ML20206Q957

Provides Fifth Integrated Plan Semiannual Update.Refueling Outage Scheduled for 1986 Changed to Start in Jan 1987 & 1987 Refueling Outage Rescheduled for 1988

ML20206Q957
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	08/29/1986
From:	Frisch R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8609050274
Download: ML20206Q957 (25)

Text

4 -F Consumers

@rewaums nlKniEAWS PEROGRESS Power General officos: 1945 West Parnall Road, Jackson, MI 49201 * (517) 788-0550 Ayust 29, 1986 Director, Nuclear Reactor Regulation US Nuclear Regulatory Commission Washington, DC 20555 DOCKET 50-155 - LICENSE DPR BIG ROCK POINT PLANT -

INTEGRATED PLAN SEMI-ANNUAL UPDATE No. 5 As required by the Big Rock Point operating license, this letter provides the fifth Integrated Plan Semi-Annual Update. Attachment 1 contains an Issue Inde,x which identifies all issues by category, rank, description and' status.

Attachment II contains a detailed listing of all open issues which includes scope, status and applicable schedule dates. The previous update identified several issues with completion dates of 1986 refueling outage. The 1986 l refueling outage schedule has been changed to start in January 1987, and therefore, all 1986 refueling outage completion dates have been changed to l 1987 refueling outage. Also, as a result of changing the 1986 refueling l outage dates, the 1987 refueling outage which was planned to begin in December l 1987 is now planned to begin in early 1988 and all 1987 refueling outage completion dates have been changed to 1988 refueling outage.

Summary of Issues Completed or Cancelled Since Previous Update Three (3) issues have been completed since the fourth update and two (2) issues have been cancelled. A summary of these five (5) issues is as follows:

Issue BN-022A Organic Materials (Wall Coatings)

The surveillance inspection procedure for triennial inspec-tion of containment coatings (TV-35) has been approved for implementation. One minor deficiency was noted during a review of the baseline inspection report issued subsequent to the 1985 refueling outage.

( Room 401, located directly below the reactor vessel (CRD l Room) was inadvertently omitted during the 1985 inspection.

Reasons for this omission were due to the inspector OC0886-0134-NLO2 860905027 \

PDR 60829 \

R ADOCK 05000155-PDR

3 P Director, Nuclear Reactor Regulation 2 Big Rock Point Plant Integrated Plan Semi-Annual Update No. 5 August 29, 1986 encounter.ing unsuitable conditions in room 401 forcing a temporary postponement of the inspection and his overlooking

the need to revisit room 401 prior to returning the plant to power.

A Deviation Report was written to assure resolution of this deficiency, now expected during the next refueling outage.

Because of the minor nature of the deficiency and the fact that it is being tracked on the corrective action system for resolution, Issue BN-022A is considered closed.

Issue B-023 Balance of Plant - QA This issue, to develop a Quality Assurance Plan for the balance of plant equipment, has been re-evaluated for desirability based on available plant resources, potential benefit vs cost and priority. It has been decided that this issue should be cancelled and it has been removed from the living schedule.

t Issue B-045 ECCS Test Terminal Box This issue involved a proposed modification to install two test boxes in the backup core spray circuitry to enable quarterly testing of the initiating sensors without stroking MO-7070 and M0-7071 valves. Re-evaluation of this proposed modification indicates minimal payback for resources that  ;

would be expended. Future testing will continue to require '

4 stroking of the two valves. It has been decided that this issue should be cancelled and it has been removed from the living schedule.

Issuc BN-090 Classification of Structures, Systems and Components This issue involved the analysis and evaluation for thermal fatigue of a piping system and a vessel nozzle. The piping system evaluation was submitted for NRC review in our February 10, 1986 letter and the nozzle evaluation in our August 29, 1986 letter. This issue is now considered closed.

Issue BN-100 Vendor Interface and Manuals A computerized listing was developed that provides a cross reference between equipment and manuals. In addition to the user index, a vendor manual control procedure has been approved. This issue is now considered closed.

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Director, Nuclear Reactor Regulation 3 Big.Reck Point Plant Integrated Plan Semi-Annual Update No. 5 August 29, 1986 Summary of Issues Added Since Previous Update Seven'(7) new issues have been ranked by the TRG and added to the Integrated Plan since the fourth update. These new issues are:

Issue B-036A EEQ Program Enhancements With the completion of the original EEQ Project (Issue A-036), it was acknowledged that plant resources will continue to be expended on EEQ to enhance the administrative controls program and support the ongoing maintenance activi-ties. Specifically, this project will provide for the review and, if necessary, revision of the Administrative Procedures to provide for additional assurance that EEQ program controls will be met. These Administrative Proce-dures may include maintenance order processing, material control, modification control, and qualification file control. This project also allocates resources to revise the existing EEQ files to incorporate the component (SCEW) sheets onto a computer form, inclusion of a new LOCA profile sheet, and general revisions to achieve a more consistent format.

Issue B-113 Relief Valve Failures Investigation Big Rock Plant reliaf valves are tested in accordance with ASME Section XI requirements per the BRP pump and valve program. Some as found set points have lacked. repeatability with both high and low set point drift. Since the set points can adversely affect plant reliability, this issue was initiated to determine the cause of the set point 1 drifting and provide recommendations to improve relief valve l performance. . Areas of investigation include procedures for establishing set points, determining as found set point, relaxation of spring constant, buildup of system impurities in valve internals, and evaluation of bench test equipment.

Issue B-114 Recirculation Pump Ronm Lighting Lighting in the recirculation pump area has been identified inadequate for operations, maintenance and health physics i

personnel. The issue is primarily one of personnel safety.

The proposed mcdification will result in the separation of electrical circuitry for normal and emergency lighting.

Issue B-115 condenser Makeup Water / Core Spray Investigation This issue was ranked #3 during the May 1986 TRG meeting.

