ML17054B594

Informs That Responses to Generic Ltr 83-28,Items 2.1,2.2, 3.1.3,3.2.3 & 4.5.3 Incomplete.Request for Addl Info Encl. Responses Requested within 60 Days for Items 2.1,2.2,3.1.3 & 3.2.3 & 90 Days for Item 4.5.3

ML17054B594
Person / Time
Site:	Nine Mile Point
Issue date:	04/23/1985
From:	Vassallo D Office of Nuclear Reactor Regulation
To:	Hooten B NIAGARA MOHAWK POWER CORP.
References
GL-83-28, NUDOCS 8505030117
Download: ML17054B594 (10)

Text

April 23, 1985 Docket No. 50-220 Mr. B.

G. Hooten Executive Director, Nuclear Operations Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, New York 13202

SUBJECT:

RE(UEST FOR ADDITIONAL INFORMATION FOLLOWING PRELIMINARY STAFF REVIEW OF LICENSEE RESPONSES TO GENERIC LETTER 83-28 Re:

Nine Mile Point Nuclear Station, Unit No.

1 The staff has completed a preliminary review to assess the completeness and adequacy of licensee responses to Generic Letter 83-28 Items 2. 1, 2.2,

3. 1.3, 3.2.3, 4.4 and 4.5.

For Nine Mile Point, your responses were found to be incomplete for Items 2. I, 2.2, 3. 1.3, 3.2.3 and 4.5.3.

Brief descriptions of the deficiencies are given as guidelines for corrective action in the enclosed Request for Additional Information.

Efforts by Owners

Groups, INPO and NSSS vendors have been or are being made to produce generic responses that may be useful in meeting the requirements of Generic Letter 83-28 Items 2. 1, 2.2.2 and 4.5.3.

You may wish to contact your Owners Group or INPO regarding the applicability of'uch generic responses to your plant.

In order to preserve our present review schedule, the staff needs to have the supplementary information within 60 days of receipt of this letter for Items

2. 1, 2.2, 3. 1.3, 3.2.3, and within 90 days for Item 4.5.3.

If you intend to formally endorse the BWR Owners Group response to Item 4.5.3 (NEDC-30844), the staff should be advised within 60 days.

Your plant-specific response to Item 4.5.3should

'then be provided within 90 days after NRC completes its review of NEDC-30844 and issues its evaluation.

We request your cooperation in meeting this schedule.

r fJ 85050301i7 850423 PDR ADOCK 05000220I PDR

I k c" rfr R

I a

~

R h '"

Ir',

/"

nr

~

Irgr 7

I 't R

f 7

Ih,,chil 7 (r 7

l'll tr )g ',

hrrgv 7

'R 7R"'l h

~

f Irh RI ','l hr 7 V7,,'R

<<RI

'l<<1 I'r '7 't I 7 'Irllh I" R 7

',,rh I I ll777 Jf I

7 r

I

. ~ ~

N

'h I

l7 I'"

l

'Rhg h

I I

I'>,

<<II=

'c R ~

R II jr NI 7

777j'r r

I,'I f

I I ry I

,lII7'7 I'

rf R

I' tl fhg hh I ~

7 "7

~

NI ~

7 N

1

>1

'R "-- II 11 II

'l

'H I

N r

)'4 I,'

N 7'I I

h, I I I

~

,h I

'I

~, ~,

RR R

~

I C'

'r'" r h

'I R

R rll

'<<t(N ~ h

~

N I N,trhp 7( (),

(I7 "(

')7.S I'\\

Nh rlr ftlh, l

1 Nr tr ~ I

'lf y

g IN Rh f.

It N

I h(

I 777'hr N',7'('

N c

~ 5 r, f

\\

j Mr. B. G. Hooten This Request for Additional Information was approved by the Office of Management and Budget under clearance number 3150-0011 which expires April 30, 1985.

Comments on burden and duplication may be directed to the Office of Management and Budget, Reports Management Room 3208, New Executive Office Building, Washington, D.

C.

20503.

