ML20035B887
| ML20035B887 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/01/1993 |
| From: | Donnelly P CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9304050247 | |
| Download: ML20035B887 (8) | |
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J g Consumers i.(R%_ '--
P0W8I patrick u conn.iry Rant Marsaw g4 MICHIGAN'S PROGRESS Big Rock Point NucLest Piant.10269 US-31 North, Charlevoix. MI 49720 i
i April 1, 1993 Nuclear Regulatory Commission Document Control Desk i
Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
1992 ANNUAL REPORT OF FACILITY CHANGES, TESTS AND EXPERIMENTS i
Attachment I to this letter is Consumers Power Company's Annual Report l
describing the Facility Changes (FC), Specification Changes (SC), Set point Changes (SPC) performed at the Big Rock Point Plant in 1992. Attachment 2 provides changes to procedures and Attachment 3 reports a test performed in 1992 that are reportable to the NRC per 10 CFR 50.59(b)(2),
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,Cf D 'nm Ol' Patrick M Donnelly Plant Manager i
CC: Administrator, Region Ill, USNRC NRC Resident Inspector - Big Rock Point i
ATTACHMENTS l
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ATTACHMENT 1 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 1992 ANNUAL REPORT Of FACILITY CHANGES, TESTS AND EXPERP#ENTS i
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NUCLEAR REGULATORY COMMISSION 1
- BIG ROCK POINT. PLANT 1992 ANNUAL REPORT - FC/SC/SPC ATTACHMENT 1 t
FACILITY CHANGES (FC) l The Safety Evaluations performed for each of the following Facility Changes concluded that none of the changes constituted an unreviewed safety question.
l FC-643A and FC-6438 Replacement of Cables / Conduit in Recirculation Pump Room
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Installed new conduit and replaced original cables in the recirculation pump room because they were identified as approaching the end of their useful life.
FC-668 Conductivity Monitor Upgrade i
Upgraded selected plant conductivity monitoring equipment to improve the sensitivity of selected monitors and provide trending capability of each monitor in its operable range. This change enhanced early detection of conductivity breakthrough on demineralizers and permits timely response to minimize transients.
r FC-680 Steam Seal Regulator Bypass Replaced manual valve (VTG-0144) with a pneumatically operated control valve to provide automatic closure of the valve under certain plant operating conditions.
FC-681 Sprinkler System Flow Alarm Installation Installation of a water flow alarm in the sprinkler system isc the cable spreading area under the control room.
This alarm alerts personnel in the control room if sprinklers actuate. This installation was the result of NRC Open item 91-16-02.
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NUCLEAR REGULATORY COMMISSION 2-BIG ROCK POINT PLANT 1992 ANNUAL REPORT - FC/SC/SPC ATTACHMENT 1 SPECIFICATION CHANGES (SC)
The Safety Evaluations performed for each of the following Specification s
Changes concluded that none of the changes constituted an unreviewed safety question.
1 SC-91-013 Modification involved changing the configuration of the non-integral attachments for rigid pipe hanger supports (CSH-20 and CSH-21) on the backup core spray line to ensure proper vertical adjustment is provided in supporting the backup core spray line.
l SC-91-020 f
A welded joint designed by General Electric was added to eliminate leakage past an inaccessible control rod drive inner seal ring which allowed excessive flow of drive water.
i 50-92-004 Replace motor leads in V0P-7050 due to environmental conditions, mainly high temperature) with Rockbestos Firewall SR Lead Wire.
This SC was never placed into service; it was superceded by SC-92-006.
SC-92-006 Replace age degradable parts in V0P-7050.
SC-92-011 Addition of NUKON insulation to reactor vessel head to reduce heat loss from the reactor and help mimimize heat load to contaiment.
i Added a length of sacrificial lead to the currert loop of LT-3171 to permit removal without cutting the instrument cable or the transmitter lead.
This will limit the amount of transmitter lead and instrument cable removed during each transmitter replacement.
SET POINT CHANGES (SPC))
SPC-92-002 Increase the setting of the Instrument Air Dryer Regenerator Temperature Controllers from 250 to 350 degrees F after 1991 Instrument Air Quality Test indicated decreased dew point.
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ATTACHMENT 2 CONSUMERS POWER COMPANY BIG ROCK POINT PLANT DOCKET 50-155 1992 ANNUAL REPORT PROCEDURE CHANGES REPORTABLE TO THE NRC I
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NUCLEAR REGULATORY COMMISSION 1
BIG ROCK POINT PLANT 1992 ANNUAL REPORT - FC/SC/SPC
, ATTACHMENT 2 1
PROCEDURES 4
Procedure TR-09 Core Spray Heat Exchanger Shell Side Flow Revision incorporated results of engineering analysis that justified lowering minimum acceptable shell side flow through core spray heat exchanger and use of the annubar flow element and digital meter to measure shell side flow.
Procedure 3.1 Engineering Organization and Responsibilities Revision to revise responsibility of Plant Fire Protection Program from Plant.
Safety Coordinator (position eliminated) to Engineering Superintendent.
There were no requirement revisions, just responsibilities.
i FHSR Chance Section 9.5.1.2.2 Clarifies flow rate requirements for fire pumps associated with NRC Branch Technical Position APCSB 9.5-1.
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-ATTACHMENT 3 7
CONSUMERS POWER COMPANY BIG ROCK POINT PLANT I
DOCKET 50-155 1992 ANNUAL REPORT TESTS AND EXPERIMENTS REPORTABLE TO THE NRC i
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MUCLEAR REGULATORY COMMISSION 1
BIG ROCK POINT PLANT 1992 ANNUAL REPORT - FC/SC/SPC ATTACliMENT 3 TEST AND EXPERIMENTS Procedure SST-37 Control Room Heat-Up Test Following Loss of Ventilation Procedureusedtocollectdataforastationblackoutissuecommitmentdadeto the NRC.
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