ML20215B819

Forwards List of Pressure Isolation Valves Tested for Leak Tight Integrity,Per Generic Ltr 87-06.List Includes Test Frequency,Description of Periodic Test Performed & Acceptance Criteria

ML20215B819
Person / Time
Site:	Indian Point
Issue date:	06/11/1987
From:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
GL-87-06, GL-87-6, IPN-87-032, IPN-87-32, NUDOCS 8706170465
Download: ML20215B819 (6)

Text

123 Main Street

-i WWte Plains, Nm York 10601 914 681 6240

1. > NewYo.rkPbwer g"jhm, tv Authonty

==eme" June 11, 1987 IPN-87-032

.U.S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D.C. 20555

Subject:

Indian Ibint 3 Nuclear Power Plant Docket No. 50-286 Response to Generic I.etter 87-06, " Periodic Verification i

of leak-Tiaht Intectrity of Pressure Isolation Valves"

Reference:

1. Supplement No. 1 to the Safety Evaluation Report

-(SER) of the Indian Point 3 Facility Operating License, dated January 16, 1975.

2. Supplement No. 2 to'the SER of the Indian Point 3 Facility Operating License, dated W W r 12, 1975.

3. Confirmatory Order related to population density concerns at Indian Point, dated February 11, 1980.

Dear Sir:

This letter transmits a list of pressure isolation valves (PIVs) tested for leak-tight integrity as requested by the subject j

generic letter (GL 87-06). 'Ihe PIVs are those defined as any two 1

normally closed valves in series within the reactor coolant pressure boundary (RCPB) which separate the high pressure reactor coolant system from an attached low pressure system. I:cluded in this list is a description of the periodic tests performed, the acceptance criteria and the frequency of testing.

j All the PIVs which are listed as check valves appear in the IP-3 Technical Specifications on page 4.5-7 of section 4.5.B.2.

This list was added to the 'Ibchnical Specifications in response to an ACRS concern similar to GL 87-06 which arose during the operating license review of IP-3 (Reference 1). The Technical Specifications were modified to require gross leak rate testing to insure the proper positioning of those check valves intended to j

isolate law pressure systems connected to the primary system.

It was concluded by Reference (2) that this was an acceptable method

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.of verifying-proper position.

The low. head injection group of

'these:same valves were also included in the reference:(3)

Econfirmatory order which required testing of the pressure isolation function after each cold shutdown.

Should you or your staff have anycquestions regarding this

. matter, please contact Mr.

P. Kokolakis.of my. staff..

Very.tru yoursb m

o'hn

.' :,rons Executive Vice President Nuclear Generation-

' Attachment-

'cc: U.S. Nuclear Regulatory Commission 631 Park Avenue-King ~of. Prussia, PA 19406 Resident Inspector's Office Indian Point Unit 3 U.S.~ Nuclear; Regulatory Commission P.O. Box 337 Buchanan, NY 10511-Joseph D. Neighbors,' Senior Project Manager PWR Project Directorate I-1

' Division of Reactor, Projects I/II U.S.. Nuclear Regulatory Commission-7920 Norfolk Avenue ~

Bethesda, MD 20014 Marylee M.. Slosson, Project Manager Project Directorate I U.S. Nuclear Regulatory Commission-7920 Norfolk Avenue Bethesda,.MD 20014 1

.+

ATTACHMENT TO IPN-87 032

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REACTOR COOLANT' PRESSURE: BOUNDARY.

PRESSURE ISOLATION VALVES t.

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NEW YORK POWER AUTHORITY

' INDIAN. POINT 3 NUCLEAR POWER PLANT DOCKET No. 50-286 DPR-64 i

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REACIOR CDOIANP PRESSURE BOUNDARY.

l PRESSURE ISOIATION VALVES Notation used in the table extract of valves requiring gross leak testing to verify proper position:

{

VALVE -

The valve alpha-numerical identification.

i 000R

'Ihe location of the valve on the referenced P&ID.

FUNCTION

'Ihe functional system description of the valve.

'IYPE The valve type as follows:

CK Check GA Gate ACT The valve actuator type as follows:

SA Self-actuated MO Motor-operated POS The nonnal position of the valve:

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Open j

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Closed i

L FREQ The required leak test interval as follows:

RR Nczninally every two years during reactor refueling outage.

