider our response to the generic letter closed and all required changes implemented.

References

1) Letter, G02-89-128, GC Sorensen (SS) to NRC, "Final Response to Generic Letter 88-14 Instrument Air Supply System Problems Affecting Safety-Related Equipment", dated July 28, 1989.

2) Letter, G02-89-170, GC Sor ensen (SS) to NRC,"Response to GL 88-14 Instrument Air Supply System Problems Affecting Safety-Related Equipment, Follow-Up Report", dated September 15, 1989.

3) Letter, G02-90-063, GC Sorensen (SS) to NRC,"Response to Generic Letter 88-14, Instrument Air Supply System Prob'.ems Affectin Safety-Related Equipment, Concluding Report (TAC No.71741)", dated Harch 29, 1990.

51/L913 The Supply System's response to Generic Letter 89-13 was provided in Reference 1) below. Various activities relative to the generic letter remain to be completed as discussed in this reference.

The longest term open item addressed in the reference is the installation of a corrosion coupon system in our spring 1991 refueling outage (Part III.4 of the reference).

However, a design study to evaluate the potential need for biologi-cal control of the service water pond water to be concluded by September 1990 (Part I. 1 of the reference) may identify the need for a design change whose implementation will extend beyond the spring 1991 outage.

This GSI remains to be fully implemented for WNP-2.

Reference

1) Letter, G02-90-017, GC Sorensen (SS) to NRC, "Response to Generic Letter 89-13, Service Water Problems Affecting Safety-Related Equipment", dated February 5, 1990.

67.3.3/A017 In Reference 1) below, the NRC provided an SER for Regulatory Guide 1.97, Revision 2, implementation at WNP-2. In References 2) and 3),

we responded to NRC request for additional information for this SER.

In Reference 4) the NRC replied to References 2) and 3) by stating that our response to Generic Letter 82-33 and NRC review of conformance to Regulatory Guide 1.97 was closed.

Reference 4) did acknowledge that the requirements for a qualified post-accident neutron flux monitoring capability remained open as a license condition. In Reference 5), we documented closure of this license condition.

A remaining action on the NRC's part is to respond to the Technical Specification change request of Reference 5) relative to the wide range neutron monitor. In Reference 6) the NRC agreed that the license condition was closed.

The issuance of the Technical Specification change and the incorpo-ration of the change into our processes remain to be implemented.

References

1) Letter, WR Butler (NRC) to GC Sorensen (SS), "Emergency Response Capability - Conformance to Regulatory Guide 1.97, Revision 2", dated August 9, 1985.

2) Letter, G02-85-710, GC Sorensen (SS) to NRC, "Emergency Response Capability - Conformance to Regulatory Guide 1.97, Revision 2", dated October.8, 1985.

3) Letter, G02-86-097, GC Sorenson (SS) to NRC, "Emergency Response Capability - Conformance to Regulatory Guide 1.97, Revision 2, Clarification", dated January 23, 1986.

4) Letter, GW Knighton (NRC) to GC Sorenson (SS), "Emergency Reponse Capability - Conformance to Regulatory Guide 1.97, Revision 2, (TAC No. 59516)", dated Harch 23, 1988.

5) Letter, G02-89-109, GC Sorensen (SS), "Satisfaction of License Condition 2.C(16) Attachment 2, Item 3(b), Wide Range Neutron Honitor", dated June 15, 1989.

6) Letter, R.B. Samworth (NRC) to GC Sorensen (SS), "Satisfaction of License Condition 2.c.(16), Attachment 2, Item 3.(b) Flux Honitoring (TAC No. 73415)", dated Hay 2, 1990.

75/B076 Generic Letter 83-28, Item 1.1 We responded to this item in Reference 1). In References 2) and

3) the NRC found this response to be acceptable.

References

1) Letter, G02-83-1076, GC Sorensen (SS) to A Schwencer, "Re-sponse to Generic Letter 83-28", dated November 18, 1983.

2) "Letter, MR Butler. (NRC) to GC Sorensen (SS), "WNP-2 Generic Letter GL 83-28, Item 1.1, Post-Trip Review (Program Descrip-tion and Procedure)", dated May 17, 1985.

3) .

Letter, WR Butler (NRC) to GC Sorensen (SS), "WNP-2 Generic Letter GL 83-28, Item 1. 1, Post-Trip Review (Program Descrip-tion and Procedure)", dated Hay 24, 1985.

75/B085 Generic Letter 83-28, Item 1.2 We responded to this item in Reference 1) of Item 1. 1 and in a telecon on Hay 16, 1985 which is discussed in Reference 1) below. In Reference 2) the NRC found our response to this item acceptable.