The issue involves conducting a study to deternine alternatives / benefits of providing makeup water to the condenser to prolong high pressure makeup water to the OC0886-0134-NLO2

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Director, Nuclear Reactor Regulation 4 Big Rock Point Plant Integrated Plan Semi-Annual Update No. 5 August 29, 1986 reactor via reactor feed pumps in the event of a small break LOCA. This issue qualified for living schedule based on

' extensive man hours that will be required for the study.

Issue B-116 Cleanup Demineralizer Pit Access - Handrail Presently, due to a lack of space, personnel have utilized equipment and piping to stand on while working in the cleanup demineralizer pit area. This has caused damage of equipment to occur. This project may result in the instal-lation of a new working platform and support structure, addition of handrails around the platform, installation of grab bars between ladders and handrail around top of pit with an access gate. Corrective actions will be aimed at enhancement of personnel safety and reduction of damage to equipment.

Issue B-117 Replace Diesel Fire Pump Engine The existing diesel driver is an obsolete model resulting in

' replacement / spare parts not being readily available. The existing diesel driver meets functional requirements; however, if failure occurs, availability of spare parts could result in or extend an outage. The diesel driver will be replaced during the upcoming refueling outage.

Issue B-118 Underwater Filtering System for Spent Fuel Pool To enhance spent fuel pool water clarity and ALARA consider-ations, the decision was made to install an underwater filtration system. The system currently under consideration is designed so it can be used for vacuuming as well as continuous filtering. It is anticipated radiation levels over the fuel pool will drop, resulting in reduced man-rem exposure in the future. Installation is scheduled prior to the beginning of the next refueling outage.

Summary of Schedule / Scope Changes Since Previous Update l

(

Eight (8) issues have been rescheduled since the fourth update. These issues are as follows:

Tssue BN-006 Safety Parameter Display System I

l l As previously stated in our letter dated 3/27/86, a safety analysis will be submitted to NRC for review and approval by

March 1, 1987. SPDS operational date will be determined after it is determined if additional hardware will be

( required. This date will be included in the August 1987 i update report. The planned scheduled completion date has OC0886-0134-NLO2 I

Director, Nuclear Reactor Regulation 5 Big Rock Point Plant Integrated Plan Semi-Annual Update No. 5 August 29, 1986

-been revised to indicate 3/1/87 as the submittal date for the safety analysis package.

. Issue BN-014A Resolution of Seismic Issues An issue manager has been assigned. A portion of the modifications required could possibly be performed with the plant in power operation; however, the planned scheduled.

completion date of 1988 refueling outage has been estab-

, lished for those requiring an outage to perform. Further, the completion date of 1988 refueling outage reflects anticipated plant resources that will be available.

Issue BN-025 Wind and Tornado Loading NRC comments on original submittal have been received. Work will commence in the fourth quarter of 1986 to resolve..NRC's comments and to revise the risk analysis to include the Alternate Shutdown Building (ASD). If resolut13n of NRC's comments require additional structural analysis, generation of fragilities or site specific probabilistic treatment of missiles, this additional work scope will be presented to the Technical Review Group and a schedule established during the first quarter of 1987.

Issue BN-032 Emergency Operating Procedures Upgrade Development of the Procedure Generation Package (PGP) continues; the PGP will be submitted to the NRC by December 31, 1986. The status of each element of the PGP is as follows:

Writer's Guide The guide has been developed, but requires considerable revision. Revisions are sched-l uled to be completed by November 1, 1986.

Validation and Verification (V6V) Program The proce-dure for the V6V Program has been written and is currently being reviewed.

Training Program The Training Program description hss been completed.

Technical Guidelines Remaining work on the first draft

of the guidelines consists of developing the Radioac-tivity Control Guideline and its associated basis document. The completed portion of the guidelines is currently undergoing a technical review.

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Director, Nuclear Reactor Regulation 6 Big Rock Point Plant Integrated Plan Semi-Annual Update No. 5 August 29, 1986 Fellowing completion of the technical review, comments resulting from that review as well as concerns / comments resulting from the Control Room Design Review (CRDR) r will be evaluated, and the guidelines revised as appropriate. In addition, the guidelines will be reviewed to determine if additional control room instrumentation and controls need to be included in the CADR.

I Analyses to support development of the new guidelines are underway; although some of these analyses may not be completed at the time of the PCP submittal, it is believed that no significant revisions to the technical guidelines will be required as a result of the analys-es. If any changes are required following initial ,

submittal of the PGP, the technical guidelines will be revised and promptly resubmitted for NRC review.

Following submittal of the PGP, efforts in 1987 will include development of the E0Ps (the current plan is to utilize a logic-diagram / flow chart format), perform validation and verification, develop lesson plans and perform training, and rewrite existing operating procedures so that they will be aligned with the new E0Ps. There efforts will continue

, through 1987, with the upgraded E0Ps being ready for imple-mentation in January 1988.

Issue A-035B FHSR Update Study Discussions with the NRC have resulted in the scope of this

! issue being increased to include a schedular exemption l request. The indexing system and schedular exemption l request have been submitted for NRC review and approval.

Submittal of the indexing system completes the activities i which were committed to be completed by 8/27/86. A final completion date will be established pending NRC review of l

our submittals.

Issue BN-050A2 Containment Isolation - On Line Testing of MSIV i

The power source for the MSIV and several other valves (including position indication) was transferred from the

! station battery to the alternate shutdown battery as a result of fire protection modifications. Because the loads ,

supplied by the alternate shutdown battery are few and continuous in nature, power demands can now be more accu-rately measured and attributed to a given component. An online testing procedure has been written and approved for implementation that involves the measurement of power drawn by the MSlV operator upon application of a temporary open/

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Director, Nuclear Reactor Regulation ,

7 Big Rock Point Plant Integrated Plan Semi-Annual Update No. 5 August 29, 1986 close signal. Implementation of this procedure will allow better assessment of MSIV reliability.

The Nuclear Safety Department, utilizing probabilistic risk assessment techniques, is in the process of evaluating the desirability of installing a second valve. The evaluation is expected to be completed by the end of this year. This issue will be considered active until the evaluation results have been reviewed by the TRG.

