ML20237K786

Provides 7th Update of Status of Facility Integrated Plan. Attachment 1 Contains Index of All Issues & Identifies Issues by Category,Rank,Description & Status.Attachment 2 Contains Detailed List of All Open Issues

ML20237K786
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	08/31/1987
From:	Frisch R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8709080020
Download: ML20237K786 (24)

Text

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Consumers Power rowsmne RlEN8GAN5 PutnGmFEt General offices: 1945 West Parnali Road, Jackson, MI 49201 * (517) 788 0550 August 31, 1987 Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

INTEGRATED PLAN SEMI-ANNUAL UPDATE NO. 7 As required by the Big Rock Point Operating License, this letter provides the seventh update of the status of the Big Rock Point Plant Integrated Plan. contains an index of all issues,.and identifies then by category, rank, description and status. Attachment 2 contains a detailed list of all open issues and includes scope, status and applicable schedule dates.

SUMMARY

OF INTEGRATED PLAN ACTIVITIES SINCE THE FEBRUARY, 1987 UPDATE:

Two meetings of the Technical Review Group (TRG) were held; the first meeting was in March, 1987 and the second was in July, 1987. As a result of the meetings, three issues were added to the Integrated Plan; the new issues are summarized as follows:

Tasue BN-014B: Verification of Seismic Adequacy of Active Components.

fhis issue was initiated in response to Generic Letter 87-02.

Issue B-120: Access to Recire Pump Room Heat Sensors. This issue was initiated in response to a personnel safety concern.

Issue B-121: Control Rod Drive System Improvements. This issue was initiated in order to resolve plant availability concerns related to the performance of the control rod drive system.

One issue (B-106: Remove Turbine Grating) was deleted from the Integrated Plan. Deletion of the issue was permitted because of its low score (2), and because of administrative practices which obviate the need to modify the grating to facilitate egress from the area beneath the turbine. The issue had i

been originally established on the basis of personnel safety implications.

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l t-Nuclear Regulatory Commiseion 2

l Big Rock Point Plant Integrated Plan Update #7 August 31, 1987 No issues have been completed since the February, 1987 update. This is due in part to reassignment of engineering resources from active Integrated Plan issues to perform design work in support of the replacement of electrical cables during the June, 1987 EEQ outage.

STATUS OF ACTIVE ISSUES:

A brief status of each Integrated Plan issue is provided in Attachments 1 and 2.

A more detailed status of some issues is provided in this section.

Detailed status is not being provided for all issues, but rather for those which have had significant change in status since the last Integrated Plan Update.

j CATEGORY BN ISSUES lasue BN-005: Control Room Design Review (CRDR).

The Part 11 Summary Report was submitted to the NRC on August 26, 1987. This submittal satisfies a commitment made by letter dated February 4, 1987.

1700 of approximately 2000 Human Engineering Discrepancies (HEDs) have been resolved by the CRDR team; the remaining 300 HEDs are being referred to the Plant for resolution.

It is expected that some of these, because of their scope, will be referred to the Technical Review Group for ranking. Schedules for resolving these HEDs will be developed following ranking by TRG, lasue BN-014A: Resolution of Seismic " Weak Links."

The 0.lg weak link analysis has been completed and is currently being reviewed. Recommendations for improvements to plant structures / systems will be presented for ranking during the December, 1987 TRG meeting.

Issue BN-014B: Seismic Adequacy of Active Components.

This is a new issue which was ranked by TRG during its March, 1987 meeting.

This issue was initiated in response to Generic Letter 87-02.

The current effort, as ranked by TRG, is to perform equipment walkdowns and prepare a report of the results. Based on the results of the walkdown, recommendations will be made to TRG regarding further action with respect to Generic Letter 87-02.

