ML17331B335

Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove License Condition Reference to Table 1 of Fire Protection Safety Evaluation Rept for Cook Nuclear Plant, Approved on 790604 & Issued on 790731

ML17331B335
Person / Time
Site:	Cook
Issue date:	04/06/1994
From:	FITZPATRICK E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17331B336	List: ML17331B335 ML17331B338
References
A00L-940406, AEP:NRC:0692CJ, AEP:NRC:692CJ, AL-940406, NUDOCS 9404130015
Download: ML17331B335 (15)

Text

ACCELERATED DI TRIBUTION DEMONST ATION SYSTEM 4~REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9404130015 DOC.DATE: 94/04/06 NOTARIZED:

YES DOCKET 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.

Indiana Michigan Power Co.(formerly Indiana&Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Application for amends to licenses DPR-58&DPR-74,proposing to remove license condition reference to table 1 of fire protection safety evaluation rept, for Cook Nuclear Plant, approved on 790604&issued on 790731.DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:

General Distribution NOTES: D RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL: NRR/DE/EELB NRR/DRCH/HI CB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL NRC PDR COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 0 1 1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DORS/OTS B NRR/DRPW NRR/DSSA/SRXB OC/LFDCB E~IL 01 NSIC COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 0 1 1 1 1 D D D NOTE TO ALL"RIDS" RECIPIENTS:

D D PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 16 ENCL 14 Indiana Michigan~Power Company P.O.Box 16631 Coiumbus, OH 43216 INWAl84 MCHII6'HAM ltaOMKR AEP:NRC'0692CJ Donald C.Cook Nuclear Plant Units 1 and 2 Docket No.50-315 and 50-316 License No.DPR-58 and DPR-74 LICENSE AMENDMENT U.S.Nuclear Regulatory Commission Document Control Desk Washington, D.C.20555 Attn: W.T.Russell April 6, 1994

Dear Mr.Russell:

This letter and its attachments constitute an application for amendment to the licenses for Donald C.Cook Nuclear Plant, Units 1 and 2.We propose to remove the license condition reference to Table 1 of the Fire Protection Safety Evaluation Report for Cook Nuclear Plant, approved on June 4, 1979, and issued under a cover letter dated July 31, 1979.The objectives of this 1979 license condition have been achieved.The license conditions'eference to the administrative controls for fire protection, as described in the licensee's submittals dated January 31, 1977, and October 27, 1977, will remain.These license conditions currently read as follows: Docket No.315 Amendment No.31 2.c(4)The licensee may proceed with and is required to complete the modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for the Donald C.Cook Nuclear Plant dated June 4, 1979.These modifications shall be completed in accordance with the dates contained in Table 1 of that SER or Supplements thereto.Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.

9404130015 94040b PDR ADOCK 05000315 PDR o~I (

Mr.W.T.Russell 2 AEP:NRC:0692CJ Docket No.316 Amendment No.12 2.c(3)(o)ire P otect o The licensee may proceed with and is required to complete the modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for the Donald C.Cook Nuclear Plant dated June 4, 1979.These modifications shall be completed in accordance with the dates contained in Table 1 of that SER or Supplements thereto.Administrative controls for fire protection as described in the licensee's submittals dated January 31, 1977 and October 27, 1977 shall be implemented and maintained.

It is proposed that the first two sentences of paragraphs 2.c(4)and 2.c(3)(o), above, be deleted.Attachment 1 provides a detailed description of the proposed changes, the reasons for the changes, and our proposed determination of no significant hazards consideration performed pursuant to 10 CFR 50.92, Attachment 2 contains the existing license condition pages marked to reflect the proposed changes.Attachment 3 contains the proposed, revised license condition pages.There are twenty-three schedular modifications identified in Table 1 of the Fire Protection Safety Evaluation Report for Donald C.Cook Nuclear Plant dated June 4, 1979.All twenty-three items have been completed.