Issue B-106 Remove Turbine Crating Since the last semi-annual update, the possible alternatives to resolve this issue were more fully developed. Based on a significant increase in scope, this issue was presented to TRG a second time for review. During this review TRG reranked this issue from 15th to 29th out of 30 issues.

Based on the new ranking and the fact that administrative controls have been implemented to alleviate the original personnel safety concern, resoluti,on of this issue was rescheduled for completion during4 the 1988 refueling outage.

Issue BN-109 Backup High Range Stack Monitor Project has been scheduled for installation prior to startup from next refueling outage. ,

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al Ral h R risch W~

Senior Licensing Analyst

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CC Administrator, Region III, USNRC ,

NRC Resident Inspector - Big Rock Point Plant Attachments e t OC0886-0134-NLO2 1

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9 ATTACHMENT 1 Consumers Power Company

.) Big Rock Point Plant Docket 50-155 i

t.

ISSUE INDEX FOR THE BIG ROCK POINT INTEGRATED PL.AN August 29, 1986 3r ,

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i j 5 Pages l AT0886-0134-NLO2 l .

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ISSUES BY ISSUE NUMBER ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS B-001 -

HEAT EXCHANGER TUBE BUNDLE REPLACEMENT COMPLETE B-002 -

ACID LINE EXTENSION COMPLETE ,

B-003 -

REACTOR COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION COMPLETE B-004 - STACK,CAS MONITORING COMPLETE BN-005 18 CONTROL ROOM DESIGN REVIEW ACTIVE BN-006 SAFETY PARAMETER DISPLAY SYSTEM ACTIVE B-007 -

SCRAM DUMP TANK LEVEL INSTRUMENTATION COMPLETE B-008 -

SINGLE CHANNEL RESET INVESTIGATION COMPLETE B-009 -

REACTOR COOLIEG WATER PRESSURE STUDY COMPLETE B-009A 27 INSTALLATION OF TELLTALES ON SHUTDOWN HEAT EXCHANGER ACTIVE B-010 -

VENTILATION FOR PANEL C-52 COMPLETE B-011 -

RUCKER SYSTEM (STUDY) COMPLETE B-011A 2 TURBINE BYPASS SYSTEM IMPROVEMENTS ACTIVE B-012 -

RESIDUAL HEAT REMOVAL HEAT EXCHANGER TUBE FAILURE COMPLETE B-013 -

PURITY OF PRIMARY COOLANT COMPLETE B-014 -

SEISMIC DESIGN CONSIDERATIONS COMPLETE BN-014A 15 RESOLUTION OF SEISMIC ISSUES ACTIVE B-015 -

CONTAINMENT ELECRICAL PENETRATIONS COMPLETE B-016 5 SECONDARY SYSTEri INSTABILITIES ACTIVE B-017 -

PCS ISOLATION - PC SYSTEM COMPLETE f B-018 8 HIGH PRESSURE RECYCLE ACTIVE l B-019 -

HYDROGEN MONITORING COMPLETE l 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 DEVEL0EMENT CANCELLED B-024 -

INSTALLATION OF DP GAUGE ON NONREGEN HEAT EXCHANGER COMPLETE BN-025 20 WIND AND TORNADO LOAD & TORNADO MISSILE - ACTIVE i SEP TOPICS III-2 & III-4.A i

l B-026 -

ISI 0F WATER CONTROL STRUCTURES COMPLETE B-027 -

SERVICE WATER / COOLING WATER SYSTEMS COMPLETE B-028 -

PROXIMITY OF TECTONIC STRUCTURES COMPLETE AT0886-0134-NLO2

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> 2 ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS B-029 -

TURBINE MISSILES COMPLETE A-030 -

RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS COMPLETE B-031 -

DEFINITION OF OPERABILITY COMPLETE BN-032 7 EMERGENCY OPERATING PROCEDURE UPGRADE ACTIVE B-033 -

REFERENCE VOLUME CHAMBER REMOVAL COMPLETE B-034 -

CONTROL ROOM AIR CONDITIONING COMPLETE

, A-035B 26 FHSR UPDATE STUDY ACTIVE A-036 -

ENVIRONMENTAL QUALIFICATION OF ELECTRICAL COMPLETE EQUIPMENT (EEQ)

B-036A 15 EEQ PROGRAM ENHANCEMENTS ACTIVE B-037 -

PROBABLE MAXIMUM FLOOD CONSIDERATIONS COMPLETE

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B-038 -

SAFETY RELATED WATER SUPPLY - SEP TOPIC II-3.C COMPLETE B-039 -

EFFECTS OF HIGH WATER LEVEL - SEP TOPIC III-3.A COMPLETE B-040 -

PIPING AND SAFE END INTEGRITY COMPLETE B-041 - CLASSIFICATION OF STRUCTURES, SYSTEMS, & COMPONENTS COMPLETE B-042 -

ONGOING ISI COMPLETE 3-043 -

MECHANICAL SNUBBERS COMPLETE B-044 24 VERIFICATION OF BS&B VALVE DATA ACTIVE B-045 -

ECCS TEST TERMINAL BOX CANCELLED B-046 -

REVISED REACTOR VESSEL PRES 3URE/ TEMPERATURE LIMITS COMPLETE B-047 -

SPENT FUEL POOL CLEANUP COMPLETE B-048 -

CLEANUP DEMINERALIZER SYSTEM PUMP REPLACEMENT COMPLETE INVESTIGATION B-048A 8 CLEANUP DEMINERALIZER SYSTEM PUMP BYPASS ACTIVE B-049 -

VENTILATION SYSTEMS COMPLETE B-050A1 -

MSIV BACKUP VALVES - LEAK TESTING COMPLETE BN-050A2 5 CONTAINMENT ISOLATION - ONLINE TESTING OF MSIV ACTIVE BN-050B 23 CONTAINMENT ISOLATION - LEAK TEST OF SERVICE AND ACTIVE INSTRUMENT AIR B-050C -