References

1) Letter, WR Butler (NRC) to GC Sorensen (SS), "Draft Technical Evaluation Report (TER) for Salem ATMS Item 1.2, GL 83-28",

dated Nay 22, 1985.

2) Letter, WR Butler (NRC) to GC Sorensen (SS), "WNP-2 Generic Letter 83-28, Item 1.2, Post-Trip Review (Data and Information Capability)", dated June 10, 1985.

75/B077 Generic Letter 83-28, Item 2. 1 Part 1. We responded to this part in Reference 1) of Item 1. 1 and Reference 1) below. In Reference 2) the NRC responded that our response to this item was found acceptable.

Part 2. Me provided responses to this part in Reference 1) of Item

1. 1 and Reference 1) below. In Reference 3) the NRC states:that they believe Part 2 of Item 2. 1 to be closed.

References

1) Letter, G02-85-257, GC Sorensen (SS) to WR Butler (NRC),

4

"Generic Letter 83-28, Additional Information", dated Hay 17, 1985.

2) Letter, RB Samworth (NRC) to GC Sorensen (SS), "Closeout of Two Generic Letter 83-28 Items (TAC Nos. 57805 and 53730)",

dated November 30, 1988.

3) Letter, RB Samworth (NRC) to GC Sorensen (SS), "Safety Evaluation Report for Generic Letter 83-28 Item 2. 1 (Part 2)

(Vendor Interface Programs - RTS Components) for WNP-2 (TAC No. 60758)", dated February 16, 1989.

75/B086 Generic Letter 83-28, Item 2.2. 1 We responded to this item in References 1) and 2) of Item 1. 1. In Reference 2) of Item 2. 1 the NRC states that our response was acceptable.

75/L003 With the recent issuance of Generic Letter 90-03 concerning Part 2 of this item, we consider the implementation of this GSI remains to be completed. Our response to this generic letter is due to the NRC September 24, 1990. By this date we should know the schedule for any remaining activities.

75/B078 Generic Letter 83-28, Items 3.1.1 and 3.1.2 We responded to these items in Reference 1) of Item 1. 1 and in References 1) and 2) below. In, Reference 3) the'RC found our response to these two items acceptable.

References Letter, GC Sorensen (SS) to WR Butler (NRC), "NRC Generic Letter 83-28, Request for Additional Information", dated July 3, 1985.

2) Letter, G02-85-702, GC Sorensen (SS) to WR Butler (NRC), "NRC Generic Letter 83-28, Supplementary Information", dated October 7, 1985.

3) Letter, E Adensam (NRC) to GC Sorensen (SS), "Safety Evalua-tion for Generic Letter 83-28, Post-Haintenance Testing, Items

3. 1.1 and 3. 1.2 (Reactor Trip System Components) and Items 3.2.1 and 3.2.2 (All Other Safety-Related Components) for WNP-2",, dated December 3, 1985 (reissued December 13, 1985).

75/B079 Generic Letter 83-28, Item 3.1.3 We responded to this item in Reference 1) of Item 1. 1. In Reference

1) below the NRC found our response to this item acceptable.

Reference

1) Letter, WR Butler (NRC) to GC Sorensen (SS), "Safety Evalua-tion for Generic Letter 83-28, Post-Maintenance Testing, Item

3. 1.3 (Reactor Trip System Components) and Item 3.2.3 (All Other Safety-Related Components) for WNP-2", dated September 3, 1985.

75/8087 Generic Letter 83-28, Items 3.2. 1 and 3.2.2 We responded to these two items in Reference 1) of Item 1. 1 and Reference 2) of Items 3. 1.1 and 3. 1.2. In Reference 2) of these two items the NRC found our response to Items 3.2.1 and 3.2.2 accept-able.

75/B088 Generic Letter 83-28, Item 3.2.3 We responded to the item in Reference 1) of Item 1.1. In Reference

1) of Item 3. 1.3, the NRC found this response acceptable.

75/8080 Generic Letter 83-28, Item 4.1 While GL 90-04 indicates'this applies to all plants, GL 83-28 states it only applies to PWRs. We believe GL 83-28 is correct as BWRs do not use reactor trip breakers.

75/B092 Generic Letter 83-28, Item 4.5.1 We responded to this item in Reference 1) of 'Item 1. 1. In Reference

1) below the NRC found the WNP-2 design features to deal with this issue acceptable.

Reference

1) Letter, WR Butler (NRC) to GC Sorensen (SS), "WNP-2 Generic Letter 83-28, Item 45. 1, On-Line Functional Testing of Pilot and Backup Scram Valves", dated July 3, 1985.

75/B093 Generic Letter 83-28, Items 4.5.2 and 4.5.3 We provided our response to Item 4.5.2 in Reference 1) of Item 1. 1 and a telecon with the staff on April 4, 1989. In Reference 1) the NRC states that with these responses they considered Item 4.5.2 closed for WNP-2.

