ML20212D866
| ML20212D866 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/27/1987 |
| From: | Frisch R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8703040219 | |
| Download: ML20212D866 (29) | |
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i' Consumers Power rewramus maaraammaars paggAE55 oeneral offices: 1945 West Parnell Road, Jackson, MI 49201 * (517) 788-0550 February 27, 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. 6 i
As required by the Big Rock Point operating license, this letter provides the sixth update of the status of the Big Rock Point Plant Integrated Plan. contains an index of all issues, and identifies them by category, rank, description and status. Attachment 2 contains a detailed list of all open issues which includes scope, status and applicable schedule dates.
SUMMARY
OF INTEGRATED PLAN ACTIVITIES SINCE THE AUGUST, 1986 UPDATE:
Two meetings of the Technical Review Group (TRG) were held; the first was in September, 1986 and the second was in December 1986. No issues were cancelled by TRG, and one new issue (B-119: Acid system modifications) was added to Integrated Plan. This issue is described later in this report.
In November 1986 administrative controls related to management of the Integrated Plan were revised to permit cancellation of issues based on their scores. If an issue has a score of 5 or less TRG will recommend that it be deleted.
Resolutions for six issues were completed during this reporting period.
Descriptions of the issues / resolutions are provided in the next section of this report.
SUMMARY
OF ISSUES COMPLETED SINCE THE AUGUST, 1986 UPDATE:
Issue B-009As Install te11 tales on the shutdown system heat exchanger.
The need for installation of telltales was to facilitate detection of leakage through the shutdown cooling system heat exchanger relief valves.
Inasmuch as the discharge piping from the relief valves is piped directly to the enclosure dirty sump, the absence of a telltale on the discharge of the relief valves
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Nuclear Regulatory Commission Big Rock Point Plant Integrated Plan Semi-Annual Update #6 I
February 27, 1987 Although not made such determinations very difficult and time-consuming.
reflected in the title of this issue, a telltale for the cleanup system non-regenerative heat exchanger was also required.
Modifications to install the telltales were completed during the 1987 refueling outage.
Install cleanup system pump bypass line.
Issue B-048A:
The purpose of this item was to reduce the cost of operating and maintaining itself.
the cleanup system by minimizing the running time of the cleanup pump This was accomplished by installing a bypass line, with associated valving, ensure cessation of cleanup system flow under high temperature conditions.
around the cleanup pump.
Modifications have been completed.
Leak rate test of containment penetrations for instrument Issue BN-050B:
and service air.
Resolution of this issue required the development of a procedure to perform a local leak rate test of the containment instrument and service air penetrations, which had previously been exempt from the local leak rate testing requirements of 10CFR50 Appendix J.
The procedures have been developed and were conducted during the 1987 refueling outage.
Issue B-084A: Scram dump tank redundant valves.
The purpose of this item was to increase isolation reliability of the scramIn dump tank vent and drain lines by installing a second valve in each line.
l addition, position indication for the new valves was provided in the contro room.
Modifications to install additional valves and associated indicating lights were completed during the 1987 refueling outage.
Issue BN-109: Backup high range stack monitor.
involved installation of equipment As indicated by its title, this issue needed to provide an alternate method of determining high range stack An alternate method was specified in the radiological effluent Modifications have been completed.
releases.
technical specifications (RETS).
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Big Rock Point Plant Integrated Plan Semi-Annual Update #6 February 27, 1987 Issue B-117: Replacement of the engine for the diesel fire pump.
Replacement of the diesel fire pump engine was given a high ranking by TRG on-the basis of repeated engine problems which indicated deteriorating reliability of the diesel fire pump. The diesel driver has been replaced; work was completed during the 1987 refueling outage. Results of.the acceptance tests performed for this modification indicate a significant improvement in performance.
STATUS OF ACTIVE ISSUES CATEGORY A ISSUES:
Issue A-035B: FHSR Update The initial scope for resolving this issue consisted of developing a computerized document indexing system which would permit the plant staff to more readily retrieve information on the docket. The retrieved information could then be used in preparing safety evaluations to meet 10CFR50.59 requirements.
