ML20029A708

Proposed Tech Spec Surveillance Requirement 4.6.1.2 Re Determination of Containment Leakage Rates

ML20029A708
Person / Time
Site:	Beaver Valley
Issue date:	02/20/1991
From:	DUQUESNE LIGHT CO.
To:
Shared Package
ML20029A706	List: ML20029A705 ML20029A707 ML20029A708
References
NUDOCS 9103040095
Download: ML20029A708 (12)

Text

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. ATIAQlELLT_ A-1 Beaver Valley Power Station, Unit flo . 1 J Proposed Technical Specification Change 11o. 188  ;

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Revise the Technical Specifications as follows:

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9103040095 910220 PDR ADOCK 05000334 P PDR

4 corrAINMENT SYSTEMS CONTATNMENT TR1LKACE LIMITING CONDITION FOR OPERATION 3.6.1.2 containment leakage rates shall be limited tot

a. An ovarall integrated leakage rate of:

1. < L 0.10 percent by weight of the containment air p.,er 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at I' , (40.0 psig), or

b. A combined leakage rate of 0.60 L penetrations 5 a for all and valves subject to Type B and C tests as identified in Table 3.6-1, when pressurized to Pa .

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L, combined a or (b) with the measured Types B leakage and rate for all penetrations and valves subject to C tests exceeding 0.60 L restore the leakage rate (s) to within the limit (s) prior to $n, creasing the Reactor coolant System temperature above 200*F.

SURVEILIANCE REQUIREMENTS 4.6.1.2 The containment leakage rates chall be demonstrated at the following test schedule and shall be determined confermance with the criteria specified in Appendix J of 10 CTR ~

50* using the methods and provisions of ANSI N45.4-1972:

REnrate a. A Type-A test (overall Integrated containment Leakage gg n Rate) shall be conducted at 40 10-month intervals INSERT hy during shutdown at Pa (40.0 psig) .

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• Exemption to Appendix J granted on December 5, 1984. of 10 CTR 50,Section III.D.1(a),

TNIE NT "A" accorelege w A Appmdb 7 of IocTR So 5 l

BEAVER VALLEY - UNIT'l 3/4 6-2 (froposo \c U3 erb )

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., ATIActiME!1T A-2 i

Beaver Valley Power Station, Unit tio. 2 Proposed Technical Specification Change 210. 51 Revise the Technical Specifications as follows:

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CONTAINMENT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION F0F OPERATION

3. 6.1. 2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of 1 L , 0.10 percent by w9 ight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,, (44.7 psig),

b. A combined leakage rate of ( 0.60 L, for all penetrations and valves subject to Type B and C tests as identified in Table 3.6-1, when pressurized to P, (44.7 psig).

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With either (a) the measured overall integrated containment leakage rate exceeding 0.75 L , or (b) with the measured combined leakage rate for all penetrations and, valves subject to Types B and C tests exceeding 0.60 L,,

restore the leakage rate (s) to within the limit (s) prior to increasing the Reactor Coolant System temperature above 200'F.

SURVEILLANCE REOUIREMENTS 4.6.1.2 The containment leakage rates shall be daenstrated at the following test senedule and shall be determined infconformance with the criteria gpgtp, "specified in Appendix J of 10 CFR 50 using the methods and_ provisions _of- WWg tANSIN45.4-1972:j u 4 2NSERT B

a. A Type-A test (Overall Integrated Containment Leakage Rate) shall be conducted at 40 t 10-month intervals during shutdown at P*

(44.7 psig).

b. If any Periodic Type A test fails to meet 0.75 L,, the test schedule for subsequent Type A tests shall-be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet 0.75 L,,

a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L, at which time the above test schedule may be resumed.

l' og INSERT 6 acc.ordawec. u & Appedw 3 ok 10 c58 50 ;

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. l ATTACHMENT D Beaver Valley Power Station, Units No. I and No. 2 Proposed Technical Specification Change No. 188 and 51 Revision of Technical Specification 4.6.1.2 A. DESCRIPTION OF AMENDMENT REQUEST The proposed amendment would delete reference to ANSI N45.4 -

1972 in Surveillance Requirement 4.6.1.2. This surveillance requirement specifies that containment leakage rates shall be determined in conformance with the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 -

1972.