CONTAINMENT ISOLATION - ISOLATION VALVES IN COMPLETE HEATING, COOLING, OR SERVICE WATER B-050D -

CONTAINMENT ISOLATION - ADD CONTROL CIRCUIT TO COMPLETE TREATED WASTE VALVE (CV-4049) h 1

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3 ISSUE ISSUE

_ NUMBER RANK ISSUE DESCRIPTION STATUS B-050E -

CONTAINMENT ISOLATION - AIR LOCK TESTING - COMPLETE SEP TOPIC VI-4 ,

B-050F -

CONTAINMENT ISOLATION - HAND ISOLATION OF COMPLETE INSTRUMENT LINES - SEP TOPIC VI B-050G -

CONTAINMENT ISOLATION - PNEUMATIC TEST OF MSIV - COMPLETE SEP TOPIC VI-4 BN-051 30 DESIGN CODES, CRITERIA AND LOAD COMBINATIONS ACTIVE B-052 -

HELB - SEP TOPIC III-5.A COMPLETE B-053 -

PIPE BREAKS OUTSIDE CONTAINMENT COMPLETE B-054 -

PLANT SHIELDING - NUREG-0737 ITEM II.B.2 COMPLETE B-055 -

METEOROLOGICAL TOWER COMPLETE B-056 -

ESF UPGRADE COMPLETE B-057 -

CONTROL ROOM HABITABILITY - NUREG-0737 COMPLETE B-057A -

CONTROL ROOM HABITABILITY - SEAL DOORS COMPLETE B-058 -

POST ACCIDENT SAMPLING COMPLETE B-059 -

MSLB OUTSIDE CONTAINMENT COMPLETE B-060 -

REVISED SECURITY PRINTS COMPLETE B-061 -

EQUIPMENT IDENTIFICATION CANCELLED B-062 -

REVISE DRAWINGS (SYSTEM CHECKSHEET VERIFICATION) COMPLETE B-063 -

CONTAINMENT PURGE AND VENT COMPLETE B-064 -

CONTAINMENT ILRT COMPLETE B-065 -

TEST CARD READER COMPLETE

, B-066 -

RADWASTE MONITOR FLUSH TIMER CANCELLED B-067 -

ISOLATION OF RPS FROM NONSAFETY SYSTEMS COMPLETE l B-068 -

DC SYSTEM MONITORING COMPLETE i

! B-069 -

ACID AND CAUSTIC TANK PROBLEMS COMPLETE B-070 -

EMERGENCY DG PANEL VENTILATION COMPLETE B-071 -

CHANGE PIPING IN CHEM LAB HOT HOOD CANCELLED l B-072 -

FACILITY MODIFICATIONS - WAREHOUSE COMPLETE B-073 -

CONTROL OF HEAVY LOADS COMPLETE l

B-074 -

REACTOR COOLANT SYSTEM - HIGH POINT VENTS COMPLETE A-075A -

ALTERNATE SHUTDOWN SYSTEM COMPLETE A-075B -

RADIANT ENERGY SHIELDS COMPLETE l

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. 4 ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS A-075C -

ASSOCIATED CIRCUITS COMPLETE B-076 -

CONTAINMENT HIGH RANGE MONITOR COMPLETE B-077 - INVESTIGATE INCORE AVAILABILITY PROBLEM COMPLETE B-077A -

INVESTIGATE INCORE AVAILABILITY PROBLEM CANCELLED B-078 -

CLEANUP SYSTEM DRAIN LINE COMPLETE B-079 -

CONTROL ROD MISOPERATION COMPLETE B-080 -

PERFORMANCE OF BWR SAFETY VALVES COMPLETE B-081 -

POSITION INDICATION OF PORV'S CGMPLETE B-082 1 RDS RELIABILITY IMPROVEMENTS ACTIVE B-083 -

FULL STROKE TESTING OF REACTOR DEPRESSURIZATION CANCELLED VALVE B-084 -

SCRAM DUMP TANK VALVE - LACK OF REDUNDANCY (STUDY) COMPLETE B-084A 12 SCRAM DUMP TANK REDUNDANT VALVES ACTIVE B-085 -

CONTAINMENT OVERPRESSURE - NITROGEN SUPPLY TO RDS COMPLETE ISOLATION VALVES B-086 -

BYPASS OF MOV THERMAL OVERLOADS COMPLETE B-087 -

P PE BREAK OUTSIDE OF CONTAINMENT COMPLETE B-088 -

MSLB OUTSIDE CONTAIIDfENT - RADIOLOGICAL CONSEQUENCES COMPLETE B-089 -

RCPB LEAKAGE DETECTION COMPLETE BN-090 - CLASSIFICATION OF STRUCTURES, SYSTEMS AND COMPONENTS COMPLETE l B-091 -

CONTAINMENT ISOLATION - POST LOCA SYSTEM WALKDOWNS COMPLETE 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 B-096 -

INSTALLATION OF ISOL VALVE UPSTREAM OF CV-4027 COMPLETE B-097 -

REPLACEMENT OF VIP-5 WITH MOTOR OPERATED VALVE COMPLETE B-098 -

REVISIONS TO 125-VOLT DC DRAWINGS COMPLETE B-099 -

EQUIPMENT CLASSIFICATION - RPS COMPONENTS COMPLETE BN-100 -

VENDOR INTERFACE AND MANUALS COMPLETE B-101 -

POST MAINTENANCE TESTING - RPS COMPONENTS COMPLETE AT0886-0134-NLO2 l

. 5 ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS B-102 -

EQUIPMENT CLASSIFICATION - ALL SAFETY RELATED COMPLETE EQUIPMENT B-103 -

POST MAINTENANCE TESTING - ALL SAFETY RELATED COMPLETE EQUIPMENT B-104 24 CORE SPRAY PUMP SUCTION STRAINER BLOCKAGE ACTIVE E-105 -

