ML19347D278

From kanterella
Jump to navigation Jump to search
Forwards Amend 71 to Provisional License DPR-21 Re 810105 Application for Mods to Fire Protection Program.Amend Deletes Requirements for Mods within Scope of 10CFR50,App R. W/O Encl
ML19347D278
Person / Time
Site: Millstone Dominion icon.png
Issue date: 02/13/1981
From: Crutchfield D
Office of Nuclear Reactor Regulation
To: Counsil W
NORTHEAST NUCLEAR ENERGY CO.
References
LSO5-81-02-051, LSO5-81-2-51, NUDOCS 8103110723
Download: ML19347D278 (2)


Text

I 3

}

+

O

,i*

e o

DISTRIBUTION 7:.A

' NRC PDR OELD OI&E(5)

L PDR on

)

ORBe5 reading Docket No. 50-245 5

LS05-81-02-051 RSEARY 13 sin e ut OPA, CMiles TNovak RDiggs RTedesco HDenton GLainas JHelterac "nD Mr. W. G. Counsil, Vice President V

Gra" ', g

/,g h nsk1 Nuclear Engineering and Operations e)

Northeast Nuclear Energy Company JShea

\\,

Post Office Box 270 TWambach Hartford, Connecticut 06101 gy m

t' 7T[

Dear Mr. Counsil:

T 7

/ h O

SUBJECT:

FIRE PROTECTION PROGRAM - MILLSTONE 1 p

//

+

/

'.G "e/

The Connission has issued the enclosed Amensaent No. 71 to Provisional l

l Operating License No. DPR-21 for the Millstone Nuclear Power Station, Unit No.1. This amendment is in reference to your application dated January 5,1981.

The amendment modifies paragraph 3.F of 3.icense DPR-21 by replacing the words " Supplements thereto" with " Supplement No. I to the Safety l

Evaluation dated November 19, 1980", and by deleting the requirement for submitting additional information for two items in Table 3.1 of the Septerter 26, 1978 Fire Protection Safety Evaluation Report (FPSER),

both of which have been received, reviewed and approved by the NRC. This amendment also deletes the requirement for six specific modifications identified in paragraph 3.1.19 of the FPSER.

The changes you proposed have been modified to retain the requirement for the administrative controls specified in paragraph 3.F of the license.

This modification reflects telephone agreements between us and your representatives. The six modifications identified in paragraph 3.1.19 were related to improving the protection of certain equipment which l

could be used for safe shutdown of the plant following a fire in certain l

plant areas. A new Appendix R to 10 CFR 50, which becomes effective on February 17, 1981, specifies new criteria for these modifications and broadens the scope of the plant areas to be protected. All licensees are required to reassess the fire protection for safe shutdown capability I

using the new criteria of Section III.G of Appendix R to 10 CFR 50 and propose the appropriate modifications by March 19, 1981. Therefore, the modifications that had been required by paragraph 3.1.19 of the FPSER have been superseded by this new regulation and are no longer appmpriate.

In Section 3.2.2, " Fire Hose Station Evaluation," of our FPSER, we noted that hose stations would be verified to be capa:'.e cf supplying a pressure of 65 psig at the nozzle under flowing conditions.

Larger pipe sizes would be provided if required to provide a hose nozzle pressure to insure

.m-.-,..~....-.

~

u...

CFMCE) suwor)

..... 0. 3...1..1..o...

7..2.3...........

f$ 1 em)

N:c 'oa" 8'e iio,soi sacu.2 4o 0FFICIAL RECORD COPY

'u"

"*-'2""

@T4JEME9M4Ff'

N

~~

~,r

,N 3

s Mr. W. G. Counsil FEBRUAP,Y 1 3 1981 By letter dated July 31. 1979, you stated that a pressure test had been perfonned at Hose Station Nos. 44 and 45. These stations are located at the 108' level in the reattor building and represent the most i

severe condition for pressure considerations. The test results indi-cate that the pressure at the nozzle would be 72 psig and 65 psig, respectively.

We, therefore, find that this test verifics that the fire hose stations j

will supply at least 65 psig at thi hose nozzles.

This amendment deletes requirements for fire protection modifications which are within the purview of the new Appendix R to 10 CFR Part 50, and, therefore, does not authori:e a change in effluent types or total amounts nor an increase in power level, and will not result in any significant environmental igact. Having made this determination, we have fwther concluded that this amendment involves an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR 51.5(d)(4) that an environmental impact statement, or negative declaration and environmental igact appraisal need not be prepared in connection with the issuance of this amendment.

Since this amendment applies to fire protection requirements which will l

be assessed under a broadened scope, it does not involvr. a significant increase in the probability or consequences of an accioent, does not involve a significant decrease in a safety nargin and, therefore, does not involve a significant hazards consideration. We have also concluded that there is reasonable assurance that the health and safety of the public will not be endangered by this action and that the issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public.

A copy of the Notice of Issuance is also enclosed.

Sincerely.

Original Signed by DennisM. Crutchtield Dennis M. Crutchfield, Chief Operating Reactors Branch f5 Division of Licensing 1

?

Enclosures:

h

. #,f d

(

l.

Amendment Nc. 71 to i

License No. DPR-21 2.

Notice t

,g cc w/ enclosures:

p

' [j see next page p

LDWW#

onice >

ORB D

ORB #5:DL

..O..RB # : DL.(........ M......C/.

L

.............,.Q...

t.... n.,,,,,J,S hp,a,fd,',,,,,,,,,,,,,,a,

,4,5,,;h,$,,,,,,,,,%,,,,,,,,,,, pld "4

2/,(c,/,81,..,...,,,2/,j, /81.,,,,,,,2z,yza!,,,,,,,,,,2 3 / 81

, g,(,,,,,,,,,,,

2/

81

.w

--32n2 "c 'on* 3's.io, eor uncu o24o OFFICIAL RECORD COPY h

-