B. BACKGROUND Both Units 1 and 2 Technical Specifications are modeled after NUREG-0457 " Standard Technical Specifications for Westinghouse Pressurized Water Reactors" (STS) which includes reference to ANSI N45.4 - 1972 in Surveillance Requirement 4.6.1.2. Reference to this standard is intended to provide guidance for determining containment leakage rates when conducting Type A tests. This standard is also referenced in 10 CFR 50, Appendix J and is defined as one of the methods by which Type A testa can be conducteo, C. JUSTIFICATION On November 15, 1988, the NRC published in the Federal Reaister (53 FR 45891) a final rule which provided for an alternative method for leakage rate testino. This rule explicitly permits the use of the Mass Point statistical data analysis method for calculating containment leakage rates found in ANSI /ANS 56.8 -

1987 " Containment System Leakage Testing Requirements."

The present wording of Surveillance Requirement 4.6.1.2 only refers to ANSI M45.4 -

1972. This ANSI standard does not recognize the new method of Mass Point statistical data analysis, and only refers to Total Time and Point to Point analysis. As a result, our current wording in Surveillance Requirement 4.6.1.2 will not allow the use of the improved alternative method of calculating containment leakage rates designated as Mass Point analysis.

By deleting the specific reference to ANSI N45.4 - 1972 from the Surveillance Requirement 4.6.1.2, and directing that containment leakage rates be determined in accordance with Appendix J of 10 CFR 50, we will have the flexibility to follow both ANSI N45.4 -

1972 and ANSI /ANS 56.8 -

1987. Additionally, any future changes to 10 CFR 50, Appendix J would be readily adaptable to our procedures since the technical specifications would not require revisions.

Therefore, this proposed change will allow the use of the improved alternative method of calculating containment leakage rates, presently endorsed in Appendix J, and avoid future changes to Surveillance Requirement 4.6.1.2.

ATTACHMENT B, continued Proposed Technical Specification Change Nos. 188 and 51 Page 2 D. SAFETY ANALYSIS Surveillance Requirement 4.6.1.2 is performed to verify that the actual leakage rates from containment are less than or equal to that assumed in the limiting containment DBA analysis.

The deletion of the reference to ANSI N45.4 -

1972 from Surveillance Requirement 4.6.1.2 will not affect the ability of the Integrated Leak Rate Test (ILRT) to determine the actual containment leakage rate. The leakage rate will be determined in accordance with 10 CFR 50, Appendix J which still references ANSI N45.4. The Total Time and Point to Point analysic methods recognized by ANSI N45.4 enn still be used, but the new improved alternative method, Mass Point analysis, may also be used to

-determine actual containment leakage rate. The utilization of the Mass Point analysis will provide at least the same degree of accuracy as the other two methods.

Therefore, this change is considered safe based on the fact that the proposed amendment will allow the use of an approved alternative method to verify containment leakage that has been determined to produce at least the same degree of accuracy as the currently allowed methods. The determination that the actual leakage rates from containment are less than or equal to that assumed in the limiting containment DBA analysis will continue to be performed. The proposed Surveillance Requirement, 4.6.1.2, will continue to ensure that the leak tightness of the containment is maintained to prevent the uncontrolled release of radioactiv. to the environment.

E. NO SIGNIFICANT HAZARDS EVALUATION The no significant hazards considerations involved with the proposed amendment have been evaluated, focusing on the three standards set fcrth in 10 CPR 50.92(c) as quoted below:

The Coamission may make a final determination, pursuant to the procedures in paragraph 50.91, that a proposed amendment to an operating license for a facility licensed under paragraph 50.21(b) or paragraph 50.22 or for a testing facility involves no significant hazards consideration, if operation of the facility in accordance with the proposed amendment would not:

1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or

2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or

3) Involve a significant reduction in a margin of safety.

ATTACHMENT B, continued

. Proposed Technical Specificatior. Change Nos. 188 and 51 Page 3 The following evaluation is provided for the no significant hazards consideration standards.

1. Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?

The actual leakage rates from containment will still be verified to be less or equal to that assumed in the limiting containment DBA analysis.

Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.

2 . Does the change create the possjbility of a new or different kind of accident from any provicosly evaluated?

There would be no change to system configurations, plant equipment or analysis as a result of this proposed amendment. The leak-tightness of the containment will not be affected by this proposed change.

Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any-accident previously evaluated.

3. Does the change involve a significant reduction in a margin of safety?

The maximum allowable containment leakage rate is not affected by this proposed amendment. Maximum containment pressure, temperature and structural integrity remain unchanged.