Issue BN-025: Wind and Tornado Loading.

l Resolution of this issue will include procurement of one portable pump powered by a gasoline engine, and the construction of a bunker to store fuel for the l

l OC0887-0140-NLO4

\\

Nuclear Rsgulatory Commission 3

Big Rock Point Plant Integrated Plan Updcte #7 August 31, 1967-engine. Contingent on budget approval, current plans call for completion of work on this issue by July 31, 1988.

Issue BN-032: Emergency Operating Procedures (EOP) Upgrade.

E0Ps have been prepared (in flow chart form) per the technical guidelines and writer's guide. The verification program is nearly complete. Upon completion of verification, lesson plans for validation team member training will be

' completed. Validation is currently scheduled to commence in January, 1988, but could begin as soon as November 1, 1987 if resources (validation team members) can be made available.

Timely receipt of the results of NRCs review of the Procedures Generation Package (submitted in December 1986) would make the validation process more meaningful, particularly if significant changes to the E0Ps may be required as a result of NRCs review.

Issue BN-051: Design Codes, Design Criteria and Load Combinations.

(Ref: SEP topic III-7B)

This issue was presented to TRG for reranking during the March, 1987 meeting.

Reranking was based on a revised scope as follows:

Review the structural elements in Section 13 (Recommendations) of Franklin Research Center report TER-C5257-317 as they apply to each Category 1 type structure at Big Rock Point Plant. Evaluate the potential impact on those structures which do not meet the features specified.

Evaluate the selected structural elements for safety margin with respect to new codes, considering seismic, wind and tornado loads, missiles, and high energy line break loads in addition to original design loads.

Review Appendix A of the FRC report to confirm the validity of FRC's conclusions.

Determine which vadifications should be performed to address valid concerns identified during the reviews discussed above.

l The aaove tasks were estimated as requiring approximately 1600 to 1800 manhours of engineering effort to perform.

Evaluation of Class 1 structures for impact on safety margin due to code changes is nearly complete; the report for this evaluation is expected to be ready for review by September 30, 1987.

OC0887-0140-NLO4

4 Nuclear Regulatory Commission 4

Big Rock Point Plant Integrated Plan Update #7 August 31, 1987 CATEGORY B ISSUES Issue B-016: Secondary System Instabilities.

Review of the recommendations described in the February,1987 update has shown that additional analytical work is needed to permit selection of the best alternative. The analyses (flow network) are expected to be complete during March 1988.

Issue B-018: liigh Pressure Recycle.

The procedure for high pressure recycle has been drafted and is in the review process.

(This procedure supports the upgraded E0Ps),

Issue B-044: Ver'fication of BS&B Valve Data.

A schedule has been developed to complete collection of data in conjunction with performance of preventive maintenance on the valves. This method assures collection of data with minimum radiation exposure. Completion is planned during the 1989 refueling outage.

Issue B-082: RDS Reliability Improvement.

The modifications performed during the 1987 refueling outage were described in detail in the February, 1987 update. Based on operating history since the 1987 refueling outage, it appears the modifications have not improved operation of the system. Current plans to improve system operation include the following:

DEPRESSURIZATION VALVE LEAKAGE: Two spare pilot disc assemblies are currently being modified (modifications include changes in selected materials and dimensions); additionally, the pilot valve bodies will be stress relieved. These actions are in accordance with vendor recommendations to reduce pilot valve leakage.

To reduce or eliminate plant down time resulting from pilot valve leakage, a proposal to install remotely located pilot valve assemblies is being evaluated. Having remotely located pilot valves would permit a leaking pilot assembly to be valved out of service, and a spare assembly to be installed with no interruption in plant operation.

Inasmuch as the current method of stroke testing the depressurization valves is believed to be a major contributor to valve leakage (because of contaminants being deposited on the valve seats during valve stroking), it l

OC0887-0140-NLO4

Nuclear Regulatory Commission 5

Big Rock Point Plant Integrated Plan Update #7 August 31, 1987 is intended that changes to the valve test program will be proposed. The proposed changes, as currently envisioned, are discussed in the next j

paragraph.

