ML17305A911

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Responds to Generic Ltr 90-04, Status of Implementation of Generic Safety Issues.
ML17305A911
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 06/25/1990
From: Conway W
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TASK-***, TASK-OR 161-03304-WFC-G, 161-3304-WFC-G, GL-90-04, GL-90-4, NUDOCS 9007050212
Download: ML17305A911 (26)


Text

ACCELERATED STRIBUTION DEMONSTPATION SYSTEM

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'EGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9007050212 DOC.DATE: 90/06/25 NOTARIZED: NO DOCKET FACIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME AUTHOR AFFILIATION CONWAY,W.F. Arizona Public Service Co. (formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Responds to Generic Ltr 90-04, "Status of Implementation of Generic Safety Issues. D DISTRIBUTION CODE: A018D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: Generic Ltr 90-04 re Status of Licensee mpleme tation of Generic Saf NOTES 05000528 Standardized plant. 05000529 Standardized plant. 05000530 D

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL D PD5 LA 1 1 PD5 PD 1 1 PETERSON,S. 2 2 CHAN,T 2 2 INTERNAL CROCKER i L 9H3 1 1 S 10D4 1 1 NUDOCS-ABSTRACT 1 1 EG FILE 01 1 1 SCHOLL,R 13E4 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NOTES D-D NOTE TO ALL "RIDS"'ECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 14

i 0 Arizona Public Service Company P.O. BOX 59999 ~ PHOENIX, ARIZONA850724999 WILLIAMF. CONWAY 161-CKG+-tIH'/GAM EXECUTIVEVICEPRESIDENT NUCLEAR June 25, 1990 Docket Nos. STN 50-528/529/530 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Reference:

NRC Letter to All Holders of Operating Licenses and Construction Permits for Nuclear Power Reactors, "Request for Information on the Status of Licensee Implementation of Generic Safety Issues Resolved With the Imposition of Requirements or Corrective Actions (Generic Letter 90-04)," dated April 25, 1990.

Dear Sirs:

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Units 1,2, and 3 Response to Generic Letter 90-04, Status of Implementation of Generic Safety Issues File: 90-010-026 In response to Generic Letter (GL) 90-04, APS is submitting a summary of the implementation status of generic safety issues (GSI's). The attached table lists the GSI's identified in GL 90-04 and provides the implementation status for each, as requested.

If there are any questions regarding this submittal, please call A.C. Rogers of my staff at (602) 340-4041 Sincerely, WFC/GAM/tas Attachment cc: D. H. Coe J. B. Martin T. L. Chan S. R. Peterson A. C. Gehr A. H. Gutterman 50070+0212 PDR ADOCK 0500052S PDC ppIS

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GSI/ Reference (MPA No.) Title Document(s) Status Comments 40 Safety Concerns NA (B065) Associated With Pipe Breaks In The BWR Scram System 41 BWR Scram Discharge NA (B058) Volume Systems 43 Reliability of IN 87-28 APS Letters to NRC:

(B107) Air Systems IN 87-28, Sup 1 I 161-01697 02/20/89 NUREG-1275 (All units) 161-01881 04/27/89 GL 88-14 102-01474 10/16/89 161-03061 05/06/90 Outstandin Work Pro ected Com letion Date

1. Simulator upgrade to include loss o instrument air scenario.

All units: 06/91

2. Revise procedures to require instrumen air dryer desicant to be replaced i event of high dew point.

All units: 07/90

C GSI/ Reference (MPA No.) Title Document(s) Status Comments

51. Improving the IEB 81-03 I APS Letters to NRC:

(L913) Reliability of Open- GL 89-13 (All Units) ANPP 23294 03/18/83 Cycle Service Water 161-02801 01/26/90 Systems Outstandin Work Pro ected Com letion Dates

1. Implement revised testing procedure tha demonstrates 'thermal performance an heat transfer capability of service wate systems Unit 1: 06/92 (3rd refueling)

