ML17258A963

Concurs W/Approach Incorporating Tech Spec Changes Re Term Operable W/Changes Necessary During Integrated Assessment of Sep.Info Re How Procedures Have Been Modified to Reflect NRC 800410 Guidance Should Be Submitted

ML17258A963
Person / Time
Site:	Ginna
Issue date:	04/09/1981
From:	Crutchfield D Office of Nuclear Reactor Regulation
To:	Maier J ROCHESTER GAS & ELECTRIC CORP.
References
LSO5-81-04-010, LSO5-81-4-10, NUDOCS 8104170715
Download: ML17258A963 (4)

Text

0 Q.

Docket No. 50-244 LS05-81-04-010 APR 9 188]

Mr. John E. Maier, Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649

SUBJECT:

DEFINITION OF TERM "OPERABLE" DISTRIBUTION ocke file NR L PDR ORBb5 reading DEisenhut 0)

DCrutchfiel d

'/@

RSnai der g(Q~~

Ngirgiiio g498~

OELg IEi',aeuaa+

i2 IaE(3)

NSIC TERA ACRS(10)

(

By letter dated April 10, 1980, the NRC staff forwarded guidance regarding definition of the term "operable" and requested that you modify the Techni-cal Specifications for the R. E. Ginna Nuclear Power Plant to incorporate the specific guidance contained in the model technical specifications attached to the April 10 letter.

Our concern was that.

because existing technical specifications do not address the operability of necessary ancillary systems in Limiting Conditions for Operation, a large number of equipment outage combinations could exist in which the plant might not be fully protected.

Your response, dated August 25, 1980, objected to the irmediate imposition of the suggested technical specifications and noted that the requested changes would be very extensive in nature, based upon the fact that the Ginna Technical Specifications are not in Standard Technical Specification format.

You also suggested that the changes could be incorporated in the technical specifications along with others determined to be necessary during the integrated assessment of the NRC's Systematic Evaluation Program (SEP).

We concur in this approach and will include this requirement in the SEP integrated assessment.

However, in the interim we will require more assurance that "...the guidance of the Staff's April 10. letter will be followed."

as stated in your August 25, 1980 letter.

Specifically, we require information regarding how procedures have been modified and operators trained in order to assure plant protection under the various SX9.4X'ZO 7 t 7

4

~,'.g /I/gj I

,fp, C

pq I

- IIF

"<4>>~~-7 g

'I II

<<f, W

q ~

F

c

2 APR S

1981 possible combinations of equipment failures.

This information should be forwarded within 20 days of receipt of this letter.

Sincer ely, cc:

See next page Original Signed by Dennis M. Crutchfield, Chief Operating Reactors Branch ¹5 Division of Licensing ORB 5:DL 0FF1CEf>

SVR14AMCP 0A~E f> 4/Y/81

~

0 0

~ ~

~ ~

~ ~ ~

RSnai der:dn ORB¹5 HSmi 4/7 81 t ~ ~ ~ ~

~ & ~ ~ ~

~

r SMiner~~

4/7/81 C

DL

~ ~ ~ ~ 0 ~ ~ 0 WRussell 4/5 /81 C/:

L DC field 4/P /81

~ ~ ~ ~ g

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

G 4

A:DL

~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

/81 NRC FORM 318 <10/80) NRCM 0240 OFFICIAL RECORD COPY

• USGFO. 1980-329 824

l r

4C a

C p,pa 1S 198)