ML20002C809
| ML20002C809 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/17/1978 |
| From: | Bixel D CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20002C810 | List: |
| References | |
| NUDOCS 8101120055 | |
| Download: ML20002C809 (6) | |
Text
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L POWct Company General Offices: 212 West Machigan Avenue, Jackson, Micnigan 49201. Area Code 517788-0550 May 17, 1978 Director, Nuclear Reactor Regulation Att: Mr Dennis L Ziemann, Chief Operating Reactors Branch No 2 US Nuclear Regulatory Coc=ission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - T/S CHANGE ILRT Transmitted herewith are three (3) original and thirty-seven (37) confer:ed copies of a proposed change to the Technical Specifications for the Big Rock Point Pltint, Docket 50-155, License DPR-6.
The purpcse of. the change is to incorporate portions of 10 CFR 50, Appendix J, into the Big Rock Point Technical Specifications and to reiterate the tech-nical justification for not performing an integrated leak rate test during the 1978 refueling outage.
In discussions with yo:1r staff, it has become apparent that completed staff review of Consumers Power Company's past sub-mittals concerning Appendix J Technical
- Specifications and exemptions vill not be ecmplete prior to the scheduled 1978 refueling outage. Thus, approval of the proposed change is necessary prior to September 1,1978 in order to ensure that appropriate planning is ec=pletc for the scheduled outate.
The proposed changes are taken directly from 10 CFR 50, Appendix J, and are updates of previous submittals. As such, it is concluded that they are A
purely ad=inistrative in content and should be categorized as Class II.
check for the appropriate amount is attached.
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David A Bixel Nuclear Licensing Administrator CC: JGKeppler, USNRC 1
878//966SS~
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CONSGIERS POWER COMPANY Docket 50-155 Request for Change to the Technical Specifications License DPR-6 For the reasons hereinafter set forth, it is requested that the Technical
-Specifications contained in Facility qperating License DPR-6, Docket 50-155, issuedtoConsumersPowerCompanyonhay1,1964fortheBigRockPointPlant g
6 be changed as described in Section I below:
I.'
Changes A.. Delete Section 3.T.(f) and replace with the following:
(f) If two consecutive integrated leak rate tests fail to meet the specifications contained in this section, then an ILRT shall.be performed at each plant shutdown for refueling or appr'oximately 18 months, whichever occurs first, until two consecutive ILETs meet the acceptance criteria. After the above special retest requirement is satisfied, then the testing schedule outlined in 3.T.E may be resumed from the date of the last special test (ie, about 3-1/2 years after completion of the second consecutive satisfactory special test).
B.
Delete Section 3.7.(g) and replace with the following:
(g) All leakage rates determined by~a test pressure less than the applicable design pressure (containment de-
' sign or design basis accident) shall be corrected using the following for=ula:
Lg=L (P /P ) !
Lg = % measured leakage rate, at test pressure.
Le = % leakage rate, at extrapolated pressure.
P = Test pressure (PSIG).
t P, = Extrapolated pressure (PSIG).
Acceptance criteria on allevable leakage is.75 L.
NOTE: Corrected Technical Specifications pages are attached.
1 II)I/Uu% f_
f II.
Discussion-Change A is proposed to. update the Big Rock Point Technical Specifica-tions to meet the criteria established in 10 CFR Part 50, Appendix J, Section III.A.6.(b),in terms of required integrated leak rate retest requirements. This change is in full confor=ance with the cited section of 10 CFR 50, Appendix J; therefore, needs no further technical justifi-cation. When approved, this change will allow the scheduling of the next Big Rock Point Plant integrated leak rate test for the 1980-81 refueling outage; justification for which was presented in Special Report 27, dated February 3,1978, and is attached for convenience.
Change B is proposed to incorporate the formula for maximu= allowable i
leakage rate (L ), as it exists in 10 CFR 50, Appendix J, See-g tion III.A.h.(a),(1).(iii), into the Big Rock Point Technical Specifi-cations since the current Technical Specifications formula is needlessly conservative. The factor of.75 represents the acceptance criteria as specified in Section III.A.h.(a).(2) of Appendix J.
Again, since'the proposed formula is consistent with Federal regulations, no further technical justification is necessary.
i III. Conclusion Based on the foregoing, both the Big Rock Point Plant Review Co=mittee and the Safety and Audit Review Board have concluded that this change is acceptable.