DEPRESSURIZATION VALVE FULL STROKE TESTING: A change to the Big Rock Point Technical Specifications will be proposed in conjunction with the modification which will provide remotely located pilot valve assemblies.

The pilot assemblies would continue to be classified as ASME category "B" (which requires stroke testing during each cold shutdown which occurs longer than 90 days since the previous test). The main valve assemblies, however, would be reclassified as ASME category "C", such that one valve would be required to be tested during each refueling outage. The current pilot assembly repair and testing procedure would then be upgraded to incorporate the ASME category "B" testing requirements. This change would eliminate the contamination of pilot seats currently occurring during valve testing. Full stroke testing of the main valve could be performed during refueling outages. Design changes to permit full stroke testing would commence following installation of remote pilot valve assemblies and approval of the proposed change to the technical specifications to revise the testing requirements for the depressurization valve main valve assemblies.

Issue B-104: Core rpray Pump Suction Strainer Blockage.

An alternate method of resolving this issue has been proposed and consists of installing screens in the doorways to some of the rooms housing the core spray pump suction strainers. This proposal will be reviewed by TRG and ranked accordingly.

Issue B-118: Underwater Filtering System For the Spent Fuel Pool.

The design package for this modification requires review and possible additional work.

It is expected that the underwater filtering system will be made operational prior to the 1988 refueling outage.

Issue B-120: Access to Recirc Pump Room Heat Sensors.

Heat sensors installed in the recirc pump room are difficult to access, and because of their location, present a personnel safety hazard (falling hazard),

whenever they require maintenance.

l Issue B-121: Control Drive System Improvements.

l The purpose oi this issue is to determine and correct the cause of excessive control rod withdrawal times encountered during the 1987 refueling outage.

OC0887-0140-NLO4

o Nuclear Regulatory Commission 6

o Big Rock Point Plant Integrated Plan Update #7 August 31, 1987 Although not a nuclear cafety issue, this issue has strong availability implications. A plan to resolve this issue is being developed by Consumers Power and NSSS supplier personnel.

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A Ralpi,R Fr s1 Senior Licensing Analyst CC Administrator, Region Ill, NRC NRC Resident inspector - Big Rock Point Plant Attachments OC0887-0140-NLO4 a________

1 ATTACHMENT 1 Consumers Power Company Big Rock Point Plant Docket 50-155 ISSUE INDEX FOR THE BIG ROCK POINT INTEGRATED PLAN August 31, 1987 l

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5 Pages l

i MIO287-0084A-BX01 i

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l ISSUES EY ISSUE NUMBER ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS HEAT EXCHANGER TUBE BUNDLE REPLACEMENT COMPLETE B-001 ACID LINE EXTENSION COMPLETE B-002 REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION COMPLETE B-003 STACK GAS MONITORING COMPLETE B-004 BN-005 18 CONTROL ROOM DESIGN REVIEW ACTIVE i

BN-006 SAFETY PARAMETER DISPLAY SYSTEM ACTIVE SCRAM DUMP TANK LEVEL INSTRUMENTATION COMPLETE B-007 SINGLE CHANNEL RESET INVESTIGATION COMPLETE B-008 B-009 REACTOR COOLING WATER PRESSURE STUDY COMPLETE B-009A INSTALLATION OF TELLiALES ON SHUTDOWN HEAT EXCHANGER COMPLETE VENTILATION FOR PANEL C-52 COMPLETE B-010 RUCKER SYSTEM (STUDY)

COMPLETE B-011 B-011A 2

TURBINE BYPAST SYSTEM IMPROVEMENTS ACTIVE RESIDUAL HEAT REMOVAL HEAT EXCHANGER TUBE FAILURE COMPLETE B-012 PURITY OF PRIMARY COOLANT COMPLETE B-013 B-014 SEISMIC DESIGN CONSIDERATIONS COMPLETE BN-014A 15 RESOLUTION OF SEISMIC ISSUES ACTIVE BN-014B 21 SEISMIC ADEQUACY OF ACTIVE COMPONENTS ACTIVE CONTAINMENT ELECTRICAL PENETRATIONS COMPLETE B-015 B-016 5

