ML17333A510
| ML17333A510 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/24/1996 |
| From: | Fitzpatrick E AMERICAN ELECTRIC POWER CO., INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1104F, GL-89-13, NUDOCS 9607290133 | |
| Download: ML17333A510 (11) | |
Text
CATEGORY j.
REGULATOR INFORMATION DISTRIBUTION%STEM (RIDE)
ACCESSION NBR:9607290133 DOC.DATE: 96/07/24 NOTARIZED: YES DOCKET I FACIL:50-315 Donald C.
Cook Nuclear Power Plant., Unit 1, Indiana M
05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
American Electric Power Co., Inc.
RECIP.NAME RECIPIENT'AFFILIATION Document Control Bianch (Document Control Desk)
SUBJECT:
Provides suppl response to GL 89-13, "Svc Water Sys Problems C
Affecting Safety-Related Equipment."
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DISTRIBUTION CODE:
A065D COPIES RECEIVED:LTR ENCL SIZE:
'TITLE: Generic Ltr 89-13 Svc Water Sys Problems Affecting Safety-Related E T NOTES:
RECIPIENT ID CODE/NAME HICKMAN,J COPIES LTTR ENCL 1
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INTERNAL: AEOD/SPD/RAB NRR/DISP/PSIB NRR/DRPM/PECB.
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NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL'NUMBER OF CSPIES REQUIRED:
LTTR 9
ENCL 9
American Electric r
1 Riverside Plaza Columbus, OH 4321 2373 614 223 1000
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AVIEIlCQM H.MF8MC PQlPM July 24, 1996 Docket Nos.:
50-315 50-316 AEP:NRC:1104F U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, DC 20555 Gentlemen:
Donald C.
Cook Nuclear Plant Units 1 and 2
GENERIC LETTER 89-13 SERVICE WATER SYSTEM PROBLEMS AFFECTING SAFETY-RELATED EQUIPMENT Reference 1:
AEP:NRC:1104 "Generic Letter 89-13; Service Water Syst: em Problems Response" from M.P.
Alexich to A.B. Davis dated January 25, 1990 Reference 2:
AEP:NRC:1104A "Generic Letter (GL) 89-13; Service Water System Problem Response" from M.P. Alexich to A.B. Davis dated January 30, 1991 Reference 3:
NRC Inspection Reports No. 50-315/95003 (DRS); No.
50-316/95003 (DRS), "Report of the NRC Evaluation of the Service Water System Internal Assessment",
dated August 4, 1995.
The original Cook Nuclear Plant response to Generic Letter 89-13 and the required confirmation of implemented actions are contained in references 1 and 2, respectively.
The.information found in the attachment to this letter provides supplementary information that reflects work completed since the submittal of reference 2.
This letter fulfills our commitment as described in section 5.3.2 of reference 3 to update the staff of any necessary changes and revisions to commitments made in references 1 and 2.
'P607290f33 960724 f
PDR, uADQCK OS00031 5 i
U.
S. Nuclear Regulatory Commission Page 2
AEP'NRC'1104F The attachment to this letter contains addenda to the information provided in reference 2 to reflect the work described above; The addenda do not represent reductions of previous commitments, and are being provided to maintain the clarity and accuracy of docketed information.
Sincerely, E.
E. Fitzpatrick Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS~9 DAY OF 1996.
Notary ublic
/jen Attachment cc:
A. A. Blind H. J. Miller NFEM Section Chief NRC Resident Inspector
- Bridgman J.
R. Padgett
U.
S. Nuclear Regulatory Commission Page 3
AEP'NRC'1104F bc:
S. J. Brewer/D.
H. Malin/T. A. Georgantis/L.
M. Smart J.
A. Kobyra/K. R. Baker/D.
R. Hafer J.
B. Shinnock J.
S. Wiebe J. B.'ickman, NRC - Washington, DC - w/attachment M. E. Eberhardt
- w/attachment PRONET - w/attachment DC-N-6015.1
ATTACHMENT TO AEP NRC 1104F
Attachment to AEP:NRC:1104F Page 1
The following provides additional information to supplement our previous responses to actions I through V and enclosures 1 and 2 of GL 89-13.
Each response item is listed below with either an addendum to the original response or a notation that no change to the original response is needed.
Res onse to Action I No change to original response.
Res onse to Recomme dation A o Enclosure 1
90 No change to original response.
Recommendation A o Enclosure 1 Pro ram Im lementation Summar 1 91 No change to original response.
Addendum to Recommendation B of Enclosure 1 Res onse 1 25 90 In our original response, it was indicated that temporary chlorination facilities can be connected to the open-cycle service water system at Cook Nuclear Plant.
It was also indicated that a chlorination program would be prepared for chlorinating the service water system on a contingency basis.
Since then we have obtained the necessary permits and have instituted continuous chlorination of the essential service water (ESW) system when biofouling species are most reproductive.
Additionally, it was indicated that the fire protection system would be treated shortly after the service water system.
Since then a dedicated non-lake water source was installed to supply the fire protection system.
This change was submitted in AEP:NRC:0692CW, dated 3/16/94, titled "Abandonment of Fire Pumps 1-PP-75 and 2-PP-75."
Based on this submittal, the GL 89-13 concerns do not apply to the fire protection system.
Recommendation B of Enclosure 1 Pro ram Im lementation Summar 1 91 No change to original response.
Attachment to AEP:NRC:1104F Page 2
Addendum to Recommendation C of Enclosure 1 Res onse 1 25 90 In our original response, it was indicated that partial flushing of the ESW supply to the auxiliary feedwater system alternate suction source was performed.
Since then flushing connections have been installed to permit full flow flushing of these lines.
It was also indicated that the fire protection components are inspected or tested as scheduled on a twelve or eighteen-month
- cycle, and yard piping is flushed every six months.