Three of these items subsequently have been changed, as also discussed in Attachment l.We believe that the proposed changes will not result in the following:

(1)a significant change in the types of effluents or a significant increase in the amounts of any effluents that may be released offsite, or (2)a significant increase in individual or cumulative occupational radiation exposure.These proposed changes have been reviewed by the Plant Nuclear Safety Review Committee (PNSRC)and the Nuclear Safety and Design Review Committee (NSDRC).In compliance with the requirements of 10 CFR 50.91(b)(1), copies of this letter and it's attachments have been transmitted to Mr.J.R.Padgett of the Michigan Public Service Commission and the Michigan Department of Public Health.

Mr.W.T.Russell 3 AEP'NRC:0692CJ This letter is submitted pursuant to 10 CFR 50.30(b)and, as such, an oath statement is attached.Sincerely, Ee E.E.Fit p trick Vice President dr Attachments cc: A.A.Blind G.Charnoff J.B.Martin-Region III NFEM Section Chief NRC Resident Inspector J.R.Padgett STATE OF OHIO)COUNTY OF FRANKLIN)E.E.Fitzpatrick, being duly sworn, deposes and says that he is the Vice President of licensee Indiana Michigan Power Company, that he has read the foregoing Responses to the LICENSE AMENDMENT and knows the contents thereof;and that said contents are true to the best of his knowledge and belief.Subscribed end sworn to me before this~day of 19~v s s NOTARY PUBLIC Pilih D.HlLL NOTARY PUBLIC.STATE OF OHIO 0 I ,~'1 1~

ATTACHMENT 1 TO AEP:NRC:0692CJ DESCRIPTION, REASONS, JUSTIFICATION AND 10 CFR 50.92 SIGNIFICANT HAZARDS EVALUATION FOR THE CHANGES TO THE LICENSES FOR DONALD C.COOK NUCLEAR PLANT UNITS 1 AND 2 Attachment 1 to AEP:NRC:0692CJ Page 1 DESCRIPTION OF THE CHANGES The license condition references Table 1 of the 1979 Fire Protection Safety Evaluation Report (SEE).Table 1 of the 1979 Fire Protection SER is a schedule for the completion of twenty-three modifications required to meet Branch Technical Position Auxiliary and Power Conversions Systems Branch 9.5-1 (BTP APCSB 9.5-1).All twenty-three modifications have been completed and so this schedule is now obsolete.The license condition's reference to the administrative controls for fire protection described in the licensee's submittals dated January 31, 1977, and October 27, 1977, is not being changed.Since the 1979 Fire Protection SER we have made changes to three of these modifications as follows: Item C-Provide Cascade Rechar in Statio Three cascade recharging stations were originally installed on the Unit 1 633'urbine building, the Unit 2 609'rane bay and in the plant fire truck garage to meet this commitment.

These units have since been replaced with an air compressor approved for breathing air.The use of an air compressor is permissible under Appendix A to BTP APCSB 9.5-1.Item 9-Fire Proof Metal Hatches The hatches indicated in the table were all protected originally by Pyrocrete fire proofing.This was later replaced by TSI material as part of the plant's Appendix R compliance strategy.In an SER dated June 17, 1988, the NRC accepted a deviation request for unrated metal hatches.While the TSI material is still in place on most of the hatches, it will not be replaced if removed or damaged and no surveillance is being conducted on the material.Item 20-Diesel Fire Pum Controllers The old screenhouse diesel driven firepumps were upgraded to be in compliance with the SER.New fire water storage tanks, fire pumps, and associated components have been installed as part of the dedicated fire protection water supply.The old screenhouse diesel driven fire pumps were then considered to be a fixed"backup" fire suppression water system.This installation has been accepted by , the NRC staff via the March 31, 1993, letter for Amendment Nos.171 and 154.On March 16, 1994, a letter titled"Revision of Information Regarding the Backup Fire Water Supply" was sent to the NRC.This letter explains that the old screenhouse diesel driven fire pumps, which take direct suction from the forebay structure, have been experiencing recurrent operational

Attachment 1 to AEP:NRC:0692CJ Page 2 problems due to zebra mussel infestation.

Therefore, the old screenhouse diesel driven fire pumps are no longer considered to be a reliable and economically viable backup source of fire suppression water, and other"backup" fire suppression water is available.

