ML20210A900
| ML20210A900 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 05/01/1987 |
| From: | Johnson B CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| References | |
| NUDOCS 8705050187 | |
| Download: ML20210A900 (18) | |
Text
I Consumers
@ POWERING MKHoGAN'S PROGRE.55 Power General Offices: 1945 West Parnall Road, Jackson, MI 49201 * (517) 788-0550 May 1, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -
1986 ANNUAL REPORT OF FACILITY CHANGES, TESTS AND EXPERIMENTS Attached is Consumers Power Company's Annual Report describing the Facility Changes (FC), Specification Changes (SC), tests and experiments performed at the Big Rock Point Plant in 1986. This report is submitted in accordance with the provisions of 10CFR50.59(b). A delay in the submittal had been requested per telephone conversations with NRC Washington prior to the normal March 31 due date. Please note that this report has three sections:
- 1. Those Facility Changes, Specification Changes, Set point Changes, test and experiments completed in 1986.
- 2. Those Facility Changes, Specification Changes, Set Point Changes, test and experiments which have had Operability Authorization prior to December 31, 1986, but have not been officially closed out.
- 3. 1986 Procedure Changes reportable to the NRC.
.... i fn Brian D Johnson Staff Licensing Engineer CC Administrator, Region III, NRC NRC Resident Inspector - Big Rock Point Attachment 55 W9 PDR OC0387-0026-NLO2 9y lll
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i ATTACHMENTS i
!' Consumers Power Company i Big Rock Point Plant Docket 50-155 1
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} FACILITY CHANGES, SPECIFICATION CHANGES TESTS AND EXPERIMENTS i
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. ATTACHMENT I Consumers Power Company Big Rock Point Plant Docket 50-155 FACILITY CHANGES, SPECIFICATION CHANGES, TESTS AND EXPERIMENTS Completed During 1986 9 Pages MI0187-1241A-BT01-NLO4
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ATTACHMENT I Facility Changes (FC)
FC-465A: Spent Fuel Racks This change consisted of the installation of new fuel racks to increase the spent fuel storage capacity.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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FC-545: Control Room Air Conditioning l
This change consisted of providing adequate cooling for control room environment by utilizing well water instead of service water for cooling.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-577: Office Building This change consisted of installation of a modular office trailer complex east of the training classrooms in order to consolidate personnel (including personnel that were occupying a warehouse with inadequate fire exits) and eliminate satellite office t, railers.
The safety evaluation concluded that this change did not constitute an
, unreviewed safety question.
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( FC-587: Public Address System Additions This change consisted of installation of additional public address system speakers in the Radwasta Storage Facility and the Laundry Room to eliminate personnel safety concerns.
The safety evaluation cencluded that this change did not constitute an unreviewed safety question.
FC-589: Shop Frisker & Locker Room Outlets This change consisted of installation of additional 120V ac outlets in the shop and locker room areas to handle additional equipment.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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j 2 FC-592: Respirator Decontamination Station j This change consisted of installation of a respirator decontamination station j
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separate from the acceas control area to relieve overcrowded conditions during refueling outages.
'The safety evaluation concluded that this change did not constitute an j unreviewed safety question.
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-FC-601: Sealing Steam Bypass Line This change consisted of installation of a three (3) inch pipeline to allow i for the bypassing of steam from the six (6) inch steam seal piping to the i condenser in order to reduce the pressure of the steam in the steam seal j piping and to prevent the contamination of the oil with the steam.
! The safety evaluation concluded that this change did not constitute an.
l unreviewed safety question.
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1 Specification Changes (SC)
SC-84-002:
This change consisted of installation of debris screens on the suction and i-exhaust ventilation lines for the containment sphere to ensure that debris cannot prevent the proper operation of the ventilation valves.
l The safety evaluation concluded that this change did not constitute an unreviewed safety question.
l SC-84-030:
4 This change consisted of installation of ventilation seals between the Service Building and the Turbine Building to alleviate the potential of a j primary system pipe break in the Turbine Building affecting the habitability of the Control Room and the Technical Support Center,
, The safety evaluation concluded that this change did not constitute an
- unreviewad safety question, i SC-85-008
i j This change consisted of installation of two (2) emergency lighting / exit 3
sign combination units in the Radwaste Building to eliminate personnel
- safety concerns.
1 j The safety evaluation concluded that this change did not constitute an j unreviewed safety question.
