ML20002C798
| ML20002C798 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/27/1977 |
| From: | Bixel D, Youngdahl R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Desiree Davis Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20002C799 | List: |
| References | |
| 780727, NUDOCS 8101120029 | |
| Download: ML20002C798 (6) | |
Text
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t CORSUmBTS L POVlCr R_i_n,5,fl V f _ifiT....
.- m y E T ". ". C".'J.G Ompany General Offices: 212 West MichiQan Avenue. Jackson Mechigan 4920f e Area Code S17 788-OSSO July 27, 1978
[66 Director of Nuclear Reactor Regulation
-Att: Mr Den K Davis, Acting Branch Chief
-Operating Reactors Branch No 2 US Huclear Regulatory Comission Washington, DC 20555 DCCFIP 50 155 - LICENSE DPR BIG ROCK FOILT PLAUT - TECHNICAL SPECIFICATICUS CHAHGE REQUEST:
ISI Transmitted herewith are three (3) original and thirty-seven'(37) conformed copies of a propcsed change to the Technical Specifications of the Big Rock Point Plant, Docket 50-155, License'DPR-6.
The purpose cf this submittal is to inecrporate the provisions of 10 CFR 50 55a(g) into the Big Rock Point Technical Specifications.
Since the changes involve a single safety issue and reflect a current 'EC position, it is con-cluded that the propesal should be defined as a Class III amendment. A check for the appropriate amount is attached.
This change should be effective at the completion of Inservice Inspection Uo 6 which is approxi::ntely February 1,1979 Y
David A Bixel Nuclear Licensing Administrater CQ:. JGKeppler, USNRC
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I CONSUMERS 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
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Specifications contained in Facility Operating License DPR-6, Docket 50-155, is:ued to Consumers Power Company on May 1,196h for the Big Rock Point Plant be changed as described in Section I below:
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Changes
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- 1.. Replace "every '12 months" in Sections 3 7.b and 3.7.c with "each reactor shutdown for refueling but in no case at intervals greater than'two years."'
2.
Delete Sections 9 1, 9.2, 9 3 and _9.4~, and Tables 9.3(a) and 9.3(b).
j Replace'these with aev' Sections 9.1, 9.2, 9.3 and 9.4 as follows:
90 PRIMARY SYSTE4 SURVEILLANCE 91 APPLIC. LITY Applies to preoperational and inservice structural surveillance of the reactor vessel and other Class 1, Class 2 and Class 3 system components.
t 9.2 OBJECTIVE To insure the integrity of the Class 1, Class 2 and Class 3 piping j
systems and components.
l 93 SPECIFICATI0HS a '. The structural integrity of ASME Classes.1, 2 and 3 components, l
as determined by 10 CFR 50, Section 50.55a, shall be verified and maintained at an acceptable level in accordance with l
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Section XI of the ASMI B&PV Code with applicable addenda as required by 10 CFR 50, Section 50 55a(g), except where specific relief has been granted by the NRC.
b.
' Inservice testing of ASME Classes 1, 2 and 3 pu=ps and valves.
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as determined by 10 CFR 50, Section 50 55a, shall be performed in accordance with Section XI of the ASMI B&PV Code with ap-plicable addenda as required by 10 CFR 50, Secticn 50.55a(g),
except where specific relief has been granted by the NRC, and where provisions of Sections 11.h.1.h, k.1.5 and 11.h.3.h take preceden'ce.
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1:.. Sufficient records of each inspection _shall be kept to allow
~ comparison and evaluation of future tests.
(See also Sections 6.9 4 and 6.10.2.g.)
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The inservice. inspection' program shall be reevaluated as required by 10 CFR 50, Section 50.55a(s)(5) to consider incorporation of new inspection techniques that have been proven practical, and r
the conclusions of the evaluation shall be used as appropriate L
to update the inspection program, A surveillance.piogram to monitor radiation induced changes in e.
the mechanical and impact properties of the reactor vessel.
materials shall be maintained as described in Section h.l.l(h) of these Technical. Specifications.
9.h BASIS' The inspection program implementsSection XI of the ASME Boiler and.
Pressure Vessel Code to the maximum extent practical. It is recognized that: plant design and construction vere ecmpleted approximately seven years prior to the development of Section XI and it is, therefore, not possible to comply fully with the code.
3.
Delete Section h.l.2(c)3 h.
Under Reactor Depressurization System, change Section h.l.5. A to read as follows:
"A.
The isolation valves shall be test-operated at least-once every three months "
NOTE: Corrected Technical Specifications pages are attached.
II.
