ML19276F021

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Forwards Request for Addl Info Re Proposed Fire Protection Mods.Suggests Changes to Meet Acceptance Criteria
ML19276F021
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 03/05/1979
From: Reid R
Office of Nuclear Reactor Regulation
To: Cavanaugh W
ARKANSAS POWER & LIGHT CO.
References
NUDOCS 7903270009
Download: ML19276F021 (5)


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March 5,1979 Docket No. 50-313 Mr. William Cavanaugh, III Executive Director, Generation and Construction Department Arkansas Power & Light Company P. O. Box 551 Little Rock, Arkansas 72203

Dear Mr. Cavanaugh:

We have reviewed your submittals dated January 18 and 31,1979, concerning the fire protection modifications of Arkansas Nuclear One - Unit 1.

We find that additional infonnation is needed and that changes to your proposed modifications are needed to meet our criteria of acceptance.

Enclosed is our request for additional information and our positions relating to your proposed modifications. Since the modifications are scheduled for implementation during the forthcomir.g refueling outage, we request a response as soon as possible in order that the continued review of the proposed modifications will not impact upon your refueling schedule.

Sincerely, m

,73

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V Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors

Enclosure:

Request for Additional Information cc:

See next page 79032700ci

Arkansas Power & Light Company CC:

Phillip K. Lyon, Esquire House, Holms & Jewell 1550 Tower Building Little Rock, Arkansas 72201 Mr. Daniel H. Williams Manager, Licensing Arkansas Power & Light Company Post Of fice Box 551 Li ttle Rock, Arkansas 72203 Mr. John W. Anderson, Jr.

Plant Superintendent Arkansas Nuclear Cne Post Of fice Box 608 Russellville, Arkansas 72801 Mr. Thomas F. Festerman U. S. Nuclear Regulatory Commission P. O. Box 2090-Russelville, Arkansas 72801 Mr. Robert B. Borsum Babcock & Wilcox Muclear Power Generation Division Suite 420, 7735 Old Georgetown Road Bethesda, Maryland 20014 Arkansas Polytechnic College Russellville, Arkansas 72801

.s Request for Additional Information and NRC Positions Concerning Fire Protection Modifications as Proposed in Letters Dated January 18 and 31, 1979 for Arkansas Nuclear One - Unit 1 1.

SER Items 3.3 (Corridor No. 98) and 3.7 (Cable Screadinc Room):

a.

Additional details are required on the temperature rating, placement and performance characteristics of the Protectouire detection system.

The specifications should indicate the con-figuration of the Protectcwire installation pattern and whether it is to be laid cn the top of the cable trays or atcached to the underside.

The design should be suppor:ed by test data or analysis verifying that the response ti.m will be rapid enough to prevent damage to the exposed safe shutdtwn cables in conduit (Spec Item 9. 7.2).

b.

The detectors, when installed, should be tested in olage to dater-mine their adequacy with respect to the number and their placement.

As a result of the testing and with the required resconse time analysis establish the effectiveness of the procosed system.

For those areas where the speed of the response is critical. provide an analysis of the detector perfomance criteria establishing the

, required response time (Spec Item 9.1.3.1).

c. 'T'.e reliability of the Protectcwire syster ske :1d be i prived by installing the system so that every other cable tray (vertically and horizontally) is in a different zone.

Then, if there is any malfunction of one zone, the fire will still be detected prc=ptly by the Protectowire zone in the next adjacent tray (Spec Item 9.7.2.3).

d.

The reliability of the water spray system should be improved by designing the logic of the actuation system so that it includes the follcwing combinations as possible actuation modes:

(1)

Actuation of any one smoke detector and any ons Protecto-

~ ire zone; w

(2)

Actuation of any r.vo prctectcwire :cr.es; Or (3)

Actuacicn of any O.90 smcke detectors.

The syste' should still alarm on actuatier :# 1; or Fr::ect: wire ::ne (5:sc Itam 9.7.2.0).

. :re.5= ks fatectcr

e.

Compliance should be required with f1FPA 72-E-1978, " Standard on Autcmatic Fire Detectors" (Spec Item 6.2).

f.

Identify the location of the manual tripping station (s).

9' Identify the circuitry (power, actuation, and alam) or cortions of circuits that will be electrically supervised for ocen circuits, shorts to ground, and line-to-line shorts.

(This is not called out in the system specification).

(Spec Item 9.7.6.3).

h.

The water system should be capable of supplying the water spray system plus hose lines with one fire pump out of service.

Identify how many fire pumps the specified 3,800 gpm at 109 psig-assumes to be in operation (Spec Item 8.2).

i.

Provide schematics shewing the normal and emergency pcwer supply for the line-type heat detectors. - (Spec Item 9.7.6.1).

Veri fy that all portions of the detection and actuation systems are provide'd with an, emergency power source.

j.

Verify that all circuit su;arvision, including that for the existing smoke detectors in the cable spreading room, will actuate audible and visual trouble signals in the control room.

(This is not called cut in the system specification.)

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k.

Referring to Section IV, page 4, of the " Description Report," it is not clear if the trcuble alarm can be silenced when the test switch at C463 is in position to prevent automatic operation of the water spray system.

It should not be possible to silence tnis alarm.

In addition, a light should also be provided on the main control panel to indicate this condition of impairment.

l.

The statement on Section IV, page 5, of the " Description Report" that solenoid valve number 2 is mechanically operated while solenoid valve number 1 is electrical requires clarification.

2. SER Items 3.4 (Switchgear Rcoms) and.3.8 (Uccer North Electrical Penetration Recm) a.

The licensee should provide test data or reference submitted test reports to support the design of the Kacwcol installati' n to o

protect safe shutdown conduits from fire.

b.

Zone 99-M (North Switchgear Roem): Ccnduits EC1190 and EC1237 shoulc be crcticted by insula:icn rather than by s;rayinr the expcsing cable trays with fire retardant mastic.

c.

Z:ne M?-E-(north uccer elecorical :ere:raticn area):

Ccn dui t E31095 snculd be crotected by insulation rather than by scraying One ex:csing redundant cable tray with fire retardant mastic.

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. 3.

SER Item 3.11 (Hose Stations):

The locatien of propcsed fire hose stations in the Reactor and a.

Auxiliary Suildincs is censidered acceptable; hcwever, a:diticnal pressure and ficw data is required to properly evaluate the capabili.ty of the proposed systems.

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