Based on concerns raised by the NRC staff in late 15J6, Consumers Power Company agreed to change the scope of this project such that the FHSR would be updated to reflect current plant design, license requirements, transient and accident analyses, and other conditions relevant to the original FHSR. The basic format of the original FHSR will be retained, without regard to Standard Review Plan criteria for format and content of Final Hazard Summary Reports.
Consumers Power Company letter, dated December 3, 1986, to the Director of Nuclear Reactor Regulation provides a detailed description of the revised scope for the resolution of this issue.
This issue and revised resolution were reviewed by the Technical Review Group (TRG) during its December, 1986 meeting; no significant change in the ranking of this issue resulted from this review. The current schedule for performing the effort described above calls for completion by December 31, 1988.
Issue A-112: Alternate Rod Injection.
Resolution of this issue is required to address the ATWS rulemaking. The scope of this issue was to perform risk-based analyses to determine the efficacy of providing alternate rod injection for Big Rock Point.
The risk analysis was submitted to the NRC on October 1, 1986. On December 29, 1986, an exemption from the alternate rod injection portion of the ATWS rule was submitted to the NRC for approval. The exemption request is awaiting NRC review and approval.
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CATEGORY'BN ISSUES:
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Issus BN-005:- Control Room Design _ Review (CRDR).
l' In the'past six months, all CRDR task activities have been completed. The Part.1-summary report >is'to be submitted to the NRC during'the first week of
- March,:1987..During'the next six' months, CRDR activity'wil1~ consist of determining corrective actions _for remaining human _ engineering deficiencies i
' (HEDs), submittal of.HEDs and proposed corrective actions to TRG for review p
^ and' ranking..and preparation.of the Part II summary report for submittal by.
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Issue BN-006: ~ Safety Parameter Display System (SPDS).
- The safety analysis package has been. completed and will be submitted for NRC-review as part of the Part I summary report for the Control Room Design
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' Issue BN-014A Resolution of seismic " weak links".
L This issue has been divided into several phases; the first phase-consisted of -
- identifying those components and structures which could not be demonstrated to have any seismic resistance (eg, 0-g weak links). Subsequent phases would be-
_ performed to identify components and structures having increasingly greater j-resistance. At the conclusion of each of'these phases, proposed resolutions l
to strengthen the weak 111nks would be evaluated until the determination could l
- be,made that further modifications would no longer be cost effective.
I At this time, the 0-g weak links have been identified and resolutions thereto ranked by TRG. They are being resolved as follows:
Provide tip protection for cabinets located adjacent to uninterruptible power supplies for Reactor Depressurization System channels B and D.
A modification correcting this situation was completed in October, 1986.
Provide protection for reactor building pressure transmitter PT-174 to ensurelit cannot be damaged by lead shielding installed nearby. Further analysis has shown no modifications are required to protect the transmitter; therefore, this portion of the issue resolution is considered i
to be complete.
Provide protection for emergency condenser outlet valves MO-7053 and H0-7063 and core spray / backup core spray valves MO-7051, MO-7061, MO-7070, and MO-7071 to protect them from striking nearby walls and piping in the event of a seismic occurrence. Modifications to address this situation are planned to be completed prior to completion of the 1988 refueling L
outage.
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' ;Provida protection.for enclosure spray valves M0-7064 and MO-7068 to
' ensure:they will not be damaged as a result of~ tipping of the three-ton crane;fAdditional analyses are being performed to verify the necessity of modifications:to prevent damage-to-the enclosure spray valves;;if
. modifications are found to be nacessary, a schedule to perform them will be developed.
Structurally upgrade one support column in the outside cable ~ penetration
. room. Tsis modification 1s planned to be complete prior to startup from-the 1988 refueling outage.
Relocation of' pressure switches PS-636 and PS-7064 (enclosure spray actuation). The pressure switches will be renoun*ed a the south wall of the outside cable' penetration room; the modificatic scheduled to be complete by the end of the 1988. refueling outage.
The next phase of,this issue requires identification of 1.0g weak links. This
- phase is in progress and is scheduled to be complete by July 31, 1987. At that time, the 1.0 g weak links and proposed resolutions for each will be presented to TRG for consideration and ranking.