The old screenhouse diesel driven fire pumps have been retired from fire protection service, REASON FOR THE CHANGES This amendment.

was written to delete the license condition reference to Table 1 of the June 4, 1979, SER in paragraph 2,C(4)issued with Amendment No.31 from Docket No.315 and to delete the license condition reference to Table 1 of the June 4, 1979, SER in paragraph 2.C(3)(o)issued with Amendment No.12 from Docket No.316.JUSTIFICATION OF THE CHANGES The modifications identified in Table 1 were scheduled to be completed during the first through the fourth refueling outages.These modifications have been implemented and this schedule is now obsolete.The changes to the modifications that have been implemented are consistent with the intent of 10 CFR 50 Appendix A.The change to Item 7C is acceptable under BTP APCSB 9.5-1, and it is a practical enhancement.

The changes to Item 9 has been reviewed and found acceptable by the NRC.Information regarding the retirement of the old screenhouse diesel driven fire pumps has been provided to the NRC.The"backup" fire suppression water is available and is expected to be acceptable to the NRC.Our response to BTP APCSB 9.5-1 is in our Fire Protection Program Manual (FPPM).We intend to add to the UFSAR reference to the FPPM, during the next UFSAR update.Thus, any future changes to our response to BTP APCSB 9.5-1 or to our June 4, 1979, Fire Protection Safety Evaluation Report will be subject to a 10 CFR 50.59(a)(2) safety evaluation.

10 CFR 50 92 Si ificant Hazards Evaluation Per 10 CFR 50.92, a proposed amendment will not involve a significant hazards consideration if the proposed amendment does not: (1)involve a significant increase in the probability or consequences of an accident previously evaluated, (2)create the possibility of a new or different kind of accident from any accident previously evaluated, or (3)involve a significant reduction in a margin of safety.

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Attachment 1 to AEP:NRC:0692CJ Page 3 Our evaluation of the proposed change with respect to these criteria is provided below.Criterion 1 This update of the fire protection modifications contained in Table 1 of the July 31, 1979, fire protection SER does not involve a significant increase in the probability or consequences of an accident previously analyzed as follows.Item 7C-The use of an air compressor rather than the cascade recharging stations does not adversely impact the ability to supply breathing air for the fire brigade and is acceptable under BTP APCSB 9.5-1.Item 9-The use of unrated metal hatches has been accepted by the NRC in a SER dated June 17, 1988.Item 20-The new fire pumps have already been accepted by the NRC in the SER dated March 31, 1993, Amendment Nos~171 and 154.The retirement of the old screenhouse diesel driven fire pumps is based on the availability of another supply of"backup" fire suppression water.Criterion 2 This update of the fire protection modifications contained in Table 1 of the July 31, 1979, fire protection SER does not create the possibility of a new or different kind of accident from any accident previously evaluated as follows.Item 7C-The use of an air compressor rather than the cascade recharging stations does not adversely impact the ability to supply breathing air for the fire brigade and is acceptable under BTP APCSB 9.5-1.Item 9-The use of unrated metal hatches has been accepted by the NRC in a SER dated June 17, 1988.Item 20-The new fire pumps have already been accepted by the NRC in the SER dated March 31, 1993, Amendment Nos.171 and 154.The retirement of the old screenhouse diesel driven fire pumps is based on the availability of another supply of"backup" fire suppression water.

Attachment 1 to AEP:NRC:0692CJ Page 4 Criterion 3 This update of the fire protection modifications contained in Table 1 of the July 31, 1979, fire protection SER does not involve a significant reduction in a margin of safety as follows.Item 7C-The use of an air compressor rather than the cascade recharging stations does not adversely impact the ability to supply breathing air for the fire brigade and is acceptable under BTP APCSB 9.5-1.Filled spare breathing air bottles are on-site and the local municipal department will provide assistance as needed.Item 9-The use of unrated metal hatches has been accepted by the NRC in a SER dated June 17, 1988.Item 20-The new fire pumps have already been accepted by the NRC in the SER dated March 31, 1993, Amendment Nos.171 and 154.The retirement of the old screenhouse diesel driven fire pumps is based on the availability of another supply of"backup" fire suppression water.

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