Therefore, the proposed change does not. involve a significant reduction in a margin of safety.

F. NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION Based- on the considerations expressed above, it is concluded that the- activities associated with this license amendment request satisfies the no significant hazards consideration standards of 10 CFR 50.92(c) and, accordingly, a no significant hazards consideration finding is justified.

ATTACHMENT B, continued

. Proposed Technical Specification Change Nos. 188 and 51 Page 4 G. ENVIRONMENTAL EVALUATION The proposed changes have been evaluated and it has been determined that the changes do not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amount of any offluents that may be released off site, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed changes meet the eligibility criterion for categorical exclusion set torth in 10 CFR 51.22 (c) (9). Therefore, pursuant to 10 CFR 51.22 (b), an environmental assessment of the proposed changes is not required.

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ATTACllMI'NT C-1 Beaver Valley Pouer Station, Unit No. 1 Proposed Technical Specification Change No. 188 Typed Page : 3/4 6-2 l

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CONTAINMENT SYSTEMS

.C_Qb'TAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:

a. An overall integrated leakage rate of:

1. < L, 0.10 percent by weight of che containment air per 34 hours3.935185e-4 days <br />0.00944 hours <br />5.621693e-5 weeks <br />1.2937e-5 months <br /> at P a, (40.0 psig.), or

b. A combined leakage rate of 5 0.60 L for all penetrations and valves subject to Type B and C Seats as identified in Table 3.6-1, when pressurized to P a' APG CABILITY: MODES 1, 2, 3 and 4.

ACTIQN:

With either (a) the measured overall integrated containment leakage rate excee-ling 0.75 L, 3 or (b) with the measured combined leakage rate fcr ad oenetrations and valves subject to Types B and C tests exceeding 0.6) restore the leakage rate (s) to within the limit (s) prict to", increasing the Reactor Coolant System temperature above 200*F.

SURVEILLANCE REQUIREMENTS

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4.6.1.2 The containment leakage rates shall be demonstrated at the following tett schedu and shall be determined in accordance with Appendix J of 10 CFR 50}e:

a. A Type-A test (Overall Integrated Containment Leakage Rate) shall be conducted at 40 i 30-month intervals during shutdown at Pa (40.0 psig).

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• - Exemption to Appendix J of 10 CPR 50,Section III.D.l(a),

granted on December 5, 1984.

BEAVER VALLEY - UNIT 1 3/4 6-2 (Proposed Wording)

A T T A C ilM I;!J T C - ?

Beaver Valley Power Station, Unit 11 0 . 2 Proposed Technical Specification Change 11 o . 51 Typred Page : 3/4 6-2

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, CQJ{TAINMENT SYSTEMS CONTAINMENT LEAKAGE 1

i; LIMITING CONDITION TOR OPERATION 3.6.1.2' Containment leakago rates shall be limited to:

4 a. An overall integrated leakago rate-of 5 L , 0.10 percent i by weight of the containment air per 2k hours at P a' (44.7 psig). )

b. A combined leakage rate of < 0.60 Ls for all penetrations and valves subject to Type B and C tests as identified in Table 3.6-1, when pressurized to P a (44*7 P819)*

APPL 2CABILITY: MODES 1, 2, 3 and 4.

h.CTION:

i With either. (a) the measured overall integrated containment Ica.':ago rate excooding 0.75 L or (b) with the measured combined leakage rate for all. penetratio,ns and valvos subject to Types B and C tests exceeding 0.60 L, a restore the Icakage rate (s) to within the limit (s)- prior to increasing the Reactor Coolant System temperature

.above 200'F.

SURVEILLANCE REQUIREMENTS

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1 The containment Icakago rates shall be demonstrated at the

' - 1.2 foilowing test schedule and shall be datormined in accordance with Appendix J of.10 CFR 50:

a. 'A Type-A test (overall Integrated containment Leakago Rato) shall be conducted at 40 1 10-month intervals during shutdown at P a (44*7 psi 9)*

b . _- If any Periodic Type A test _ fails to meet 0.75 La , the test schedule for subsequent Type A tests shr.'.1 be reviewed and approved by the Commission. If two co r.ocutive Type A tests fall to moot 0.75 L,- a Typo A test shall bo

_ performed .at Icast every 10 months unti' two consecut.tvo Type A tests _ moet 0.75 L a at which time the above tost-schedule may be resumed.

1 BEAVER VALLEY - UNIT 2 3/4 6-2 (Proposed Wording)

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