Issue BN-025: Wind.and tornado loading.
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Resolution of this issue will be the procurement of portable pumps which can be operated independently of the screen house. The pumps will be stored in a structure having high resistance to winds and tornados; current plans call for use of the alternate shutdown building as the storage facility. As indicated by Consumers Power Company letter dated February 13, 1987, the schedule for procurement and installation of the pumps, as well as for a dedicated fuel supply (if needed) will be developed and included in the next semiannual update.
Issue BN-032:
Emergency Operating Procedures Upgrade.
In December, 1986, the Procedures Generation Package (PGP) was submitted to the NRC for review. At the January, 1987 Plant Review Committee (PRC) meeting, the PGP was submitted for PRC review. Completion of PRC's review is anticipated in mid-March, 1987, at which time development of the first draft of the E0Ps is scheduled to start. Per the program plan, completion of NRC's review is expected by April 1, 1987. Other activities (training, validation, verification) will commence upon development of the E0Ps. The project is still scheduled to be completed by the end of the 1988 refueling outage.
Issue BN-050A2: Containment isolation; on-line test of the MSIV The scope of this issue was to develop a method for testing the main steam isolation valve (MSIV) with the plant on line, so that a broader base of valve operating data (eg, successes / failures) could be developed. This data, in OC0287-0058-NLO4
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' Nuclear Regulatory Commission-6 Big Rock Point. Plant' Integrated Plan Semi-Annual Update #6 February 27,'1987 turn, would be used to refine risk-based studies which woul'd determine the need to improve; isolation capability of the main steam line.
A procedure for on-line testing of the MSIV was implemented in August, 1986.
Since that time, on-line tests have been conducted five times with no failures.
A risk-based study to determine if a second MSIV should be installed has been completed;'the study indicates that a second MSIV is marginally desirable.
The study, which includes alternatives to installing a second MSIV, will be reviewed by TRG during its March, 1987 meeting.
Issue BN-051: Design codes, design criteria and load combinations.
(ref: SEP Topic III-7B)
A revised resolution for this issue-has been developed and will be presented to the Technical Review Group for consideration and ranking during the March 1987 meeting. The proposed resolution is as follows.
Keview 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 modifications should be performed to address valid concerns identified during the reviews discussed above.
CATEGORY B ISSUES:
Issue B-011A Recommendations for turbine bypass system.
The scope related to this issue consisted of the following actions:
Check the integrity of the connection between the hydraulic cylinder and the main valve stem. This action has been completed; the connection was found to be tight, as required for proper operation.
Check the tightness of the transducer-to-valve stem coupling. This action has been completed; the coupling was found to be tight as required.
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-February 27, 1987-1 I*~ ? Develop's test-p'rogram for the hydraulic system. A'dhaft procedure has.
- been prepared'and will be reviewed followingLthe.1987 refueling outage.
i Ensure air is_ purged from the hydraulic system whenever the system is opened for repairs. A method for ensuring that this is performed has not yet been_ determined; however it is still anticipated that the scheduled-completion date_of July 1, 1987 will be met.
Adjust servo-amplifier gain. This is considered to be a "last_ resort" method for improving system performance, since such adjustments carry the risk of causing undesirable system performance.
, Issue B-016: Secondary system instabilities.
This issue stems from the observed phenomena that when the turbine bypass valve opens-with the turbine at or near full load, condenser hotwell level can swell sufficiently to cause the condensate reject valve to fully open, such that th( reactor feedwater pumps trip on low suction pressure. This situation not only represents the potential for an undesirable challenge to reactor safety systems, but is an initiator for-dominant accident sequences considered in the Big Rock Point Probabilistic Risk Assessment (PRA).
An analysis of condenser hotwell/feedwater system characteristics has been completed, and recommended changes have been proposed to resolve the problem.
Recommended fixes include:
Provide a separate reject line from the hotwell to the condensate storage tank. This would allow condensate rejection to occur without af fecting condensate pump discharge pressure.
Increase the hotwell level range band for control of the reject valve, and limit the reject capacity of the reject valve.