CS Each cold shutdown IEAK TEST ACCEPTANCE CRITA.nIA:

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'Ibtal corrected leakage is.within limits of plant l--

technical specifications lj 3

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.S_YSTEM:.. Safety In-lection DRAWING NO.:9321-F-27353.

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5 VALVE COOR FUNCTION TYPE' ACT POS FREQ

_ q 838A-

-G3 RHR' Return / LH Inj Loop 1 CK SA~

C.

RR i

CS y

838B'-

H4 RHR. Return / LH Inj Loop 2 CK SA

'C RR CS i

-838C:

I5 RHR Return / LH Inj-Loop 3' CK SA C

RR CS 838D

I6

.RHR Return / LH Inj Loop 4 CK' SA C-RRi CS

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1 4

1

'857A.

B1

-HH Safety:Inj'. to Lp 1 CL CK-SA.

.C.

-RR i

______________HH Safety Inj. to Lp 3 HL 857B' B1

.CK SA C:

'RR, j

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! 857C !

.B1 Boron.Inj. to Loop 4 CL CK:

' SA '

-C RR' 857D C1-BoronLInj. to' Loop.2 CL

.CK

-SA'

.C RR

_____________' Boron Inj. to Loop 1-CL__________________________________'SA-

'_857E.

Cl CK C

RRl 857F-C1

-Boron'Inj. to Loop 3 CL-CK SA C

RR

'857G*.

B2 HH Safety Inj. to Lp 1 CL CK SA' C.

RR i -

857H*-

B2.

HH Safety Inj. to Lp CK SA

.C J

~ RR-i

_3 HL 857J*i 'B2 Boron Inj. to Loop-4 CL CK SA

'C RR 857K*

C2 Boron Inj. to Loop 2 CL.

CK SA C

RR 857L*

C2 Boron Inj. to Loop 1 CL CK SA C

RR 857M*.

C2 Boron Inj.'to Loop 3 CL CK SA C

RR 857Nl D1

, Boron Inj. to Loop 1 HL CK SA C

__________________________________________________________RR 857P*..

D2, Boron Inj. to Loop 1 HL-CK SA C

RR.

857Q Al HH Safety Inj. to Lp 3 CL-CK SA C

.RR e

857R*-

A2 HH Safety Inj. to Lp 3 CL CK SA C

RR

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1 SYSTEM: Safety Iniection DRAWING NO.:9321-F-27353

' VALVE COOR-FUNCTION' TYPE ACT POS FREQ i

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'857S.

Al HH Safety Inj. to Lp lt CL

.CK SA C-

'RR' j

857T*

'A2 HH Safety Inj. to Lp 2 CL CK SA C

.RR.

i 857U Al

HH Safety Inj. to JQp 4 CL CK SA C

RR

'I 857W*

A2 HH~ Safety Inj. to Lp 4 CL CK SA'

'C RR.

.895A G3

-SIS Accum.1 #31 Disch.

CK SA C

RR CS l

j 895B G4

' SIS Accum.,#32 Disch.

CK SA C

RR CS i

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895C G5 SIS'Accum. #33 Disch.

CK SA C

RR

-~ CS -

895D=

G6 SIS Accum.'#34 Disch.

CK SA C

RR CS-q 897A Gl.

SIS Accum. Disch. to LP 1 CL CK 194 C

RR.

CS 897B:

H1 SIS Accum. Disch. to LP 2 CL CK SA

.C RR CS 897C-Il

' SIS'Accum. Disch. to LP 3~CL-

_CK SA C

RR CS 1

897D Il SIS Accum. Disch. to LP 4 CL CK SA C

RR-CS L

SYSTEM: Auxiliary Coolant DRAWING NO.:9321-F-27203

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VALVE COOR FUNCTION TYPE ACT POS FREO i

s 730 B2 RHR Supply From RCS GA MO C

RR I

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~731 B2 RHR Supply From RCS GA MO C.

RR q

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• These check valves constitute the third normally closed. valve in series separating the RCPB from an attached low pressure system ~

and by' definition are not PIVs.

They are included in this list

as the Technical Specifications require gross leak testing to verify proper valve position.

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