We provided responses to Item 4.5.3 in References 1) and 2) of Item

1. 1, and Reference 2) below. In Reference 3) the NRC concluded that Item 4.5.3 was complete for WNP-2. However, NRC issuance of the Technical Specification change request of Reference 2) regarding optimized RPS surveillance intervals remains to be issued.

References

1) Letter, RB Samworth (NRC) to GC Sorensen (SS), "Closeout of Generic Letter 83-28 Item 4..5.2 (TAC No. 54040)", dated April 25, 1989.

2) Letter, G02-89-161, GC Sorensen (SS) to Document Control Desk (NRC), "Request for Amendment to Technical Specification 3/4.3.1 Reactor Protection System Instrumentation and Closeout of Item 4.5.3 of Generic Letter 83-28", dated September 14, 1989.

3) Letter, RB Samworth (NRC) to GC Sorensen (SS), "Safety Evaluation for Generic Letter 83-28, Item 4.5.3, Reactor Trip Reliability -- On-Line Functional Testing of the Reactor Trip System (TAC No. 54040)", dated October 3, 1989.

86/B084 The Supply System responded to NUREG-0313 Revision 1 and Generic Letter 84-11 in References 1 and 2 below respectively. Those changes identified in these two references have been implemented for WNP-2. References 3 and 4 concern open issues relative to Generic Letter 88-01, but Generic Letter 90-04 states that GL 88-01 is beyond the scope of GSI 86.

Refer~aces

1) Letter, G02-83-833, GC Sorensen (SS) to A Schwencer (NRC),

"Update on Implementation of NUREG-0313, Rev; I", dated September 14, 1983.

2) Letter, G02-84-364, GC Sorensen (SS) to D Eisenhut (NRC),

"Supply System's Response to NRC's Generic Letter 84-11",

dated Hay 30, 1984.

3) Letter, GI2-89-44, RB Samworth (NRC) to GC Sorensen (SS),

"Generic Letter 88-01 Response, Request for Additional Information", Hay 16, 1990.

4) Letter, G02-88-164, GC Sorensen (SS) to NRC, "Supply System's Response to NRC's Generic Letter 88-01", dated July 26, 1988.

A-13/B017 The WNP-2 Technical Specifications were issued by the NRC on December 20, 1983 which was subsequent to the November 20, 1980 NRC letter mentioned in Generic Letter 90-04. As such, we assume the NRC's concerns for snubber operability assurance were adequately addres'sed in the Technical Specifications as issued by the NRC.

A-13/B022 See above note for A-13/B017 A-16/D012 Generic Letter 90-04 states no actions were requested of BWR 3, 4

and 5s.

A-35/B023 The original WNP-2 SER issued in March, 1982 (NUREG-0892) discussed the NRC review of WNP-2 against BTP PSB-1 (referenced in Generic Letter 90-04) in Section 8.4.4 (Pages 8-16). Concerns for the WNP-2 design are mentioned for which the staff found commitments by the Supply System adequate to resolve these concerns. The need for a license condition and FSAR revision are mentioned. This was included in Section 1.7 of the SER as "open" in Item 14. The.

Supply System amended the FSAR to address this concern (including a change to the response to guestion 040.36) in June 1982. In Supplement No. 3 of the SER issued in May 1983, this is an item documented as being resolved.

B-36 The WNP-2 application was submitted for acceptance review on March 17, 1978 and, having passed this process, formal docketing occurred on June 16, 1978.

B-63/B045 The issue of interfacing LOCAs was raised by the NRC during the WNP-2 OL review by guestion 040.079. No additional questions were raised, or license conditions established, relative to this issue prior to the issuance of the operating license.

In Reference 1 below the NRC raised a concern relative to fire-induced failure of a high/low pressure boundary. This was eventual-ly resolved by a change to the prior design which has been imple-mented as described in References 2) and 3).

References Letter, DF Kirsch (NRC) to GC Sorenson (SS), "Nonconformance of Safe Shutdown Equipment to Appendix R Requirements", dated June 7, 1985.

2) Letter, GL2-88-209, GC Sorenson (SS) to Document Control Desk (NRC), "Fire Protection and Safe Shutdown Capablity Response to Safety Evaluation Report (Revised Response to guestion No.

25)", dated September 30, 1988.

3) Letter, G02-88-214, GC Sorenson (SS) to JB Martin (NRC),

"Schedule for Completion of Fire Protection Issues (Inspection Report 88-16)", dated October 7, 1988.