REACTOR DEPRESSURIZATION SYSTEM HANGER REPLACEMENT COMPLETE B-106 29 REMOVE TURBINE GRATING ACTIVE B-107 -

FLOOD ANNUNCIATION CANCELLED B-108 -

MAIN STEAM LINE DRAIN ISOLATION COMPLETE BN-109 28 BACKUP HIGH RANGE STACK MONITOR ACTIVE B-110 20 LIGHTNING PROTECTION ACTIVE

B-111 10 REPLACEMENT OF NEUTRON MONITORING INSTRUMENTATION ACTIVE A-112 13 ALTERNATE ROD INJECTION ACTIVE B-113 13 RELIEF VALVE FAILURES INVESTIGATION- ACTIVE B-114 20 RECIRCULATION PUMP ROOM LIGHTING ACTIVE B-115 3 CONDENSER MAKEUP WATER / CORE SPRAY INVESTIGATION ACTIVE B-116 10 CLEANUP DEMIN PIT ACCESS HANDRAIL ACTIVE B-117 4 REPLACE DIESEL FIRE PUMP ENGINE ACTIVE B-118 15 UNDER WATER FILTERING SYSTEM FOR SPENT FUEL POOL ACTIVE i

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a ATTACHMENT 2 Consumers Power Company Big Rock Point Plant Docket 50-155 4

I BIG ROCK POINT INTEGRATED PLAN OPEN ISSUES August 29, 1986 i

11 Pages AT0886-0134-NLO2

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!1 PAGE 1 BIG ROCK POINT PLANT

INTEGRATED PLAN TYPE ' A ' PROJECTS PLAN **

SCHEDULED ISSUE ISSUE C0tiPL ETIUtl NUMBER RANK TITLE DATE

)

i A -0358 26 FHSR UPDATE STUDY 00-00-00 t

639 SCOPE: STATUS:

. FINALIZE THE DESIGN AND IMPLEMENTATION INDEXING SYSTEM AND SCHEDULAR EXEMPTION 1 0F A Cot 1PUTERIZED DOCUMENT INDEXING SYSTEM SUDt1ITTED FOR HRC REVIEH OH 8/27/86. FINAL 1 AS A SUBSTITUTE FOR AN UPDATED FHSR, SUBMIT C0f1PLETION DAIE TO BE ESTABLISHED PENDING i SCHEDULAR EXEMPTION AND RESOLVE NRC NRC REVIEN OF DUR SUBMITTALS.

1 CONCERNS.

4 1

A -II2 13 ALTERNATE ROD INJECTION 09-30-86 1 685 SCOPE: STATUS:

PERFORM ADDITIONAL RISK BASED EVALUATIONS RISK ASSESSMENT EVALUATION ON SCHEDULE FOR 10 DETERMINE THE EFFICACY OF ALTERNATE ROD C0f1PLETION 9/30/86. SUBMITTAL To NRC HILL j INJECTION (IOCFR50.62). OCCUR FOLLONING PRESENTATION OF RESULTS TO TRG.

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1 BIG ROCK POINT PLANT ,

i INTEGRATED PLAN i

TYPE

• BN ' PROJECTS PLAN s SCllEDUL ED ISSUE ISSUE C0(1PL ETI0ll j NUMBER RANK TITLE DATE 1

i BM-005 18 CONTROL ROOM DESIGN REVIEW 03-01-87 j 530 #

! SCOPE: STATUS:

ISSUES TO BE ADDRESSED ARE THE HED'S VALIDATION HALKTHROUGils FOR ATHS AND FIRES ASSESSMENT AND PROPOSED CORRECTIVE ACTION, C0t1PLETED HEEK OF 7/21. VERIFICATION ND J IC. IN H N L D ONTRd Hh S FbR HSHAEBEENGNhATED ROOM EQUIPMENT SATISFIES SPDS NEEDS.

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BN-000 SAFETY PARAMETER DISPLAY SYSTEM 03-01-87 1 034 SCOPE: STATUS:

. HRITE AND SUBMIT SPDS SAFETY ANALYSIS SAFETY ANALYSIS PACKAGE HILL BE SUBMITTED

, PACKAGE FOR NRC REVIEH AND APPROVAL, FOR NRC REVIEH AND APPROVAL BY MARCH I, 1987.

1 DECLARE SPDS OPERATIONAL. SPDS OPERATIONAL DATE HILL BE DETERi1INED

] AFTER If IS DETERMINED IF ADDITIONAL HAPDHARE HILL BE REQUIRED. REFERENCE ISSUE BN-005 i .BN-014A 15 RESOLUTION OF SEISMIC ISSUES 88 REF OUT 699 l SCOPE: STATUS:

PERFORM MODIFICATIONS TO UPGRADE "0.0G* HEAK FIVE PROPOSED SEISMIC UPGRADE (10DIFICATI0 tis

! LINK COMMITMENTS. HERE RANKED BY THE TRG AT THE OCTOBER 8,1985

! TRG MEETING. PROJECT SCOPE AND SCHEDULE HAVE j BEEN INTIATED.

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PAGE 2 3 08/28/86 BIG ROCK POINT PLANT a-INTEGRATED PLAN TYPE ' BN ' PROJECTS PLAll a-1 SCHEDULED 3

ISSUE ISSUE COMPLETIUta j NUMBER RANK TITLE DATE I

, BN-025 20 HIND AND TORNADO LOADING 00-00-00 j 638 SCOPE: STATUS:

I SEP TOPIC III-2 AND III-4A. UPDATE ANALYSIS RESOLUTION OF flRC C0tC1ENTS AND REV. OF RISK I REFLECTING INTEGRATION WITH NEH QUALIFIED ANALY. TO INCLUDE ASD BLDG HILL C0C*1ENCE 4TH j ALTERNATE SHUTDDHN PANEL BUILDING. OTR 86. IF ADD STRUCT. At!AL . , Gell. OF FRAGIL-ITIES OR SITE SPECIFIC PROBABILISTIC TREATNT OF HISSILES IS REQ'D HORK SCOPE HILL BE PRE-

SENTED TO TRG & SCHEDULE EST. IST QTR 87.