SECONDARY SYSTEM INSTABILITIES ACTIVE B-017 PCS ISOLATION - PC SYSTEM COMPLETE B-018 8

HIGH PRESSURE RECYCLE ACTIVE HYDROGEN MONITORING COMPLETE B-019 B-020 INSTRUMENTATION TO DETECT INADEQUATE CORE COOLING COMPLETE B-021 RECIRCULATION PUMP TRIP COMPLETE BN-022A ORGANIC MATERIALS (WALL COATINGS)

COMPLETE B-022B POST ACCIDENT CHEMISTRY - SEP TOPIC VI-1 COMPLETE B-023 BALANCE OF PLANT QA PLAN DEVELOPMENT CANCELLED B-024 INSTALLATION CF DP GAUGE ON NONREGEN HEAT EXCHANGER COMPLETE BN-025 21 WIND AND TORNADO LOAD & TORNADO MISSILE -

ACTIVE SEP TOPICS III-2 & III-4.A ISI 0F WATER CONTROL STRUCTURES COMPLETE B-026 B-027 SERVICE WATER / COOLING WATER SYSTEMS COMPLETE MIO287-0084A-PX01

.+

2 ISSUE ISSUE-NUMBER RANK ISSUE DESCRIPTION STATUS PROXIMITY OF TECTONIC STRUCTURES COMPLETE B-028 TURBINE MISSILES COMPLETE B-029 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS COMPLETE A-030 DEFINITION OF OPERABILITY COMPLETE B-031 BN-032 7

EMERGENCY OPERATING PROCEDURE UPGRADE ACTIVE B-033 REFERENCE VOLUME CHAMBER REMOVAL COMPLETE CONTROL ROOM AIR CONDITIONING COMPLETE B-034 A-035B 25 FHSR UPDATE STUDY ACTIVE ENVIRONMENTAL QUALIFICATION OF ELECTRICAL COMPLETE A-036 EQUIPMENT (EEQ)

B-036A 15 EEQ PROGRAM ENHANCEMENTS ACTIVE.

PROBABLE MAXIMUM FLOOD CONSIDERATIONS COMPLETE B-037 SAFETY RELATED WATER SUPPLY - SEP TOPIC II-3.C COMPLETE B-038 EFFECTS OF HIGH WATER LEVEL - SEP TOPIC III-3.A COMPLETE B-039 B-040 PIPING'AND SA1/E END INTEGRITY COMPLETE CLASSIFICATION OF STRUCTURES, SYSTEMS, & COMPONENTS COMPLETE B-041 B-042 ONGOING ISI COMPLETE B-043 MECHANICAL SNUBBERS COMPLETE B-044 23 VERIFICATION OF BS&B VALVE DATA ACTIVE ECCS TEST TERMINAL BOX CANCELLED B-045 REVISED REACTOR VESSEL PRESSURE / TEMPERATURE LIMITS COMPLETE B-046 B-047 SPENT FUEL POOL CLEANUP COMPLETE CLEANUP DEMINERALIZED SYSTEM PUMP REPLACEMENT COMPLETE B-048 INVESTIGATION B-048A CLEANUP DEMINERALIZED SYSTEM PUMP BYPASS COMPLETE VENTILATION SYSTL COMPLETE j

B-049 MSIV BACKUP VALVES - LEAK TESTING COMPLETE B-050A1 BN-050A2 5 CONTAINMENT ISOLATION - ONLINE TESTING OF MSIV ACTIVE BN-050B CONTAINMENT ISOLATION - LEAK TEST OF SERVICE AND COMPLETE INSTRUMENT AIR B-050C CONTAINMENT ISOLATION - ISOLATION VALVES IN COMPLETE HEATING, COOLING, OR SERVICE WATER MIO287-0084A-BX01 1

ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS CONTAINMENT ISOLATION - ADD CONTROL CIRCUIT TO COMPLETE B-050D TREATED WASTE VALVE (CV-4049)

B-050E CONTAINMENT ISOLATION - AIR LOCK TESTING -

COMPLETE SEP TOPIC VI-4 B-050F CONTAINMENT ISOLATION - HAND ISOLATION OF COMPLETE l

INSTRUMENT LINES - SEP TOPIC VI B-050G CONTAINMENT ISOLATION - PNEUMATIC TEST OF MSIV -

COMPLETE SE? TOPIC VI-4 BN-051 26 DESIGN CODES, CRITERIA AND LOAD COMBINATIONS ACTIVE B-052 HELB - SEP TOPIC III-5.A COMPLEII PIPE BREAKS OUTSIDE CONTAINMENT COMPLETE B-053 PLANT SHIELDING - NUREG-0737 ITEM II.B.2 COMPLETE B-054 METEOROLOGICAL TOWER COMPLETE B-055 ESF UPGRADE COMPLETE B-056 B-057 CONTROL ROOM HABITABILITY - NUREG-0737 COMPLETE CONTROL ROOM HABITABILITY - SEAL DOORS COMPLETE B-057A POST ACCIDENT SAMPLING COMPLETE B-058 MSLB OUTSIDE CONTAINMENT COMPLETE B-059 B-060 REVISED SECURITY PRINTS CANCELLED EQUIPMENT IDENTIFICATION CANCELLED B-061 B-062 REVISE DRAWINGS (SYSTEM CHECKSHEET VERIFICATION)

COMPLETE CONTAINMENT PURGE AND VENT COMPLETE B-063 b-064 CONTAINMENT ILRT COMPLETE B-065 TEST CARD READER CANCELLED RADWASTE MONITOR FLUSH TIMER CANCELLED B-066 ISOLATION OF RPS FROM NONSAFETY SYSTEMS COMPLETE B-067 B-068 DC SYSTEM MONITORING COMPLETE B-069 ACID AND CAUSTIC TANK PROBLEMS COMPLETE B-070 EMERGENCY DG PANEL VENTILATION COMPLETE CHANGE PIPING IN CHEM LAB HOT HOOD CANCELLED B-071 B-072 FACILITY MODIFICATIONS - WAREHOUSE COMPLETE CONTROL OF HEAVY LOADS COMPLETE B-073 REACTOR COOLANT SYSTEM - HIGH POINT VENTS COMPLETE B-074 M10287-0084A-BX01

4 ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS A-075A ALTERNATE SHUTDOWN SYSTEM COMPLETE RADIANT ENERGY SHIELDS COMPLETE A-075B ASSOCIATED CIRCUITS COMPLETE A-075C B-076 CONTAINMENT HIGH RANGE MONITOR COMPLETE INVESTIGATE INCORE AVAILABILITY PROBLEM COMPLETE B-077 l

B-077A INVESTIGATE INCORE AVAILABILITY PROBLEM CANCELLED CLEANUP SYSTEM DRAIN LINE CANCELLED B-078 CONTROL ROD MISOPERATION COMPLETE B-079 PERFORMANCE OF BWR SAFETY VALVES COMPLETE B-080 B-081 POSITION INDICATION OF PORV'S COMPLETE B-082 1

RDS RELIABILITY IMPROVEMENTS ACTIVE FULL STR0KE TESTING OF REACTOR DEPRESSURIZATION CANCELLED

• B-083 VALVE B-084 SCRAM DUMP TANK VALVE - LACK OF REDUNDANCY (STUDY)