ENCLOSURE 2 FACILITY NAME: WNP-2 DOCKET NO: 50-397 LICENSEE: Washington Public Power Supply System GSI Status Summary Licensee Staff GSI/MPA Status Status No. Titie Determination Determination Remarks 40 (B065) Safety Concerns SSER 83 Associated With Pipe Breaks In The BWR Scram System 41 (B058) BWR Scram Discharge NC SSER 5'2 Volume Systems 43 (B107) Reliability Of C 9/15/89 C 9/15/89 Air Systems 51 (L913) Improving the I 6/91 C 2/5/90 Licensee continuing to install Reliability of enhancements beyond the scope Open-Cycle Service of this GSI.

Water Systems 67.3.3 (A017) Improved Accident I 5/2/90 C 5/2/90 Licensee awaiting license Monitoring change which is related but beyond the scope of this GSI.

75** (B076) Item l.l - Post-Trip Review (Program C NC Description and Procedure)

-Licensee Staff GS I/HPA Status Status No. Tit1e Determination Determination Remarks 75 (B085) Item 1.2 - Post-Trip C 6/10/85 C 6/10/85 Review - Data and Information Capability 75 (B077) Item 2.1 - Equipment Classification and Vendor Interface (Reactor Trip System Components) 75 (8086) Item 2.2.1 - Equipment Classification for Sa fety-Re lated Components 75 (L003) Item 2.2.2 - Vendor Response to GL 90-03 due 9/24/90 Interface for Safety-Related Components 75 (B078) Items 3.1.1 & 3.1.2- C 10/7/85 C 10/7/85 Post - Maintenance Testing (Reactor Trip System Components)

Licensee Staff GSI/MPA Status Status No. Ti t1e Determination Determination Remarks 75 (B079) Item 3.1.3 - Post- C NC Maintenance Testing-Changes to Test Require-ments (Reactor Trip System Components) 75 (B087) Items 3.2.1 5 3.2.2 - C 10/7/85 C 10/7/85 Post-Maintenance Testing (All Other Safety-Related Components) 75 (8088) Item 3.2.3 - Post-Maintenance Testing - Changes to Test Requirements (All Other Safety-Related Components) 75 (B080) Item 4.1 - Reactor N/A N/A Trip System Reliability (Vendor-Related Modifications)

Licensee Staff GSI/HPA Status Status No. Title l Determination Determination Remarks 75 (B081) Items 4.2.1 5'4.2.2 - N/A N/A Reactor Trip System Re 1 iab i 1 i ty-Ha intenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) 75 (B082) Item 4.3 - Reactor N/A N/A Trip System Reliability-Design Modifications (Automatic Actuation of Shunt Trip Attachment for Westinghouse and B&W Plants) 75 (B090) Item 4.3 - Reactor N/A N/A Trip System Reliability-Tech Spec Changes (Automatic Actuation of Shunt Trip Attachment For Westinghouse and BSW Plants) 75 (B091) Item 4.4 - Reactor N/A N/A Trip System Reliability (Improvements in Maintenance and Test Procedures for BKW Plants)

Licensee Staff GSI/MPA Status Status No. Title Determination Determination Remarks 75 (B092) Item 4.5.1 - Reactor Trip System Rel iabi 1ity - Diverse Trip Features (System Functional Testing) 75 (B093) Items 4.5.2 5 4.5.3- I 10/3/89 C 10/3/89 Licensee awaiting related Reactor Trip license change which is beyond System Rel iabi1 ity- the scope of this GSI Test Alternatives and Intervals (System Functional Testing) 86 (B084) Long Range Plan for C 5/30/84 C 5/30/84 Dealing with Stress Corrosion Cracking in BWR Piping 93 (B098) Steam Binding of N/A N/A Auxiliary Feedwater Pumps 99 (L817) RCS/RHR Suction N/A N/A Line Valve Interlock on PWRs 124 Auxiliary Feedwater N/A N/A System Reliability A-13 (B017) Snubber Oper ability NC NC Assurance-

@draulic Snubbers

Licensee Staff GSI/MPA Status Status No. Ti tie Determination Determination Remar ks A-13 (8022) Snubber Operability NC Assurance - Mechanical Snubbers A-16 (D012) Steam Effects on BWR NA Core Spray Distribution A-35 (8023) Adequacy of Offsite NC FSAR question 040.36 (6/82)

Power Systems SSER 2 8-10 Behavior of BWR NA Mark III Containments B-36 Develop Design, NA Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsor ption Units for Engineered Safety Features Systems and for Normal Ventilation Systems

Licensee Staff GSI/HPA Status Status No. Tit'le Determination Determination Remarks 8-63 (8045) Iso1ation of Low FSAR gestion 040.079 Pressure Systems SSER 4 (12/83)

Connected to the Reactor Coo1ant System Pressure Boundary