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3 SC-85-013:
This change consisted of replacement of the PVC pads under the Spent Fuel Racks with stainless steel and aluminum plates to inhibit galvanic corrosion between the aluminum fuel racks and the stainless steel pool liner.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-85-029:
This change consisted of installation of Michigan Bell Telephone equipment and carrier system to provide future expansion capability.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-001 This change consisted of redesigning the fuel pump mounting bracket on the emergency diesel auxiliary fuel pump to eliminate vibration problems which have resulted in Woodruff key failure and subsequent fuel supply failure.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-003:
This change consisted of modifying the temporary support structure for the lead shielding protecting the Rosemount transmitters (PT-173, PT-174, &
PT-187, Model 1151) on the Post Incident System and the Containment Isolation System, to a permanent support structure to eliminate the possibility of damage to the trsusmitters by the temporary structure.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-006:
This change consisted of replacing existing fire detectors rated at 190 degrees Fahrenheit rate-of-rise model with fire detectors rated at 200 degrees Fahrenheit rate compensated model in the Recirculation Pump Room. The rate-of-rise model is no longer manufactured by the company which supplies the fire detectors.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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t i SC-86-008:
4 This change consisted of replacement of the sprinkler heads in the Exterior Cable Penetration Room with the original open head spray nozzles and a return to a manual system which had been temporarily changed to an automatic system until the Alternate Shutdown System was installed.
4 The safety evaluation concluded that this change did not constitute an 4
unreviewed safety question.
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! SC-86-013:
i This change consisted of replacement of Station Power System 480V ac circuit breaker 052-1E27 which failed during testing.
4 The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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j SC-86-014 :
- This change consisted of replacment of the screenhouse receptacles circuit I breaker which failed during testing.
i The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-86-017:
- This change consisted of replacing the underground portion of the 125V dc alarm cable serving the well house. This change was necessary due to grounding of the existing underground cable.
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The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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Set Point Change (SPC):
l l SPC-86-001:
l This set point change consisted of changing the alarm set point on the stack i gas normal range Noble gas monitor. This change was done to concur with a I recent change to the Technical Specification (Amendment No. 77).
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[ The safety evaluation concluded that this change did not constitute an j unreviewed safety question.
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i Facility Changes (FC)
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FC-462B: Detector Modifications This change consisted of installation of smoke and/or fire detection sensors in accordance with NFPA standards to comply with the intent of the NRC Branch Technical Position 9.5-1 and its Appendix A.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-462C: Fire Hose Reels Modification This change consisted of installation of two hose reel stations inside containment and the addition of sprinklers in the recirculating pump area in order to comply with Appendix A to the NRC Branch Technical Position 9.5-1.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-462D: Fire Barrier and Fire Stop Modification This change consisted of providing fire barriers and/or fire stops in wall penetrations and in horizontal and vertical cable trays to prevent fire i propagation in order to comply with Appendix A to the NRC Branch Technical Position 9.5-1.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-462G: Emergency Lighting System This change consisted of the addition of battery powered emergency lighting in accordance with Branch Technical Pocition 9.5-1.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
, FC-462H: Smoke Removal This change consisted of installation of a smoke and heat vent above the vent duct chase on the roof of the electrical equipment room in order to comply with Appendix A of NRC Branch Technical Position 9.5-1.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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6 FC-4621: Fire Dampers This change consisted of installation of fire dampers in large ventilation air ducts where they penetrate fire barriers and a manual smoke damper was installed in the control room ventilation ducts in order to comply with Appendix A of NRC Branch Technical Position 9.5-1.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-462J-1,J-2,J-3: Safe Shutdown System This change consisted of installation of an Alternate Safe Shutdown System with a control station, remote from the control room, from which the plant can be brought to and maintained in " Hot" shutdown in the event of a fire that prevents such an operation from the control room. The system also provides means of bringing the plant to cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This change was done in order to comply with Appendix R to 10 CFR 50.
The safety evaluation concluded that this change did not constitute an 1 unreviewed safety question.
FC-548: Addition of Isolation Valve to CV-4027 This change consisted of installation of a manual isolation valve upstream of l CV-4027 (clean-up demin and fuel pit drain line containment isolation l valve-inside) and a test tap line with two manual isolation valves between CV-4027 and the newly installed valve upstream of CV-4027. This change was done to improve containment isolation valve leak rate testing.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-558: Modification of Stack Gas Monitoring Piping This change consisted of replacing some of the existing stack gas monitor piping between the stack and sampling area so that it is compatible with the new Radioactive Gaseous Effluent Monitoring System (see FC-519).