Unit 2: 01/92 (3rd refueling)

Unit 3: 09/91 (2nd refueling)

2. Add additional tasks to the PM program-Unit 1: 06/92 (3rd refueling)

Unit 2: 01/92 (3rd refueling)

Unit 3: 09/91 (2nd refueling)

3. Perform design review of service wate systems and perform as-built walkdo inspections-Unit 1: 06/92 (3rd refueling)

Unit 2: 01/92 (3rd refueling)

Unit 3: 09/91 (2nd refueling)

4. Review service water system training-All units: 09/91

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GSI/ Reference (MPA No.) Title Document(s) Status Comments/APS Letters to NRC 67.3.3 Improved Accident R. G. 1.97, R2 C ANPP-23505 04/14/83 (A017) Monitoring GL 82-33 (All Units) ANPP-24121 06/17/83 ANPP-30092 08/30/84 ANPP-31334 12/05/84 75 Generic Implications GL83-28 of ATWS Events at NUREG-1000, the Salem Nuclear Vol 1 & 2 Plant 75 Item 1.1 - Post-Trip C ANPP-32455 04/19/85 (B076) Review (Program (All Units)

Description and Procedure) 75 Item 1.2 - Post-Trip C ANPP-28167 ll/03/83 (B085) Review - Data and (All Units)

Information Capabili 75 Item 2.1 - Equipment C ANPP-28167 ll/03/83 (B077) Classification and (All Units) ANPP-35938 04/03/86 Vendor Interface 161-00507 09/15/87 (Reactor Trip System Components)

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GSI/ Reference (MPA No.) Title Document(s) Status Comments/APS Letters to NRC 75 Item 2.2.1- GL 90-03 C ANPP-28167 11/03/83 (B086) Equipment Classifi- (All Units) ANPP-35938 04/03/86 cation for Safety- 161-00507 09/15/87 Related Components 75 Item 2.2.2 - Vendor GL 90-03 C ANPP-.30778 10/09/84 (L003) Interface for Safety- INFO 84-010 (All Units) ANPP-35938 04/03/86 Related Components 75 Items 3.1.1 6 3.1.2- C ANPP-28167 ll/03/83 (B078) Post-Maintenance (All Units)

Testing (Reactor Trip System Components) 75 Item 3.1.3 - Post- C ANPP-28167 11/03/83 (B079) Maintenance Testing- (All Units)

Changes to Test Requirements (Reactor Trip System Components) 75 Items 3.2.1 & 3.2.2- C ANPP-28167 11/03/83 (B087) Post-Maintenance (All Units) ANPP-31523 12/18/84 Testing (All other ANPP-32455 04/19/85 Safety-Related Components)

i GSI/ Reference (MPA No.) Title Document(s) Status Comments/APS Letters to NRC 75 Item 3.2.3 - Post- C ANPP-28167 ll/03/83 (B088) Maintenance Teseing- (All Units)

Changes to Test Requirements (All other Safety-Related Components) 75 Item 4.1 - Reactor C ANPP-28167 11/03/83 (B080) Trip Syst: em (All Units) ANPP-35939 04/03/86 Reliability (Vendor-Related Modifi-cations) 75 Items 4.2.1 & 4.2.2- C ANPP-28167 11/03/83 (B081) Reactor Trip System (All Units) ANPP-32455 04/19/85 Reliability- ANPP-35939 04/03/86 Maintenance and Testing (Preventive Maintenance and Surveillance Program for Reactor Trip Breakers) 75 Item 4.3 - Reactor NA (B082) Trip System Reliability - Design Modifications (Automatic Actuation of Shunt Trip Attach-ment for Westinghouse and B & W Planes)

