ML18038A221

Forwards marked-up FSAR Page 9A.3-23 & Figures 9A.3-4, 9A.3-5 & 9A.3-6.Change on Page 9A.3-23 Deletes Ref to HPCS Room & 600-volt Switchgear Room.Changes Will Be Incorporated in Future FSAR Update

ML18038A221
Person / Time
Site:	Nine Mile Point
Issue date:	10/22/1986
From:	Mangan C NIAGARA MOHAWK POWER CORP.
To:	Adensam E Office of Nuclear Reactor Regulation
References
(NMP2L-0922), (NMP2L-922), NUDOCS 8610280221
Download: ML18038A221 (14)

Text

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ACCESSION NBR: 8610280221 DOC. DATE: 86/10/22 NOTARIZED: YES FACIL".50-410 Nine Nile Point Nuclear Stations Unit 2> Niagara aloha AUTH. NAf'fE AUTHOR AFFILIATION NANGAN C. V.

Niagara Nohawk Power Corp.

RECIP. NANE RECIPIENT AFFILIATION ADENSANn E. G.

BflR Prospect Directorate 3

DOCKET ¹ 05000410 SUBJECT Forwards marked-up FSAR Pages VA. 3-23 8< Figures 9A. 3 4s VA. 3-5 h 9A. 3-b. Change on Page 9*. 3-23 deletes reF to HPCS room Zc 600-volt switchgear room. Changes vill be incorporated in future FSAR update.

DISTRIBUTION CODE:

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1N U MOoNIAMK NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVAROWEST, SYRACUSE. N.Y. 13202/TELEPHONE (315) 474 1511 October 22, 1986 (NMP2L 0922)

Ms. Elinor G. Adensam, Director BWR Project Directorate No.

3 U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Hashington, DC 20555

Dear Ms. Adensam:

Re:

Nine Mile Point Unit 2 Docket No. 50-410 Enclosed are marked-up changes to the Nine Mile Point Unit 2 Final Safety Analysis Report for Page 9A.3-23, Figures 9A.3-4, 9A.3-5 and 9A.3-6.

The change on Page 9A.3-23 deletes the reference to the HPCS room and 600-volt switchgear room to be consistent with Table 9A.3-1 (page 2 and 3

of 4).

Table 9A.3-1 shows that the HPCS and 600-volt switchgear rooms both have an average fire loading of less than one hour.

This change was requested by the Nuclear Regulatory Commission reviewer in a telecom discussion on October 20, 1986.

The changes on Figures 9A.3-4, 9A.3-5 and 9A.3-6 reflect our Safety Evaluation Report Supplement 4,

Pages 9-12, 9-13 and 9-14, comments as discussed in recent letter NMP2L 0919, and as discussed with the Nuclear Regulatory Staff on October 21, 1986.

These changes will be included in a subsequent Final Safety Analysis Report update.

Very truly yours, C. V. Mang Senior Vice President LSL/pns 2153G Enclosure xc:

N. A. Cook, NRC Resident Inspector Project File (2) 8610280221 861022 PDR ADOCK 05000410 A.....

PDRl.

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UNITED STATES OF AHERICA NUCLEAR REGULATORY COHHI SS ION In the Hatter of Niagara Hohawk Power Corporation

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(Nine Nile Point Unit 2)

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Docket No.

50-410 AFFIDAVIT C. V. Han an

, being duly sworn, states that he is Senior Vice President of Niagara Hohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belief.

Subscribed and sworn o before me, a Notar~@bl/c Sn and for the State of New York and County of

, this M day of &06t, 1986.

Notary Public in and for

County, New York

'5NAQPk@N"""

'otary Public in the State of Neer York ualiFed in Onondaga Co. No. 418768' Commission Exptres March 30, lfUV

NfRN 3Hil2lflit) haY ere to st% s4 ni oild6 qcJc)1 tNT87t.ul'I a3 s~~br~c<<0 nl twbh~9 0l,05 liat~"t( cislqX3 0 "fNlNLf<V3(tA

Nine Mile Point Unit 2 FSAR Drains are discussed in Section 9A.3.5. 1. 12.

Smoke removal is provided by normal ventilation and portable

'smoke removal units.

9A.3.1.2.5.10 Reactor Building Introduction Due to the presence'of floor openings, the entire reactor building is considered a

single fire area.

Each floor elevation is considered a separate fire zone and each half of the building is considered as a

fire subarea.

The analysis of the contained hazards indicates that the avera e

fire loading for each zone wi,t e exception of the HPCS room an 0-swi c gear room is ess than 1

r.

2

-wi e zone is provi e etween the north and

,south halves on the 0- to 180-deg line.

The 20-ft zone consists of two adjacent 10-ft zones with detection and automatic suppression systems.

To reduce the potential for the vertical spread of fire along cable tray risers, penetration seals are provided for cable tray risers'.

Refer to Figures 9A.3-2 through 9A.3-8 for the actual configuration of the fire stops'levation 353 ft. 10 in is a nonrated barrier which separates fire subareas FSA 34 and FSA 35:

There is no fire loading or safe shutdown equipment located on 'levation 353 ft 10 in; therefore, safe shutdown capability is not affected.

The reactor building has a

ventilation system utilizing 100 percent outside air for normal operation.

This system will remove smoke in the event of a

fire, as long as radiation levels remain below acceptable levels.

The primary containment is also considered one fire area.

However, due to the low fire

loading, primary containment

inerting, and lack of continuity of combustibles, a fire that would spread from one hazard to another is not postulated.

Safet -Related and Reactor-Associated S stems The following table includes both safety-related and reactor-associated systems and gives their locations in the reactor building.

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