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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4 FC-575: Additional Isolation Valves on Primary System
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l This change consisted of addition of six second redundant isolation valves to primary coolant system vent and drain lines to reduce the probability of a small LOCA.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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FC-584: Replace Existing Containment Level Transmitter This change consisted of replacement of an unqualified containment water level 2
transmitter (ITT Barten 386/351, transmitter / sensor) with that of a qualified transmitter (ITT Barton 764/351, transmitter / sensor) and upgrading the associated scheme to meet Electrical Equipment Qualification (EEQ) requirements.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-595: Ir. stall Two Vacuum Gauges on the Gland Seal Exhauster System
'j This change consisted of installation of two vacuum gauges upstream of each gland seal exhauster on the air ejector system to aid in the adjustment of i exhauster louvers.
i The safety evaluation concluded that this change did not constitute an 4 unreviewed safety question.
1 FC-597: Air Testing of Main Steam Isolation Valve This change consisted of installation of a manual valve upstream of CV-4104 (steam to steam seal regulator and air ejector) and a manual valve downstream of CV-4106 (turbine bypass warmup valve). This change was done to facilitate pneumatic testing of the main steam isolation valve (MSIV).
1 The safety evaluation concluded that this change did not constitute an
- unreviewed safety question. ,
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Specification Changes (SC) ,
SC-81-022:
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This change consisted of upgrading the plant emergency lighting system to meet l the eight hour requirements of Appendix R to 10 CFR*50,Section III J. As i originally installed, the lights were designed for a 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> rating (see '
> FC-462G).
9 The safety evaluation concluded that this change did not constitute an l
i unreviewed safety question.
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8-3 '.' 1 SC-84-008:
This change consisted of relocating the control rod drive pressure controller and pressure transmitter to a concrete wall from the previously existing mounting on a handrail. This change eliminates a vibration problem which was causing excesa.ive maintenance and failure of the instrumentation.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-85-017:
This change consisted of removing the electrical source to the solenoid valve which operated the main steam drain line outside isolation valve (CV-4107),
thereby failing the valve closed and fulfilling it's safety ralated function.
The main steam drain-line is no longer used and the motor operated inside containment isolation valve has been disabled closed for some time.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-85-018:
ThisSpecificationChangeconsistedofreplacingthereactorcoresprayfiow transmitters (FT-2162, -2163) and containment enclosure spray flow transmitrers (FT-2161, -2164) with LOCA qualified units. This change was part of the instrument upgrade for Electrical Equipment Qualification (EEQ); the original transmitters could not meet equipment aging requirements.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-85-027:
This change consisted of replacement of previously installed flanges on containment penetrations with flanges that matched the Conax penetration assembly flanges. This change was part of the Alternate Safe Shutdown System (see FC-462J). ,
The safety evaluation concluded that this change did not constitute an unrevtewed safety question.
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9 SC-85-034:
The change consisted of replacement of four existing Westinghouse Model 59DP4D99-7050 transmitters (Reactor Depressurization System Steam Drum Level l Transmitters; LT-3184, -3185, -3186, -3187) with that of qualified Rosemount l Model 1153DD4 transmitters. This change was performed to eliminate the continual repair required on the Westinghouse transmitters and the difficulty in obtaining parts for them.
l The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-85-035:
This change consisted of replacement of all General Electric Type HFA normally energized safety related AC relays along with those DC relays necessary to maintain emergency diesel operability and shutdown cooling system overpressure protection. This change was performed in response to IEB 84-02.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-85-036:
This change consisted of replacement of the turbine thrust bearing alarm and indicator with a different model; the original unit had failed and a direct replacement was no longer available.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
Set Point Change (SPC)
SPC-85-001:
This change consisted of temporarily lowering the domestic water accumulator pressure control setpoint from 85 psig to 75 psig due to a degraded condition of the plant air compressors. This was an attempt to reduce the number of low air pressure alarms. The plant air compressors have been upgraded and the accumulator pressure was returned to its normal setting.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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l ATTACHMENT II Consumers Power Company Big Rock Point Plant Docket 50-155 FACILITY CHANGES, SPECIFICATION CHANGES, SET POINT CHANGES. TESTS AND EXPERIMENTS Declared Operable Prior to December 31, 1986 l Package Not Closed Out 3 Pages M10187-1241A-BT01-NLO4
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'8 ATTACHMENT II Facility Changes (FC)
FC-239: Relocation of the New Fuel Storage Criticality Monitor This change consisted of relocating the criticality monitor detector on the steam drum wall to west of the new fuel storage area to improve criticality '
monitoring.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
) FC-462J: Safe Shutdown System This change consisted of installation of an Alternate Safe Shutdown System with a control station, remote from the control room, from which the plant can j be brought to and maintained in " Hot" shutdown in the event of a fire that i prevents such an operation from the control room. The system also provides means of bringing the plant to cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This change was done in order to comply with Appendix R to 10 CFR 50.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-462J-04: Change to commitment for CRD Booster Pump This change consisted of permanently wiring the alternate power source to CRD l Pump No 1 in an arrangement that allows CRD Pump No 1 to be powered from the alternate power source by the operation of two switches and one disconnect.