CONSUMERS POWER COMPANY 37 f
C R Bilby, Vice P2j4 spent Production & Transa.ission Swcrn and subscribed to before me this 17th day of May 1978.
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All
~ Lilida R Thayer, ITotary %blic Jackson County, Michigan-My ec= mission expires July 9, 1979 2
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3.7'(Contd) i leakage rate shall yield an overall leakage rate not greater
.than 0.5%/ day at 27 psig.
(d) A containment sphere integrated leakage rate test of at least 2h-sours duration shall be performed at a pressure not less than 10 psig. Although routine maintenance may be performed, repairs to items listed in 3 7 (a), -(b) and (c) shall not be made inmediately prior.to or during the test.
The accuracy of the leakage rate measuring system shall be verified.(1) by superimposing a controlled leakage rate equivalent to the allowable leakage rate at the test pres-sure (measured through a gas flowmeter) upon the existing leakage rate and continuing the test a sufficient period of time to measure the composite leakage, or (2) by other means of equivalent accuracy.
If the leakage is in excess of 0.5%/ day of contained atmos-phere (weight basis) at the design prissure (27 psig) or extrapolated to the design pressure, repairs shall be made and the leakage rate test repeated until the 0.5%/ day of contained atmosphere (weight basis) specification is met.
(e) An integrated leakage rate test shall be conducted on the containment sphere at approxi=ately three equal intervals during each 10-year service period.
(f) If two consecutive integrated leak rate tests fail to meet the specifications contained in this section, then an ILRT shall be performed at each plant shutdown for refueling or approximately 18 months, whichever occurs first, until two consecutive ILRTs meet the acceptance criteria. After the above special retest requirement is satisfied, then the testing schedule outlined in 3 7.E =ay be resumed from the date of the last special test (ie, about 3-1/2 years after completion of the second consecutive satisfactory special test).
l (g) All leakage rates determined by a test pressure less than the applicable design pressure (containment design or de-sign basis accident) shall be corrected using the following formula:
+; -
' ll e
-'3 7-(Conta)
-(g)
(Contd) e (P /P,) !
L
- b t
t L = 5 measured leakage rate, at test pressure.
t L,= % leakage rate, at extrapolated pressure.
P = Test pressure'(PSIG).
t P,= Extrapolated pressure (PSIG).
' Acceptance criteria on allowable leakage is.75 L.
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p5 19/ W REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-155 REC: ZIEMANN D L ORG: BIXEL D A DOCDATE: 05/17/78 NRC CONSUMERS PWR DATE RCVD: 05/19/78 COPIES RECEIVED DOCTYPE: LETTER NOTARIZED: YES LTR 3 ENCL 40
SUBJECT:
FORWARDING LiC NO DPR-6 APPL FOR AMEND: TECH SPEC PROPOSED CHANGE CONCERNING REITERATE TECH SPEC JUSTIFICATION FOR NOT PERFORMING AN INTERGRATED LEAK RATE TEST DURING THE 1978 REFUELING OUTAGE.
NOTARIZED 05/17/78.. W/ATT.
REV'2WER INITI AL:
XJM PLANT NAME: BIG ROCK PT DIS.RIBUTOR INITI AL: 4 occo************* DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE A001)
FOR ACTION:
BR CHIEF y 4N**W/7 ENCL INTERNAL:
<EG EILEPMJ/EF NRC PDR**W/ ENCL I & E**W/2 ENCL OELD**LTR ONLY HANAUER**W/ ENCL CHECK **l' ' ENCL EISENHUT**W/ ENCL SHAO**W/ ENCL BAER**W/ ENCL BUTLER **W/ ENCL EEB**W/ ENCL J COLLINS **W/ ENCL i
J.
MCGOUGH**W/ ENCL EXTERNAL:
LPDR'S l
CHARLEVOIX. MI**W/ ENCL I
-TIC **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL 000$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$
CHECK NBR:C 20, 293 C
AMOUNT:
$1,200.00 CHECK AND COPY OF TRANSMITTAL LTR ADVANCED 0
TO W.
MILLER (LFMD) (05/19/78) UPON RECIEPT DISTRIBUTION:
LTR 40 ENCL 39 CONTROL NDR:
7010^^922 SIZE: 1P+7P inco*******************************
THE END s
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