1' BN-032 7 EMERGENCY OPERATING PROCEDURES UPGRADE 88 REF UUI 531 SCOPE: STATUS:

FINALIZE PLT SPEC TECH GUIDELINES. PREPARE RADI0 ACTIVE RELEASE GUIDLINES MUST BE l BASES DOC. FOR PLT SPEC GUIDELINES. SUBf1IT DEVELOPED. GENERAL AND SPECIFIC CAUTI0 TIS FOR j PROC GEN PKG TO NRC. DRAFT E0P FLOH CHARTS. ALL GUIDELINES TO BE HRITTE

N. PROCEDURE

GEN-i BEGIN OPERATOR TRNG. IMPLEt1ENT AND COMPLETE ERATION PACKAGE TO BE SUBNITTED TO !!RC IN DEC i VALIDATION & VERIFICATION PROGRAM. INCORP 1986. BECAUSE THE 87 REFOUT HAS BEEN f*0VED

NRC C0t1MENTS. COMPLETE OPERATOR TRAINING. TO 1988 THE Cor1PLETION DATE HAS BEEN SHIFTED.

l.

! B;4-050A2 5 CONTAINMENT ISO - ON-LINE TEST OF MSIV 87 REF uu!

J 495 l SCOPE: STATUS:

4 PROVIDE ON-LINE TEST CAPABILITY FOR THE MAIN A PROCEDURE TO TEST THE IISIV HAS BEEN HRITTEN l STEAM ISOLATION VALVE. AND APPROVED FOR It1PLEl1ENTATIO!I. IN ADDITION, NUCLEAR SAFETY DEPARTMENT EVALUATING DESIR-ABILITY OF INSTALLING SECOND VALVE USING PRA i

TECH.

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PAGE 3 1 08/28/86 BIG ROCK POINT PLANT -.

INTEGRATED PLAN

, TYPE ' BN ' PROJECTS j PLAN - o-SCHEDULED ISSUE ISSUE ConPLETIUH NUMBER RANK TITLE DATE BN-050B 23 LEAK RATE TEST DN SERVICE AND INSTRUMENT AIR 87 REF OUT j 494 SCOPE: STATUS:

PROVIDE A iEAK TEST PROGRAM FOR INSTRUMENT PRELIMINARY ENGINEERIliG UNDERHAY. TEST

AND SERVICE AIR LINE CONTAINMENT ISOLATION PROCEDURE BEING DRAFTED. SPf.RE CHECK VALVE 1 CHECK VALVES. PERFORM TEST. IN STOCK R00n. HORK HILL BE DONE ON MAINTENANCE ORDER.

4

, BN-051 30 DESIGN CODES, CRITERIA AND LOAD COMBINATIONS 00-00-00 640 l

SCOPE: STATUS:

REVIEN HORK PERFORMED BY CONTRACTORS ON REVIEN OF HOW TO COLLECTIVELY INTERRELATE SEP SEISMIC, HIND AND TORNADO MISSLES. REVIEH TOPIC III-2, 4.A, S.A & 6 FOR INPUT TO l ORIGIANAL PLANT STRUCTURAL DESIGN / ANALYSES STRUCTURAL ANALYSES IS TO BE COMPLETED BY i TO IDLATIFY POTENTIAL STRUCTURES, SYSTEMS 12/31/86. DVERALL COMPLETION DATE DEPEllDS

AND COMPONENTS FOR MODIFICATION. OH POTENTIAL MODIFICATIONS RESULTING FROH THESE REVIEHS.

l BN-109 28 BACKUP HIGH RANGE STACK MONITOR 87 REF OUT

! 592 (ROUTE RGEM EXAUST TO "0LD" MONITOR)

SCOPE: STATUS:

3 ROUTE THE EXHAUST OF THE HIGH RANGE STACK ENGINEERING IS COMPLETE HITH ANTICIPATED i

MONITOR THROUGH THE "0LD" HIGH RANGE STACK INSTALLATI0H PRIOR TO STARTUP FROH NEXT l MONITOR SHIELDING AS A BACKUP MONITOR. REFUELING OUTAGE.

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1 PAGE I 08/28/86 BIG ROCK PUINT PLANT -.

INTEGRATED PLAN TYPE ' B ' PROJECTS PLAN '*

SCHEDULED ISSUE ISSUE CDt1PLETION NUMBER RANK TITLE DATE B -009A 27 INSTALL TELLTALES ON SCS HT EXCH 87 PEF OUT 544 -

SCOPE: STATUS:

REQUIRES ROUTING DISCHARGE FRDM SHUTDOHN ENGINEERING OF PROJECT IS HEARLY COMPLETE.

HEAT EXCHANGER AND NON-REGEN HEAT EXCHANGER ANTICIPATE INSTALLATION DURING 87 REFUELING RELIEF VALVES TO A POINT VISIBLE TO THE OUTAGE. MATERIALS HAVE BEEN PROCURED.

OPERATORS. NEED TO PROCURE PIPE, INSTALL AND REVISE DRAMINGS. NON-SAFETY RELATED. -

B -Olla 2 RECOMMENDATIONS FOR TURBINE BYPASS SYSTEM 07-01-37 704 SCOPE: STATUS:

CHECK INTEGRITY OF CONNECTILN BETHEEN MAINTENANCE ORDERS TO CHECK CONNECTION OF HYDRAULIC CYLINDER AND MAIN VALVE STEM. HYDRAULIC CYLINDER AND TRANSDUCER REVEALED NO PURGE AIR FRDM HYDRAULIC PIPING AFTER LOOSE CONNECTIONS. HYDRAULIC SYSTEN TEST REPAIRS. DEVELOP TEST PROGRAM FOR HYDRAULIC PROCEDURE IN PRELIMINARY DRAFT.