Since then a dedicated non-lake water source was installed to supply the fire protection system.
This change was submitted in AEP:NRC:0692CW, dated 3/16/94, titled "Abandonment of Fire Pumps 1-PP-75 and 2-PP-75."
Based on this submittal, the GL 89-13 concerns do not apply to the fire protection system.
Addendum to Recommendation C of Enclosure 1 Pro ram Im le e tat on Su mar 91 In our response under program implementation, several plant procedures are referenced.
Since then some of these procedure references have changed.
The following procedure changes are noted:
PREVIOUS REFERENCE NEW REFERENCE 1 THP 4030 STP.241 ESW Flow Balance 2 THP 4030 STP.241 ESW Flow Balance MHI-4030 PM Task 72 PM and EQ 1 EHP 4030 STP.241 ESW Flow Balance 2
EHP 4030 STP.241 ESW Flow Balance MHI-5030 PM Task 72 PM Sand Accumulation in ESW Piping Res onse to Recommendatio D of closure 1
1 25 90 No change to original response.
Recommendation D of Enclosure 1 Pro ram Im lementation Summar 1 91 No change to original response.
Addendum to Res onse to Action I 1
90 In our original response, the diesel driven fire pump lube oil coolers were included in the test program.
- However, these coolers are no longer part of the program since a dedicated non-lake water source was installed to supply the fire protection system.
This change was submitted in AEP:NRC:0692CW, dated 3/16/94, titled "Abandonment of Fire Pumps 1-PP-75 and 2-PP-75."
Based on this submittal, the GL 89-13 concerns do not apply to the fire protection system.
Res onse to Recommendation 1 of Enclosure 2
1 25 90 No change to original response.
Attachment to AEP:NRC:1104F Page 3
Res onse to Recommendation 2 of Enclosure 2
1 25 90 No change to original response.
Res onse to Recommendation 3 of Enclosure 3
1 5 90 No change to original response.
Addendum to Recommendation 4 of Enclosure 2
1 25 90 In our original response, the diesel driven fire pump lube oil coolers were included in the test program.
- However, these coolers are no longer part of the program since a dedicated non-lake water source was installed to supply the fire protection system.
This change was submitted in AEP:NRC:0692CW, dated 3/16/94, titled "Abandonment of Fire Pumps 1-PP-75 and 2-PP-75."
Based on this submittal, the GL 89-13 concerns do not apply to the fire protection system.
ddendum to Action II Pro ram Im lementation Summa 1 91 In our response under program implementation, several plant procedures are referenced.
Since then some of these procedure references have changed.
The following procedure changes are noted:
PREVIOUS REFERENCE NEW REFERENCE 12 THP 6040 PER.002
- Canceled, incorporated into new rocedures below 12 THP 6040 PER.002.CCW CCW Ht Exchan er Functional Test 12 EHP 6040 PER.002.CCW CCW Ht Exchan er Functional Test 12 THP 6040 PER.002.EDG EDG Coolers Performance Test 12 EHP'6040 PER.002.EDG EDG Coolers Performance Test ddendum to Res onse to Action III 1 25 90 In our original response, it was indicated that the Cook Nuclear Plant inspection and maintenance program for open-cycle service water system piping and components is performed on a post-maintenance basis.
Since then a formal inspection program has been instituted at the Cook Nuclear Plant.
This program is performed per procedure 12 PMP 5030.001.005, "Essential Service Water System Inspection Program," approved 1/12/96.
The procedure establishes a routine inspection and maintenance program for the components and piping of the service water system that ensures against degradation resulting from corrosion, erosion, silting and biofouling.
This action item also included inspection and flushing of the fire protection system.
Since then a dedicated non-lake water source was installed to supply the fire protection system.
This change was submitted in AEP:NRC:0692CW, dated 3/16/94, titled "Abandonment of Fire Pumps 1-PP-75 and 2-PP-75."
Based on this submittal, the GL 89-13 concerns do not apply to the fire protection system.
Attachment to AEP:NRC:1104F Page 4
dde dum to ct o P o ram Im erne tat o Summa 1
In our response under program implementation, several plant procedures are referenced.
Since then some of these procedure references have changed.
The following procedure changes are noted:
PREVIOUS REFERENCE NEW REFERENCE MHI-5030 PM Task 72 PM and E
Pro ram MHI-5030 PM Task 72 PM Sand Accumulation in ESW Pi in MHI-5030 PM Task 10 EDG Cooler Ins ection 12 SHP 5050 NDE.008 UT Insp for Thickness Measurements 12 MHP 5020.032.015 EDG En ine Intake Air Aftercooler 12 QHP 5050 NDE.008 UT Examination for Thickness Measurements 12 SHP 5050 NDE.014 Grid Layout for Erosion/Corrosion 12 QHP 5050 NDE.014 Grid Layout for Flow Accelerated Corrosion Examinations ddendum to Res onse to Action IV 1 25 90 In our original response, it was indicated that a review of the Cook Nuclear Plant service water system confirmed that the system is capable of performing its required safety function in the event of a failure of a single active component.
Since then a design basis reconstitution program has been instituted.
This program has produced the essential service water design basis document (DBD) as well as other pertinent DBDs.
The DBDs review and document the single failure criteria requirements and indicate that the ESW system is designed with appropriate redundancy to ensure that no single failure (mechanical, electrical or instrumentation) can prevent the system from performing its safety related function.
This conclusion was also affirmed by the Service Water System Operational Performance Inspection conducted in 1995.
Action IV Pro ram Im lementation Summa 1 91 No change to original response.
Res onse to Action V 1 25 90 No change to original response.
Action V Pro ram Im lementation Summa 1
9 No change to original response.
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