ML19309E547

Forwards Responses to NRC Requests 331.31 & 423.1.Plant Radiation Protection Program Complies W/Reg Guides 8.8 & 8.10 W/Certain Exceptions.Program Does Not Include Specicfic Measurement Sys.Hand & Foot Monitors Are Unnecessary

ML19309E547
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	04/11/1980
From:	Novarro J LONG ISLAND LIGHTING CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
SNRC-472, NUDOCS 8004220620
Download: ML19309E547 (6)

Text

/

4 LONG ISLAND LIGHTING COM PANY

fMO

. J 7aarmw/stw SHOREHAM NUCLEAR POWER STATION P.O. BOX 618, NORTH COUNTRY ROAD e WADING RIVER N.Y.11792 April 11, 1980 SNRC-472 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322

Dear Mr. Denton:

In accordance with our recent telephone discussion, enclosed herewith are fifteen (15) copies of our responses to NRC requests 331.31 and 423.1 which apparently became detached from our March 31, 1980 SNRC-469 submittal.

Very truly yours, J. P. Novarro, Project Manager Shoreham Nuclear Power Station JPM/cc Enclosures cc: J. Higgins D\

ht 8004220620 F C.3 93 5

r h,5,*

REOUEST 331.31 It is our position that you base your radiation protection

- practices on the latest revisions of Regulatory Guide 8.8 (Rev. 3, June 1978) and Regulatory Guide 8.10 (Rev. 1, May 1977).

RESPO::SE With regards to the radiation protecti5n practices, the Shoreham Radiation Protection Program complies with Regulatory Guides 8'.8 (Revision 3, June 1978) and 8.10 (Revision 1, May 1977) with the following clarifications and exceptions:- .

Regulatory Guide 8.h (Revision 3, June 1978)

Regulatory Position 1.b. (1) (b) : (1) (c) The Shorcham Radiation Protection Program does not include a specific measurement nystem. Howcycr, authorization through specific radiation work permits (RWP) issued by !!calth Physics (!!P) and approved by the HP Engineer and the Watch Encincer is required for all work in a radiation contaminated arca as specified in the FSAR Section 12.5.3.2. Prior to

' issuance of an RWP, the job is reviewed and developed such as to maintain exposures to ALARA. All RWP's and associated doses. received are . revicwed by the 11P Supervisor. In additien, the review of the Operations Ccm=ittee (ROC) is responsible for performing a formal revicof the program at least

!' once a year to' ensure that the ALARA objectives of the prcgram are achieved.

For additional information refer to

- Section 12.1.1.3.2 and 12.5.3.3.4.

I 1.b. (3) The Shorcham Plant Managcr has the overall responsibility to carry out the policy of the Long Island Lighting I Company with regards to ALARA. Accord-

! ingly, the Health Physics Engineer is not independent of the station division and has direct reccurse to the Plant Manager.

I i

f 331.31-1

. P. 2 .- -

Regulatory Position 3.b. (1) Health Physics technicians are presently assigned to work Monday to Friday from 0800 - 1630 and are available for on call during their off hours. Additional HP tech coverage is presently being evaluated.

4.a. (4) Liquid Scintiilation analyses will be performed by an outside vendor due to the small number of samples.

c. (5) .

A hand and foot monitor is unnecessk;y since adequate " Friskers" and " Portals" are provided with appropriate procedures to ensure that this equipment is utilized properly.

Regulatory Guide 8.10 (Revision 1, May 1977)

Regulatory Position .

Col. (c) The qualifications of the Health Physics supervision are shown in their resumes in the FSAR. These qualifications are communsurate with the needs of the facility.

The applicable Reg. Guides and ANSI Standard were used to ensure this capability. For additional information refer to FSAR Section 13.1.2 and 13.1.3.

331.31-2

__ c .

.. .. *.-~ J t

Recuest 423.1 We have concluded that Regulatory Guide 1.68.2, " Initial l Startup Test Program to Demonstrate Remote Shutdown capability for Water-Cooled Nuclear Power Plants" (Revision 1, July 1978) and negulatory Guide 1.108, "Pericdic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants" (Revision 1, August 1977) are applicable for your facility. Modify your FSAR to describe how your initial test program will conform to Regulatory Guide 1.68.2 ,

and regulatory positions C.2.a and C.2.b of Regulatory Guide 1.108 or describe how you will provide for equivalent alternative testing. ,

Response

Section 14.1.4.8.25 has been revised to address conformance with Regulatory Guide 1.68.2, " Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Ccoled Nuclear Pcwer Plants" (Revision 1, July 1978). The revised section is attached.

During the plant preoperational test program, the Diesel .

Generators shall be tested in accordance with reculatory positions C.2.a and C.2.b of Regulatory Guide 1.105,

" Periodic Tasting of Diesel Generator Units Used as Casite Electric Power Systems at Nuclear Pcwer Plants" (Revisicn 1, August 1977). The applicable preoperational test procedures and FSAR Sections 14.1.3.7.24 and 14.1.3.7.49 will be revised as necessary.

423.1-1

Ma,*9. . .

, e FNPS-1 FSAR

. 14.1.4.8.25 Shutdown From Outside the Main Control P.ccm Startuo Test Objective

. To demonstrate that the following actions can be taken from outside the control roem:

a) Shutdown the plant safely b) Maintain the plant in a hot standby condition c) Safely cool the plant from hot standby to cold shutdown condition J.;

Test Method

1. A reactor scram will be initiated from a suitable location outside the main control room from a steady state power level greater than 20 percent of rated and the MSIVs are tripped.

t .

I

2. Subsequently, the vessel water icvel and pressure will

! be controlled from cu' aide the main control recm.

Suitable emergency operating procedures will be used.

j Refer to Section 7.5.1.4.5.

I

3. The controlled shutdown from outside the control reca 3

will verify that the plant can be placed in a stable l hot standby condition for at leas: 30 minu:es. Also, verify frca cutside che centrol rec: that a safe I

cooldown frca hot standby to cold shutd .n is initiated and centrolled to reduce the coolant temperature by approximately 50 F using the decay heat removal system at a rate that would not exceed technical specifica ica limits. These two ccnditions can be acccmplished in one step or individually, I

I depending en plant cperating ecnditions. g

4. The actions at the locations outside the centrol rocs will be performed by a number of pecple equal to the minimum shift crew as defined by technical specifications.

Additicnal personnel will he statiened in the main control room and at other lccr; ions in the plant as required to assist if'an emergency or unsafe condition devoleps '

during the tests and to perforn ncn-cafety related activiticc.

1anl-69

~ .-*

j ..

I l .

1 i Acceptance Criteria (Level 2) l During a simulated main control room evacuation, when the reactor '

has been brought to the point where cooldown is initiated and

.t under control, reactor vessel pressure and water level shall be

'l properly controlled using equipment and ccatrols outside the main control room.

4

• l l

t .

i i

i l i j .

l l

a l

l l i 1

1 f

4 P

i ,

I i

14.1-89a

,