COMPLETE B-084A SCRAM DUMP TANK REDUNDANT VALVES COMPLETE B-085 CONTAINMENT OVERPRESSURE - NITROGEN SUPPLY TO RDS COMPLETE ISOLATION VALVES B-086 BYPASS OF MOV THERMAL OVERLOADS COMPLETE B-087 PIPE BREAK OUTSIDE OF CONTAINMENT COMPLETE B-088 MSLB OUTSIDE CONTAINMENT - RADIOLOGICAL CONSEQUENCES COMPLETE RCPB LEAKAGE DETECTION COMPLETE B-089 CLASSIFICATION OF STRUCTURES, SYSTEMS AND COMPONENTS COMPLEIE BN-090 CONTAINMENT ISOLATION - POST LOCA SYSTEM WALKDOWNS COMPLETE B-091 B-092 CONTAINMENT ISOLATION - CLOSED SYSTEMS COMPLETE B-093 EMERGENCY RESPONSE FACILITIES (UPGRADE TSC)

COMPLETE B-094A POST TRIP REVIEW - DATA & INFORMATION CAPABILITIES COMPLETE B-094B POST TRIP REVIEW - DATA & INFORMATION CAPABILITIES COMPLETE B-095 INSTALLATION OF FILTERS IN INSTRUMENT AIR LINE COMPLETE INSTALLATION OF ISOL VALVE UPSTREAM OF CV-4027 COMPLETE B-096 B-097 REPLACEMENT OF VIP-5 WITH MOTOR OPERATED VALVE COMPLETE

• This issue was combined with Issue B-082.

MIO287-0084A-BX01

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ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS REVISIONS TO 125-VOLT DC DRAWINGS COMPLETE B-098 EQUIPMENT CLASSIFICATION - RPS COMPONENTS COMPLETE B-099 VENDOR INTERFACE AND MANUALS COMPLETE BN-100 B-101 POST MAINTENANCE TESTING - RPS COMPONENTS COMPLETE EQUIPMENT CLASSIFICATION - ALL SAFETY RELATED COMPLETE B-102 EQUIPMENT POST MAINTENANCE TESTING - ALL SAFETY RELATED COMPLETE B-103 EQUIPMENT B-104 23 CORE SPRAY PUMP SUCTION STRAINER BLOCKAGE ACTIVE B-105 REACTOR DEPRESSURIZATION SYSTEM HANGER REPLACE}' INT COMPLETE REMOVE TURBINE GRATING CANCELLED B-106 B-107 FLOOD ANNUNCIATION CANCELLED MAIN STEAM LINE DRAIN ISOLATION COMPLETE B-108 BACKUP HIGH RANGE STACK MONITOR COMPLETE BN-109 B-110 19 LIGHTNING PROTECTION ACTIVE B-111 9

REPLACEMENT OF NEUTRON MONITORING INSTRUMENTATION ACTIVE A-112 12 ALTERNATE ROD INJECTION ACTIVE B-113 12 RELIEF VALVE FAILURES INVESTIGATION ACTIVE B-114 19 RECIRCULATION PUMP ROOM LIGHTING ACTIVE B-115 3

CONDENSER MAKEUP WATER / CORE SPRAY INVESTIGATION ACTIVE B-116 9

CLEANUP DEMIN PIT ACCESS HANDRAIL ACTIVE REPLACE DIESEL FIRE PUMP ENGINE COMPLEi-B-117 B-118 15 UNDER WATER FILTERING SYSTEM FOR SPENT FUEL POOL ACTIVE B-119 4

AClD SYSTEM MODIFICATIONS TO ELIMINATE PIPING CORROSION ACTIVE B-120 12 ACCESS TO RECIRC PUMP ROOM HEAT SENSORS ACTIVE B-121 9

CRD SYSTEM IMPROVEMENTS ACTIVE l

I M10287-0084A-BX01 l

ATTACHMENT 2 Consumers Power Company Big Rock Point Plant Docket 50-155 l

L BIG ROCK POINT INTEGRATED PLAN OPEN ISSUES August 31, 1987 9 Pages M10287-1084A-BX01

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