Sincerely, Original signed by/

Domenic B. Vassallo, Chief Operating Reactors Branch ¹2 Division of Licensing

Enclosures:

1.

Request for Additional Information 2.

Ltr dtd March 20,

1985, H. Thompson (NRC) to S.

Rosen (INPO) cc w/enclosures:

See next pageI, NRC PDR Local PDR ORB¹2 Reading HThompson OELD SNorris RHermann ELJordan BGrimes JPartlow ACRS (10)

Gray File RAuluck JHopkins JStevens DLasher DBeckham RKarsch DISTRIBUTION C. oc et i e rs I

B O

s Irr 1I s,

n OL:

RB¹2 OLQBB¹2 SNorrss:ass RNPmann 04/)8/85 04/)g /85

.0 B¹2 DVassallo 04@ /85

f 1

R II a~I A

I I

Fl 1

t tt ~

tp II

"~

k

'4

Mr. B. A. Hooten

'iagara Mohawk Power Corporation Nine Mile Point Nuclear Station, Unit No.

1 CC:

Troy B. Conner, Jr., Esquire Conner 5 Wetterhahn Suite 1050 1747 Pennsylvania

Avenue, H.

W.

Washington, D.

C.

?0006 Frank R. Church, Supervisor Town of Scriba R.

D. j/2

Oswego, New York 13126 Niagara Mohawk Power Corporation ATTN:

Mr. Thomas Perkins Plant Superintendent Nine Mile Point Nuclear Station Post Office Box 32

Lycominq, New York 13093 Thomas A. Murley Regional Administrator Region I Office U.

S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Mr. Jay Dunkleberger Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza

Albany, New York 12223 Resident Inspector U. S. Nuclear Regulatory Commission Post Office Box 126

Lycoming, New York 13093 John W. Keib, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, Hew York 13202

t,

ENCLOSURE 1

REQUEST FOR ADDITIONAL INFORMATION NINE MILE POINT NUCLEAR STATION, UNIT NO.

1 Item 2.1 (Part

1) - Incomplete Licensee needs to submit his new 0 List when complete.

Has licensee committed to assuring that RTS components are identified as safety-related on all drawings, documents and in information-handling systems?

Item 2.2 - Incomplete Licensee needs to present his evaluation of the NUTAC program and describe how it will be implemented at Nine Mile Point, Unit No.

1.

The staff found the NUTAC program fails to address the concern about establishing and maintaining an jnterface between all vendors of safety-related equipment and the utility.

Accordingly, the licensee will need to supplement his response to address this concern.

This additional information should describe how current procedures will be modified and new ones initiated to meet the elements of this concern.

Item 3. 1.3 - Incomplete Licensee needs to state if he has found any post-maintenance testing requirements for RTS components that may degrade safety.

If any such requirements are identified, the licensee shall describe actions to be taken including submitting needed Technical Specification changes.

Item 3.2.3 - Incomplete Licensee needs to submit some type of information for safety-related components other than RTS that was required for Item 3. 1.3.

Item 4.5.3 - Incomplete The staff finds that modifications are not required to permit on-line testing of the backup scram valves.

However, the staff concludes that testing of the backup scram valves (including initiating circuitry) at a

refueling outage frequency, in lieu of on-line testing, is appropriate and should be included in the Technical Specification surveillance requirements.

The licensee needs to address this conclusion.

Regarding the scram pilot valves (including all initiating circuitry), the licensee needs to provide the results of a review of existing or proposed intervals for on-line testing considering the concerns of sub-items 4.5.3. 1 to 4.5.3.5 of the generic letter.

The response shall show how these intervals result in high reactor trip system availability and present proposed Technical Specification changes for staff review.

1 Letter dated March 20,

1985, H. Thompson (NRC) to S.

Rosen (INPO)

I

?,

The staff has just received the BWR Owners Group response to Item 4.5.3 (NEDC-30844).

If the licensee intends to formally endorse the Owners Group

response, the 'licensee should delay his plant-specific response to Item 4.5.3 unti 1 after the staff completes its review of the Owners Group response.

F

~