ML20197E848

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Replacement Pages 160 & 279 & mark-up Pages to Proposed TS Change 190 Containing Editorial Changes
ML20197E848
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 12/22/1997
From:
VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20197E846 List:
References
NUDOCS 9712300089
Download: ML20197E848 (4)
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TABLE 4.7. .

(Cont'd)

PRIMARY CotrTAINMEttr ISOLAT10N VALVES

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TV[E C EIAKAGF/ TESTS /

/ / / / t t launber of Power Operated Valves Maximum Action on Isolation * '

Group (1) Valve Identification _ Inboard Outboard Time (sec) Position Stonal 3 Exhaust to Standby Cas Treatment Syste's 1 10 open GC 116-19-6)

Containment Purge Supply (16-19-23) 1 10 3 Open

@ ar.

3 n eup hI HA Closed SC ,

5 Reactor cleanup System (12-15, 12-18) 1. 1 25 open cc l 6 HPCI (23-15, 23-16) 1 1 55 open GC 6 RCIC (13-15, 13-16) 1 1 20 open cc Primary / Secondary Vacuum. Relief (16-19-11A. 2 NA Closed SC 16-19-118)

Primary / Secondary Vacuum Relief (16-19-12A, 2 NA Closed Process 16-19-128)

Containment Air Sampling (VG 23, VG 26, 4 l 3 109-7 6AI.8) 5 open m Feedwater Check Valves (V2-27A, -96A, -28A, NA open Process

-28B) 4 00

/ v v ~ <

Conta.amut Ab.up supply O'-2.o-2o,is-2o-228 2. 5 DM GC,

- - A ~ ~

9712300009 971222 pDR ADOCK 05000271 p PDR r ,.. . - i . 1, , .. tr . (n t. 74 m. I?'

VYNPS 4 An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous offluents and/or quantity of solid waste that diffor from those previously predicted in the license application and anwmdments thereto -

5. An evaluation of the change, which shows the expected maximum exposures to member (s) of the public at the site boundary and to the general population that differ ~from those previously estimated in the license application' and c.mendments theret.or
6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous offluents and in solid waste, to the actual releases for the period prior to when the cha.ges are to be made:
7. An estimate of the exposure to plant operating personnel as a result of the chances and
8. Documentation of the f act that the change was re viewed and found acceptab?e by PORC.

B. Shall become of f active upon review and acceptance by PORC and approval by the Plant Manager.

L, --

N 6.15 Primary containment Leak Pate Testino Procram A program shall be established to implement the leak rate test ing ,

of the primary containment as required by 10CTR50.54(o) and 10CTR50, Appendix J, option B as modified by approved exernptions.

This program shall be in accordance with the guidelines contained i in Regulatory Guide 1.'.63, entitled 'Perf orTnance Based Contair.sent [

[ t.eak. Test Program," dated September 1995.

The peak calculated containment internal pressure for the dosi an I basia loss of coolant accident, Pa, is 44 peig.

The maximwn allowe.ble primary containment leak rate, La, at Pa shall be 0.8% of primary containment air weight per day, Leak rate acceptance criteria aret

1. Primary containment link rate acceptance criterion i 1.0 La.

.2. The as-left primary containment integrated leak rate test (Type A test) acceptance criterion is 1 0.75 1.a.

3 The coa 61ned local leak rate test (Type 8 and C tests) acceptance criterion is L 0.60 La, calculated on a maximwn pathway basis, prior to eatering a mode of operation where

. containment integrity is sequired.

'4. The combined local leak rato test (Type B cnd C tests) acceptance criterion is 1 0.60 La, calculated on a minimum pathway basta. at all times when primary containment integrity.is required.

5. Airlock overall leak rate acceptance criterion is 1 C.10 La

, - when tested at 1 Pa.

.The provision of 'he Definition (1.0.Y) for surveillance Frequenca

- does not apply to the test frequencies specified in'the Primary Containment Leak Rate Testing Program.

Amendment No.;41,i95 279 l e

VYNPS '

l TABLE 4.7.2 (Cont'd)

PRIMARY CONTAIh m ISOLATION VALVES

. I i

[ Number of Power Operated Valves Maximum Action on Isolation Operating Normal. Initiating Group (1) Valve Identification Inbeard Outboard Time (sec) Position Signal

3. Exhaust.to Standby Gas Treatment System 1 10 Open GC (16-19-6) l 3 Containment Purge Supply (16-19-23) 1 10 . Cloned SC i l 3 Containment Makeup Supply (16-20-22A) 1 NA Closed SC

, 3 Containment' Makeup Supply (16-20-20, 2 5 Open GC 16-20-22B) i 5 Reactor Cleanup System (12-15, 12-18) 1 1 25 Open GC 6 HPCI (23-15, 23-16) 1 1 55 Open GC 6 RCIC-(13-15, ?3-16) 1 1 20 Open GC Primary /Seconcary Vacuum Relief (16-19-11A, 2 NA Closed SC 16-19-11B)

Primary / Secondary Vacuum Relief (16-19-12A, 2 NA Closed Process

, 16-19-12B) 3 Containment Air Sampling (VG 23, VG 26, 4 5 Open GC 109-76A&B)

Feedwater Check Valves (V2-27A, -96A, -28A, NA Open Process

-28B)

Amendment No. 54, M, -74, M, MG, 160

- - -_. . ....- - -- - - - - . ..- - -_ . _ . - = ~ ... .. .

1

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4. An evaluation of the change, which shews the predicted releases of radioactive materials in liquid and caseous i

- effluents-and/or quantity of solid waste that differ '

i from those previously predicted in the licenan application a.nd an endments thereto  !

l S. An evaluation of the changes which shows the expected maximum exposures to member (s) of the public at the site i boundary and to the general population that differ from those previously estimated in the license application l

. and amendments thereto;  ;

(t A comparison of the predicted releaaes of radioactive 4

6.

materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to  ;

when the changes are to be medes

7. An estimate of the exposure to plant operating personnel l as a result of the change; and
8. Documentation of the fact that the change was reviewed and found acceptable by PORC.
B. Shall become effective upon review and acceptance by PORC and approval by the Plant Manager.  ;

0.15 Primary Containment Leak Rate Testino Pronram

'A program shall be established to implement the leak rate testing  ;

of the primary containment as required by 10CFR50.54(o) and i 10CFR50, Appendix J. Option B as modified by approved exemptions. l This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, entitled " Performance Based Containment Leak-Test Program," dated September 1995. ,

The peak calculated containment internal pressure for the design .

basis loss of coolant accident, Pa, is 44 psig.

l The maximum allowable primary containment leak rate, La, at Pa, shall be 0.8% of primary containment air weight per day.

Leak rate acceptance criteria are

1. Primary containment leak rate acceptance criterion 1 1.0 La.
2. The as-left primary containment integrated leak rate test (Type A test) acceptance criterion is 1 0.75 La.
3. The combined local leak rate test (Type B and C tests) acceptance criterion is 1 0.60 La, calculated on a maximum pathway basis, prior to entering a mode of operation where containment integrity is required.
4. _The' combined local leak rate test (Type B and C tests) acceptance criterion is 1 0.60 La, calculated on a minimum

. pathway. basis, at all times when primary containment integrity is required.

5. Airlock overall leak rate acceptance criterion is 1 0.10 La when tested at 1 Pa, The_ provision'of the Definition (1.0.Y) for Surveillance Frequency I

-does not apply-to the test frequencies-specified in the Primary '

Containment Leak Rate Testing Program. i Amendment.No. 83, 95, 279 i

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