Change the condenser high pressure trip setpoint (reactor scram) from 8"Hg (abs.) to 10" Hg (abs.). This recommendation has been made with the intent that it be implemented in addition to whichever of the first two recommendations is selected for implementation. This recommendation has no bearing on feedwater system reliability, but is intended to reduce the potential for a direct challenge to the reactor safety system.
The above recommendations are being evaluated; the decision regarding which of the recommendations (if any) should be implemented will be made by July 1, 1987.
ISSUE B-018: High pressure recycle.
The resolution to this issue will be the development of a procedure which will permit an alternate method of recirculating and cooling water in the OC0287-0058-NLO4
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- February 27, 1987-containment. sump when the post incident system is not capable of performing
,this function. - Implementation of this procedure will be in conjunction with the upgraded emergency operation procedures (EOPs).
Issue-B-036A:-.EEQ Program enhancements.
'This: issue is a' follow-on to the development of the initial EEQ program for-Big Rock' Point;-its scope consists of the following' activities:
Ensure. administrative controls are in place to provide a high degree.of assurance that EEQ requirements are preserved during the course of maintenance and modification _ activities. This effort has been completed
'to the extent that the minimum administrative controls needed to preserve EEQ requirements are in place. Refinement and augmentation of these controls are scheduled to be complete by July 1, 1988.
- *' Provide guidance for the development of new EEQ files and the revision of existing files. -This effort will be completed by July 1, 1988.
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Review exit,tig EEQ files to incorporate the new main steam line break-temperature prol.le and convert the component data sheets to a computer-i produced form. Seven files have been revised, and it is anticipated that four.or five additional files will have been revised by the completion of
'the 1987 refueling outage. Completion of this activity is scheduled for-July 1,-1988.
Issue B-044: Verification of BS&B valve data.
The purpose of this project is to obtain valve operating data for BS&B valves installed in the Plant. This on-going project involves obtaining the data during performance -of maintenanc e on the subject valves; to date, data on 28 of 56 valves has been obtained.
Issue B-082: RDS Reliability improvements.
The scope of this issue consists of two major parts: correction of valve leakage problems, and development of an economical method to fully stroke the valves during testing.
Efforts to correct valve leakage have consisted of the following:
Closing forces within the pilot valve assembly have been increased in two ways.
(1) The pilot disc hold-down spring preload force was doubled from approximately 6 lbs to 12 lbs.
(2) The through hole size in the main disc was increased from 0.110 to 0.140; this will result in higher closing forces from system pressure. These changes are intended to prevent the onset of leakage through the pilot valve.
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- - A pilocidisc. sleeve has been~added around the pilot disc and the pressure' inlet _ hole:through the main disc repositioned from_approximately'45'
- degrees'to a horizontal orientation.
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The. materials in the main' valve-top,-pipe nipples, elbow and position.
indicator-housing were changed from carbon. steel to stainless steel-in an-attempt-to reduce the quantity-of corrosion products which can enter the
~ pilot-valve assembly and;become ' lodged on the pilot valve L seat.
The main valve top bolting has been replaced with new stud-bolts, double
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nuts and washers. This change was not associated with efforts to reduce
. leakage, but rather were intended to improve torquing operations during valve reassembly.
The actions described above were completed during the 1987 refueling outage.
Additional actions to improve valve performance will include investigations to
- determine if the main disc hold-down springs should be replaced and the main valve disc and seats replaced or refurbished. A schedule for this
- inve'stigation/ study is being developed.
- To ' resolve the issue with respect to full-stroke testing of the
. depressurization valves, a feasibility study is being performed to determine-whether in-place testing can be performed. The test method under
. consideration would involve supplementing the volume of the spoolpiece between each depressurization valve and isolation valve by using an accumulator. This study is expected to be completed by July 31, 1987, at which time recommendations will be'made to the Technical Review Group for consideration and ranking.
Issue B-104: Core spray pump suction strainer blockage.
The scope of this issue is to determine the feasibility of installing instrumentation to determine core spray pump net positive suction head and/or 1
l providing the capability to backflush the suction strainer screens.
L Background information, including Generic Letter 85-22, the Standard Review Plan and. Regulatory Guide 1.82, is being reviewed to determine the suitability of various. alternatives. Determination of a means to resolve this issue is scheduled to be complete by September 1, 1987.