SYSTEM. CHECK TIGHTNESS OF TRANSDUCER COUPL-ING TO VALVE STEM. ADJ. SERVO-AMP. GAIN.

B -016 5 SECONDARY SYSTEM INSTABILITIES 12-31-86 557 SCOPE: STATUS:

PERFORM ANALYSIS OF CONDENSER-HOTHELL/ FEED- ANALYSIS CURRENTLY IN PROGRESS.

HATER SYSTEM CHARACTERISTICS. PROVIDE RECDMMENDATIONS TO PREVENT LOSS OF FEEDWATER UPON PLANT LDAD REJECTION.

il 2 PAGE 08/23/86 BIG ROCK POINT PLANT a INTEGRATED PLAN TYPE ' B ' PROJECTS PLAN o i SCllEDUL Ell i ISSUE ISSUE COMPLETI0il

NUMBER RANK TITLE DATE 4

j B -018 8 HIGi* PRESSURE RECYCLE 88 REF OUI j 636

! SCOPE: STATUS:

IMPLEMENTATION THROUGH UPGRADED EMERGENCY CDnPLETE, PENDING FINAL IMPLEMEATATION OF OPERATING PRDCEDURES. E0P'S.

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i B -036A IS EEQ PROGRAM ENHANCEMENTS 07-01-88 t

713 i

i SCOPE: STATUS:

REVIEN & REVISE THE ADMI

N. PROCEDURE

S TO SEVEN OF SI EXISTING EEQ FILES REVISED.

PROVIDE ADDITIONAL EEQ PROGRAM CONTROL.

REVISE EXISTING EEQ FILES TO PROVIDE MORE CONSISTENT FORMAT HITH NEN LDCA PROFILE AND COMPONENT SHEETS (COMPUTER FORM).

1 B -044 24 VERIFICATION OF BS8B VALVE DATA 12-51-87 422 SCOPE: STATUS:

THIS IS AN ONGOING PROJECT. VALVE OPERATING DUE TO ALARA CONSIDERATI0t!S, THE REMAINIt!G DATA IS NEEDED FOR 28 0F 56 VALVES. DATA HILL BE COLLECTED HHEN VALVE t1AINTENAtlCE IS REQUIRED. VALVE DATA HAVE BEEN GATHERED FOR 28 VALVES. INSTRUMENT DATA SilEETS UPDATED, AS DATA IS GATHERED, SHEETS HILL BE UPDATED. NO CHANGE IN CBMPLETION DATE.

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PAGE 3 08/28/86 BIG ROCK POINT PLANT ..

INTEGRATED PLAN TYPE ' B ' PROJECTS .

PLAN s SCHEDULED ISSUE ISSUE COMPLETION NUNBER RANK TITLE DATE B -048A 8 INSTALL BY-PASS LINE AROUND CLEANUP DEMIN 12-31-86 415 SYSTEM PUMP SCOPE: STATUS:

SEPARATE OPERATION OF CLEANUP PUnP AND BYPASS LINE INSTALLED. ENGINEERING DESIGN DISCHARGE VALVE CV-4042. INSTALL CONTROL CHANGE FOR ELECTRIC CIRCUITRY FOR P-5 AND SNITCH FOR BYPASS LINE. CV-4042 TO INTERFACE HITH BYPASS LINE IS COnPLETE AND AHAITING ALL NECESSARY REVIENS, AND TESTING.

3 -082 1 RDS RELIABILITY IMPROV2MENTS 87 REF OUT 489 SCOPE: STATUS:

1. RESEARCH SYSTEM HISTORY. PURCHASE OF 4 NEN PILDT VALVES & VALVE TOPS

2. DEVELOP LIST OF POSSIBLE SYSTEM IN PROGRESS. INSTALLATION TO BE 1987 REFOUT.

IMPROVEMENTS. CONSIDER

• TION OF METHODS TO PERFORM IN PLACE

3. PROGRAM PLAN FOR SYSTEM MODIFICATION. FULL STROKE TEST OF TARGET ROCK VALVES IN

4. INITIATE AND IMPLEMENT FACILITY CHANGES. PROGRESS. DATE FOR RESOLVING FULL STROKE

5. INVESTIGATE FULL STROKE TEST METHODS. TEST ISSUE UNKNOHN.

B -084A 12 REDUNDANT VALVES FOR SCRAM DUMP TANK 87 REF OUT 487 SCOPE: STATUS:

ADD DOUBLE ISOLATION TO SCRAM DUMP TANK ENGINEERING IS IN PROGRESS. VALVES HAVE BEEN VENT LINE AND DRAIN LINE. NEED TO CDMPLETE PROCURED WITH ANTICIPATED INSTALLATION DURING DETAILED ENGINEERING INCLUDING PIPING 87 REFUELING OUTAGE.

ANALYSIS AND PROCURE VALVES FOR INSTALLATION.

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! BIG ROCK POINT PLANT ..

INTEGRATF.D PLAN TYPE ' B d PROJECTS ,

PLAN - e SCHEDULED-

ISSUE ISSUE C0tIPLETION 1

NullDER RANK TITLE '

DATE j B -104 24 CORE SPRAY PUMP SUCTION STRAINER BLOCKAGE 09-01-87 q

521 I SCOPE: STATUS:

l INVESTIGATE THE POSSIBILITY.0F BACKFLUSHING PRELIMINARY INVESTIGATION IN PROGESS. BACK-

, THE SUCTION STRAINER SCREENS OR ADDING GROUND INFORt1ATION IN CONJUNCTION HITH THE INSTRUMENTATION TO DETERMINE PUMP BLOCKAGE. VARIOUS ALTERNATIVES TO RESOLVE THIS ISSUE IS j BEING RESEARCHED.