Discussion Proposed Change 1 to the Big Rock Point Technical Specifications vould simply change the surveillance interval for specific integrated leak rate tests from every 12 months to each reactor refueling (not to exceed intervals greater
-than two years). This change would make the Technical Specifications wording consistent with Section XI of the Boiler and Pressure Vessel Code and with the criteria of 10 CFR 50, Appendix J.
The propo, sed Change 2 to the Big Rock Point Technical Specifications reflects the-verding and intent of your letters of April 28, 1976, November 2h, 1976 and January 16, 1978 pertaining to inservice inspection requirements.
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i In general, proposed Sections 91 and 9 2 deal with the upgrading of the Technical Specifications, incorporating Class 2 and Class 3 systems irto the inservice structural surveillance program as required by 10 CFR 50 55a(g).
Section 9 3.a has been altered to require updating inspection programs to the applicable addenda of Section XI of the ASME Boiler and Pressure Vessel Codes. Section 9 3.b reflects the ausnereation of a pu=p and valve progra=
into the primary system surveillance program. Finally, Section 9 3.d has been added to comply with the requirements of 10 CFR 50.55a(g) requiring periodic updating of the inservice inspection prcgram based upon new inspection techniques that have proven to be practical.
Since a submittal requesting relief from specific code requirements and centaining a description of the planned inservice inspection and testing programs will be developed, all references to code relief and testing and inspection methodology have been deleted from the current Big Rock Point Technical Specifications. This is consistent with the intent of having the nechanics of the approved plan independent of the Technical Specifi-cations and thereby simplifying the process for incorporating changes.
One final change that is incorporated in the proposed Technical Specifica-tions changes is that deleting augnented interim surveillance requirements for high energy lines. This interim surveillance program vas incorporated in Amendment 8 to the Big Rock Point Technical Specificatier.s dated November 11, 1974 and was intended to remain in effect until the modifica-tions described in our letter of June 29, 1973 were completed. Since these modifications have been completed and documented (reference the Big Rock Point 1976 Annual Report dated February 25,1977), it is requested that the interim surveillance requirements be deleted, and that surveillance required by the inservice inspection program be restaed.
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. Conclusion-Based on'the foregoing, both the Big Rock Point Plant. Review Co=mittee and i--
the Safety and Audit Review Board have concluded that these. changes are
. acceptable from a safety standpoint.
CONSUMERS' POWER 01 ANY By
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_/Ilt t,,Ma R C Youngdahl, E ecutiv Vice President-Sworn and subscribed to.before me this 27th' day of July 1978.
AfY W
Linda R Thayer, Notaryptublic Jackson County, Midfiigan My commission expires July 9, 1979 e
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-155 REC: DAVIS D K ORG: BIXEL D A DOCDATE: 07/27/78 NRC CONSUMERS PWR DATE RCVD: 08/01/78 DOCTYPE: LETTER NOTARIZED: YES COPIES RECEIVED
SUBJECT:
LTR 1 ENCL 1 FORWARDING LIC NO DPR-6 APPL FOR AMEND: TECH SPEC PROPOSED CHANGE CONCERNING REVISION TO THE PRIMARY SYSTEM SURVEILLANCE, APPLICABLE TO PREOPERATIONAL AND INSVC STRUCTURAL SURVEILLANCE OF THE REACTOR VESSEL AND OTHER CLASS 1, 2,
t< 3 SYSTEM COMPONENTS.. NOMEt7c0 $J7/78 PLANT NAME: BIG ROCK PT REVIEWER INITI AL:
XJM DISTRIBUTOR INITIAL:g ococoo*********** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICEN3E.
(DISTRIDUTION CODE AOO1)
FOR ACTION:
ER CHIEF ORB #2 BC**W/7 ENCL
)
INTERNAL:
hEG FILE **W/ ENCL NRC PDR**W/ ENCL I & E**W/2 ENCL OELD**LTR ONLY HANAUER**W/ ENCL CORE PERFORMANCE BRk*W/ ENCL AD FOR SYS & PROJ**W/ ENCL ENGINEERING BR**W/ ENCL REACTOR SAFETY CR*xW/ ENCL PLANT SYSTEMS BR**W/ ENCL EEB**W/ ENCL EFFLUENT TREAT SYS**W/ ENCL J.
MCGOUGH**W/ ENCL EXTERNAL:
LPDR'S CHARLEVOIX. MI**W/ ENCL TERA **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL Lept 2 DIGTRIBUTION:
LTR 40 ENCL 39 CONTROL'NDR:
78g12OO38
' SIZE: 1P+4P5P
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