Issue B-106: Remove turbine grating.
The purpose of this item is to enhance personnel safety by providing an additional egress route from under the turbine. The current method of j
implementing security requirements for the area under the turbine prevents rapid exit from that area under emergency conditions. Resolution of this r
issue would require installation of an easily-opened barrier which would facilitate egress while still meeting security requirements.
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Because of the. low ranking'for'this-issue,'a recommendation for its
,cancelation will be made at the next TRG meeting.
Issue B-110: ' Lightning protection.
Resolution of.this. issue would make the plant less susceptible to damage from clightning s'trikes, thereby improving plant reliability and availability.
, Proposed modifications include:
- -Eliminate the routing of DC alarm circuits to the well house.
- ' Add surge arresters on each phase of the power leads for the well pump.
Ensure ~the stack ladder and platforms are properly grounded.
Modify the grounding of the meteorological. system.
Modify lightning protection for the stack.
The design package for the modifications discussed above is under technical review. The modifications are scheduled to be completed by June 30, 1987.
' Issue B-111: Neutron monitoring system equipment replacement.
The scope of.this item includes replacement of the cabling and electronic
. portion of the power range, intermediate range, and source range neutron monitoring equipment with state of the art equipment. The detectors will not be changed. As'part of the conversion, the intermediate range channels will
'be combined with the power range instrument channels.
During the 1987 refueling outage, the source range instrumentation was replaced. Replacement of the remaining instrumentation is scheduled to be
' completed during the 1988 refueling outage.
Issue B-113: Relief valve failure investigation.
This issue was initiated in response to numerous problems experienced with relief valve leakage, setpoint drif t, and sticking. The project is one of an on-going nature; accordingly, projection of a completion date at this time is not practicable.
During the 1987 refueling outage, a significant finding was made with respect to the steam drum relief valves when it was determined that lapping compound residue was causing the valve seats and discs to bind, with the result that the relief setpoints were significantly increased. This condition, which has been corrected, will be reported in detail in a licensee event report to be submitted in the near future.
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-Issue B-114: Recirc pump room lighting.:
O Thiis ' issue resulted from a personnel safety concern with respect to poor
- 1ighting in the recirculating pump room / steam drum cavity. -During the
- 1987
-. refueling outage, additional lighting was installed underneath the steam drum.
Modifications to provide's separate source of electrical power for'11ghts in Lthe recire pump room will be completed during the~1988 refueling outage..
Issue'B-115:- Provide an alternate source of makeup to the condenser hotwell.
The' scope of this issue is to determine if modifications are needed to assure
- a source of makeup water to the condenser hotwell in the event normal sources of condensate makeup are depleted. Potential methods'being considered include use of the existing tie-in from the firewster system (through motor-operated valves NO-7073 and MO-7074) with no modification, modification to the control'
. schemes for MO-7073 and HO-7074 to cause these valves to close automatically.
upon opening of the primary or backup core spray valves; or use of a different system (eg, service water.or condenser circulating water) to supply water.
Studies to permit making this determination will be completed by December 31,
'1987.
Issue B-116: Install handrail in cleanup demin pit access.
This issue resulted from both a concern for personnel safety as well as for avoiding equipment damage. The resolution of this issue requires installation of a removable platform which will ensure safe access to the cleanup domineralizer pit without the need to step on fragile equipment such as air operated' valves.
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Completion was scheduled for the 1987 refueling outage; however, measurements needed to verify the design of the platform could not be performed early enough in the outage to permit fabrication to begin on schedule. The required measurements were obtained during the 1987 refueling outage; the platform will be fabricated prior to the 1988 refueling outage, with installation scheduled for the 1988 refueling outagu.
Issue B-118: Underwater filtering system for the spent fuel pool.
The principal reason for implementing this design change was to lower radiation fields in the vicinity of the spent fuel pool and filter sock tank and to provide a more efficient means of cleaning spent fuel pool water and I
reactor vessel water during head-off operations.