~ i GSI/ Reference (MPA No.) Title Document(s) Status Comments/APS Letters to NRC 75 Item 4.3 - Reactor NA (B090) Trip System Reliability - Tech Spec Changes (Automatic Actuation of Shunt Trip Attach-ment for Westinghous and B & W Plants) 75 Item 4.4 - Reactor NA (B091) Trip System Reliability-(Improvements in Maintenance and Test Procedures for B & W Plants) 75 Item 4.5.1 - Reactor C ANPP-28167 ll/03/83 (B092) Trip System (All Units) ANPP-32455 04/19/85 Reliability - Divers Trip Features (Syste Functional Testing) 75 Items 4.5.2 & 4.5.3- C ANPP-28167 ll/03/83 (B093) Reactor Trip System (All Units) ANPP-35938 04/03/86 Reliability - Test Alternatives and CE NPSD-277 Intervals (System Functional Testing)

i' GSI/ Reference (lfPA No.) Title Document(s) Status Comments/APS Letters to NRC 86 Long Range Plan for NA (B084) Dealing with Stress Corrosion Cracking i BWR Piping 93 Steam Binding of IEB 85-01 C ANPP-35355 02/28/86 (B098) Auxiliary Feedwater GL 88-03 (All Units) 161-01057 05/27/88 Pumps

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GSI/ Reference (MPA No.) Title Document(s) Status Comments

.99 RCS/RHR Suction GL 87-12 I APS Letters to NRC:

(L817) Line Valve Interlock GL 88-17 (All Units) 161-00517 09/14/87 on PWRs NUREG/CR-5015 161-01597 01/05/89 161-01674 02/06/89 Outstandin Work Pro ected Com letion Date

l. Install permanent refueling level indicatio'n -.

Unit 1: 06/92 (3rd refueling)

Unit 2: 01/92 (3rd refueling)

Unit 3: 09/91 (2nd refueling)

2. Install shutdown cooling system low-flow alarm-Unit 1: 06/92 (3rd refueling)

Unit 2: 01/92 (3rd refueling)

Unit 3: 09/91 (2nd refueling)

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GSI/ Reference (MFA No.) Title Document(s) Status Comments 99 4. Tech Spec Changes (Cont.)

a. Elimination of auto closure interlocks for SDCS suction valves-All units: 01/91
b. Reduction of SDCS flow rate requirement-All units: 10/90
5. ISEG review of RCS perturbations afte experience with new procedural controls-Unit 1: 07/90 Unit 2: 01/92 (3rd refueling)

Unit 3: 09/91 (2nd refueling)

i r GSI/ Reference (MPA No.) Title Document(s) Status Comments 124 Auxiliary Feedwater System Reliability A-13 Snubber Operability NRC LTR 11/20/80 NC Incorporated in CE Standard Technical (B017) Assurance- NRC LTR 03/23/81 (All Units) Specifications which were basis of PVNGS Hydraulic Snubbers Technical Specifications A-13 Snubber Operability NRC LTR 11/20/80 NC Incorporated in CE Standard Technical (B022) Assurance- NRC LTR 03/23/81 (All Units) Specifications which were basis of PVNGS Mechanical Snubber's Technical Specifications A-16 Steam Effects on NA (D012) BWR Core Spray Distribution A-35 Adequacy of Offsite NRC LTR 08/08/79 NC Incorporated into licensing review of PVNGS (B023) Power Systems BTP PSB-1 07/81 (All Units)

B-10 Behavior of BWR Mark NA III Containments B-36 Develop Design, R.G. 1.52, R2 Applicable to all plants with operating Testing and Mainte- R.G. 1.140, Rl license applications after 04/01/80. PVNGS nance Criteria for operating license application was forwarde Atmosphere Cleanup to NRC 10/01/79.

System Air Filtratio and Adsorption Units for Engineered Safet Features Systems and for Normal Venti-lation Systems

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GSI/ Reference (MPA No.) Title Document(s) Status Comments B63 Isolation of Lov WASH 1400 NC Incorporated into PVNGS Technical (B045) Pressure Systems (NUREG-75/014) (All Units) Specifications Connected to the Reactor Coolant System Pressure Boundary

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