The CRD booster pump has temporary wiring available in the form of a cable which is permanently connected and switchable to an alternate power source.
The other end of the cable must be bolted to connectors attached to the booster pump.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-519: Gaseous Effluent Monitoring System (RGEM)
This change consisted of replacing the existing stack gas monitoring system with a new Radioactive Gaseous Effluent Monitoring System (RGEM) in order to comply with NUREG-0578, Section 2.1.8b. The system obtains a continuous representative sample of plant gaseous effluent from the plant stack during normal and emergency operating conditions.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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FC-520: Containment Gamma Radiation Monitoring This change consisted of installation of two redundant gamma radiation i monitors, each with a range of 10* to 107 R/hr, to monitor gamma radiation in the containment atmosphere. The detectors were mounted inside the exterior electrical cable penetration room with the indicators and recorders installed in the control room. This change was completed in order to comply with NUREG-0578, Section 2.1.8b.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-535: Fire Pump Discharge Header Pipe Supports This change consisted of installing additional pipe supports on the fire pump discharge header. This change will improve reliability of the system response during a seismic event.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
FC-598: Cleanup Pump Bypass This change consisted of the installation of a bypass line around the cleanup demineralizer pump to allow operation of the cleanup system during power operation with the cleanup pump shut off.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
Specification Changes (SC)
SC-81-036:
This change consisted of temporarily relocating the stack gas monitoring equipment to allow for installation of the new stack gas monitor equipment (see FC-519).
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-83-025:
This change consisted of replacing an installed 1/16" raised face 8", 150#
standard weld neck flange with a flat face 8", 150# standard weld neck flange on a fire system discharge header valve in order to comply with ANSI B 31.1.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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3 SC-83-038:
This Specification Change was used to address the design requirements of a temporary cylinder which was manufactured to continue irradiation of the antimony (Sb) pin while a beryllium (Be) cylinder was being manufactured.
This change was necessary because the Be cylinder of the Sb-Be source was found broken in two pieces during the 18th refueling.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
SC-85-002:
I This change consisted of removing the old stack gas monitoring system wiring '
and associated equipment. The stack gas monitoring system was replaced with a 1 new system (see FC-519).
The safety evaluation concluded that this change did not constitute an
. unreviewed safety question. j SC-85-040:
This change involved the Alternate Shutdown Building security modifications.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
Set Point Change (SPCl SPC-83-039:
This change consisted of changing the set point on the redundant enclosure spray relief valve (RV-5082) from 140 +5-0 psig to 145 +5-0 psig to eliminate different set points for the three enclosure spray relief valves.
The safety evaluation concluded that this change did not constitute an unreviewed safety question.
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ATTACHMENT III Consumers Power Company Big Rock Point Plant Docket 50-155 1986 Procedure Changes Reportable to the NRC 4
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ATTACHMENT III Procedure 1-1.7.2: Operator Training This procedure was incorporated into the plant's Administrative Procedures and upgraded the training requirements to meet the INPO accreditation criteria.
The safety evaluation concluded that this procedure did not constitute an unreviewed safety question.
Procedure ALP 1.6: Edwards and Pyrotronics Fire System Annunciator Tabulation This procedure change involved updating of the model of detectors being used in the Recirculation Pump Room. (See SC-86-006)
The safety evaluation concluded that this procedure change did not constitute an unreviewed safety question.
Procedure TR-100: Recirculation Pump Room Fire Detector Test This procedure change involved a title change and a model change of the type of detector being used in the Recirculation Pump Room. (See SC-86-006)
The safety evaluation concluded that this procedure change did not constitute an unreviewed safety question.
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