ML20002C795
| ML20002C795 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 07/28/1978 |
| From: | Bixel D, Youngdahl R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Desiree Davis Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20002C796 | List: |
| References | |
| NUDOCS 8101120021 | |
| Download: ML20002C795 (4) | |
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@n "'r d c-d C0mpany Generet omces: 212 West Michigan Avenue, Jackson. Michigan 49201. Area Code 517788-0550 July 28,1978 Director of Nuclear Reactor Regulation Att: Mr Don K Davis, Acting Branch Chief Operating Reactors Branch No 2 US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT - T/S CHANGE REQUEST:
INCREASING ROD SPEED SURVEILLANCE INTERVAL Trans=itted herewith are three (3) original and thirty-seven (37) conformed copies of a proposed change to the Technical Specifications of the Big Rc 3 Point Plant, Docket 50-155, License DPR-6.
The purpose of this change is to increase the required time interval to perform rod withdrawal timing tests. Approval of this Technical Specifications change request is necessary to prevent a forced outage necessitated by the current Technical Specifications rod withdrawal timing surveillance require-ments. As such, approval of this test is required by September 1, 1978.
It should be noted that submittal of this change in no way supersedes or replaces the Technical Specifications change request dated November 1, 1974. This submittal provided, justification for the deletion of the rod withdrawal timing surveillance and limitations and has not yet received staff review.
It is determined that this change request qualifies as a Class III A=endment since there is a single safety issue under consideration. A check for the.
appropriate amount is attached.
David A Bixel Nuclear Licensing Administrator CC: JGKeppler, USNRC 762 4 avg 5 i k2 3(
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t 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 Specifications contained in Facility Operating License DPR-6, Docket 50-155, issued to Consumers Power Company on May 1, 196h for.the Big Rock Point Plant be changed as described in Section I below:
I. : Change A.
Change the periodicity of Section 5 2.2(a)(1) from "during each major refueling shutdown and at least once every six months during periods of power operation" to "each major refueling."
4 NOTE:
Corrected Technical Specifications are attached.
II.
Discussion By letter dated July 19, 19Tk, Consumers Power Company described temperary
. corrective action implemented at Big Rock Point to eliminate the possi-
- bility of exceeding the 23-second control rod withdrawal time limit of Technical Specification Section 5.2.2(a)(i). This temporary measure involved lifting and insulating Lead 1 on the 1/lT contacts of the con-
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trol rod positioning jog-run hS5 switch, disabling the ability to with-l draw control rods in the continuous run mode. The continuaus run mode is only reenabled during periods when the reactor is in the shutdown condition, primarily to perform control rod drive surveilk m:e testing requirements of Section 5 2.2(a).
A Technical Specifications change request was submitted to the NRC on November 1, 1974 to delete the minimum continuous rod with-drawal rate limit and eliminate the need to disable the continuous run 4
feature. As of this date, this Technical Specifications revision has not been approved and the temporary measures eliminating continuous run remain in effect.
The control rod drive surveillance tests required by Section 5 2.2(a) become due once again during the first week of September 1978. These tests are currently planned to be performed during power operation.
Since the ability to test and time continuous withdrawal is no longer if
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=possible because of the controls in effect, relief from Section 5 2.2(a)(i) will be required.
It is requested that the surveillance interval for timing continuous withdrawal be changed from every six months to each major refueling. outage.
The-temporary measures controlling the continuous run feature vill remain in effect during power operation precluding the possibility of exceeding the existing 23-second withdrawal limit. Once approved, the Technical Spet ifications request of November 1,1974 vill eliminate the concern of excessive withdrawal speeds and bring Big Rock Point Technical Specifications in line with current BWR Standard Technical Specifications which require no surveillance of.this type.
It is requested.that this change be approved by Septe=ber 1, 1978 to pre-vent a forced outage necessitated by the current Technical Specifications rod-withdrawal timing surveillance requirements.
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 from a safety standpoint.
CONSUMERS POWER COMPANY By
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R C Youngdahl, ecutiv Vice President Sworn and subscribed to before me this 28th day of July 1978.
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" Lffnda R Thayer,. Notary ublic Jackson County, Mic agan My commission expirep.Tuly 9, 1979 l
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-155 REC: DAVIS D K ORG: BIXEL D A DOCDATE: 07/28/7C NRC CONSUMERS PWR DATE RCVD: 07/31/
DOCTYPE: LETTER NOTARIZED: NO
SUBJECT:
COPIES RECEIVEE LTR 3 ENCL 4C FORWARDING LIC NO DPR-6 APPL FOR AMEND: TECH SPEC PROPOSED CHANGE CONCERNI INCREASING THE REQUIRED TIME INTERVAL TO PERFORM ROD WITHDRAWAL TIMING TESTS.,
NOTARIZED 07/28/78.. W/ATT LIC FEES.
PLANT NAME: BIG ROCK PT PEVIEWER INITI AL:
XJM DISTRIBUTOR INITIAL: (
eco**************
DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS *****************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRIBUTION CODE AOO1)
FOR ACTION:
BR CHIEF ORB #2 BC**W/7 ENCL
'T INTERNAL:
REG FILE **W/ ENCL.
NRC PDR**W/ ENCL
'I L E**W/2 ENCL OELD**LTR ONLY HANAUER**W/ ENCL CORE PERFORMANCE BR**W/ ENCL AD FOR SYS & PROJ**W/ ENCL ENGINEERING BR**W/ ENCL REACTOR SAFETY BR**W/ ENCL PLANT SYSTEMS BR**W/ ENCL CEB**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 0$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$$
0 CHECK NBR:C32. 642 5
AMOUNT:
$4,000.00 CHECK AND COPY OF TRANSMITTAL LTR ADVANCED TO W.
MILLER (LFMG) (07/31/78) UPON RECIEPT DISTRIBUTION:
LTR 40 ENCL 39 CONTROL NBR:
75212v392 SIZE: 1P+0P ocoo*******************************
THE END P00R OR M W
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