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I B -10G 29 REMOVE TURBINE GRATING 88 REF UUI 573

]

SCOPE: STATUS:

MODIFY GRATING INSIDE TURBINE DOOR TO ALLOW PLANT HAS IHPLE!1ENTED ADMINISTRATIVE CONTROLS IT TO BE REMOVED TO ACCOMODATE PERSONNEL THAT PRECLUDE THE NEED TO MAKE THE T10DIFICA-ACCESS. TIONS COVERED BY THIS ISSUE. TRG HAS RERANKED PROJECT. HEH C0t1PLETION DATE CONSIDERING EXISTING 110RKLOAD AND PLANT PRIORITY HAS BEEN ESTABLISHED.

B -110 20 LIGHTNING PROTECTION 12-31-86

, 582

! SCOPE: STATUS:

i PERFORM MODIFICATIONS RECOMMENDED IN MEMO PRELIt1IllARY DESIGN PACKAGE GENERATED.

i LARK 02-84 (PARAGRAPHS 1,2 AND 3). FC PRELIMINARY EllG. PACKAGE HAS BEEN PRC j REVIEMED AND APPROVED.

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PAGE 5 BIG ROCK POINT PLANT ..+

INTEGRATED PLAN TYPE ' B ' PROJECTS .

$ PLAN t i

SCllEDULED i ISSUE ISSUE COMPLETIDH 4 MUHBER RANK TITLE DATE l

j B -111 10 REPLACEMENT OF NEUTRON MONITORING SYSTEM 89 REF DUT 002 SCOPE: STATUS:

1 FC-599 A,B, & C. REPLACEMENT OF NEUTRON EQUIP DELIVERY FOR CH 6 & 7 IS 9/30/86 NITH l MONITORING INSTRUMENTS (STARTUP, LOGN AND INSTALLATION 87 REFOUT. EQUIP DELIVERY FOR l P0HER RANGE), PROCESS AND AREA MONITORS. CN 1 - 5 IN 1987; INSTALLATION 88 REFOUT.

1 EQUIP DELIVERY FOR AREA & PROCESS MONITORS l IN 1989; INSTALLATION 89 REFOUl.

4

]

{ B -113 13 RELIEF VALVE FAILURES INVESTIGATION 06-30-87

549 1

i SCOPE: STATUS:

i DETERMINE THE INCONSISTENT SET POINT INFORMATION BEING DRANN FROM OTHER UTILITY 4

MEASUREMENTS OF RV'S. EVALUATION OF SYSTEM PROGRAMS (RV TESTING). PO ISSUED FOR PRE-SET POINTS, SET POINT TOLERANCES, TEST STAND CISION DIGITAL GAGE FOR BRP RV TEST PROGRAM.

APPARATUS AND SET POINT PROCEDURES. RECOnnENDATIONS GIVEN TO PRC ON 5/22/86.

PROCEDURES (NEN/ REVISED) BEING DRAFTED FOR ESTABLISHING SET POINTS ON VALVES, i

B -114 20 RECIRC. PUMP ROOM LIGHTING 88 REF OUI 4

696 -

i SCOPE: STATUS:

INSTALL SEMI-PERMANENT LIGHTING UNDER THE MAINTENANCE ORDER HRITTEN FOR INSTALLATION

! STEAM DRUM AREA. SEPARATE ELECTRICAL CIRCUIT OF SEMI-PERnANENT LIGHTING. ANTICIPATE

( FOR NORMAL AND EMERGENCY LIGHTING IN RCP INSTALLATION DURING 87 REFUELING OUTAGE.

! ROOM / STEAM DRUM AREA. SEPARATION OF ELECTRICAL CIRCUITS HILL BE

} PERFORMED DURING 88 REFUELING OUTAGE.

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PAGE 6 BIG ROCK POINT PLANT ,f INTEGRATED PLAN TYPE ' B ' PROJECTS ,

PLAtt .g SCHEDULED ISSUE ISSUE Col 1PL ETIUt3 NUNDER RANK TITLE DATE B -115 3 CONDENSER MAKEUP N20 / CORE SPRAY INVEST. 12-31-87 515 SCOPE: STATUS:

EVALUATE ALTERNATE MAKEUP HATER TO HOTHELL/ PROJECT HAS ASSIGNED. HORK TO BEGIH UPON CORE SPRAY AND PROVIDE RECONMENDATIONS TO TRG COI1PLETION OF OTHER PROJECTS CURRENTLY IN FOR POTENTIAL PLANT MODIFICATION. PROGRESS.

5 -116 10 CLEAN-UP DEMIN PIT ACCESS - HANDRAIL 87 REF OUT 097 SCOPE: STATUS:

PROVIDE A SAFE MEANS OF ACCESSING THE BOTTOM ENGINEERING IN PROGRESS FOR MODIFICATION OF THE CLEAN-UP DEMIN PIT HHILE AVOIDING INSTALLATION 87 REFOUT.

EQUIPMENT DAMAGE.

B -117 4 REPLACE DIESEL FIRE PUMP ENGINE 87 REF OUI 714 SCOPE: STATUS:

PROCURE AND INSTALL A NEH DIESEL ENGINE DRIVE THE REPLACE!1ENT OF A DIESEL EtlGIllE DRIVE FOR FOR FIRE PUMP P-7. P-7 HITH A Col 1PATIBLE DRIVE FOR DRIVIllG A RIGHT AtlGLE GEAR HAS BEEN INITIATED AND PRELIMINARY SCOPE IS COMPLETE.

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INTEGRATED PLAN

! TYPE ' B ' PROJECTS .

PLAN **

SCilEDULED ISSUE ISSUE COMPLETI0!l NUi1 DER RANK TITLE DATE i

B -118 15 UNDERNATER FILTERING SYSTEM FOR SFP 12-51-86 1 705 SCOPE: STATUS:

INSTALL UNDERHATER FILTERING SYSTEM FOR THE CONCEPTUAL DESIGN PACKAGE AtlD SOME DETAILED SPENT FUEL POOL. ENGINEERING COMPLETED. PACKAGE ROUTED FOR .

PRC REVIEll. ATP FOR UFU 250 UNIT PREPARED.

COST ESTINATE FOR CONSTRUCTION MATERIALS EXPECTED FROM RYERSON.

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