All hardware has been installed. Although the vacuuming equipment performs in accordance with design requirements, the radiation monitoring equipment does not, such that automatic (unattended) operation of the system cannot be performed. The equipment vendor has made recommendations which will be implemented following the 1987 refueling outage.
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-Big Rock Point Plant Integrated Plan Semi-Annual Update #6 February 27, 1987-will be fully operational by August 1, 1987. Although work to enhance system performance remains to be done, and completion of this issue will'not be reported until such work is complete, the December 31, 1986 commitment date for installation of. underwater filtering equipment is' considered to have been met.
Issue B-119: Acid system modifications to eliminate piping cerrosion.
This issue was presented to TRG at the September,-1986 Technical Review Group meeting. Problems with the acid system had been previously addressed (reference completed issues B-002 and B-069); however, a permanent solution to this long-standing personnel safety issue has been elusive. TRG has commissioned a study to determine a fix to this problem. A schedule will be developed by June 1, 1987.
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Ralph R Frisch Senior Licensing Analyst CC Administrator, Region III, NRC hhc Resident Inspector - Big Rock Point Plant Attachment OC0287-0058-NLO4
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. ISSUE INDEX FOR THE BIG ROCK FOINT INTEGRATED PLAN February 27, 1987 i '
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ISSUES BY ISSUE NUMBER
, 11SSUE ISSUE
, NUMBER RANK ISSUE DESCRIPTION
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': STATUS 1
. g B-001' HEAT EXCHANGER TUBE BUNDLE REPLACEMENT.
COMPLETE
,5-002.
t,: ACID LINE EXTENSION COMPLETE' B-003 REACTOR' COOLANT PRESSURE BOUNDARY LEAKAGE DETECTION' COMPLETE
'B-004 STACK GAS MONITORING
. COMPLETE f
-BN-005 16 CONTROL' ROOM DESIGN REVIEW ACTIVE BN-006 SAFETY PARAMETER DISPLAY SYSTEM ACTIVE-B-007' SCRAM DUMP TANK LEVEL INSTRUMENTATION COMPLETE 1
B-008 SINGLE CHANNEL RESET INVESTIGATION COMPLETE.
'T B-009 REACTOR COOLING WATER PRESSURE STUDY
. COMPLETE B-009A INSTALLATION OF TELLTALES ON SHUTDOWN HEAT EXCHANGER -COMPLETE B-010 VENTILATION FOR PANEL C-52 COMPLETE B-011 RUCKER SYSTEM (STUDY)
COMPLETE B-011 A-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 13 RESOLUTION OF SEISMIC ISSUES ACTIVE B-015-CONTAINMENT ELECTRICAL PENETRATIONS COMPLETE B-016 5
SECONDARY SYSTEM INSTABILITIES ACTIVE B-017 PCS ISOLATION - PC SYSTEM COMPLETE B-018 8
HIGH PRESSURE RECYCLE ACTIVE B-019 HYDROGEN MONITORING COMPLETE B-020 INSTRUMENTATION TO DETECT INADEQUATE CORE COOLING COMPLETE i
B-021 RECIRCULATION PUMP TRIP COMPLETE ORGANIC MATERIALS (WALL COATINGS)
COMPLETE Bt:-022A F
B-0225 POST ACCIDENT CHEMISTRY - SEP TOPIC VI-1 COMPLETE i
B-023 BALANCE OF PLANT QA PLAN DEVELOPMENT CANCELLED l-B-024-INSTALLATION OF DP GAUGE ON NONREGEN HEAT EXCHANGER COMPLETE i
BN-025 19 WIND AND TORNADO LOAD & TORNADO MISSILE -
ACTIVE r,
P SEP TOPICS III-2 & III-4.A
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ISI 0F WATER CONTROL STRUCTURES COMPLETE B-026 SERVICE WATER / COOLING WATER SYSTEMS COMPLETE B-027 B-028 PROXIMITY OF TECTONIC STRUCTURES COMPLETE h3
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ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS-TURBINE luSSILES COMPLETE B-029 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS COMPLETE A-030 EB-031 DEFINITION OF OPERABILITY COMPLETE
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BN-032 7
EMERGENCY OPERATING PROCEDURE UPGRADE ACTIVE REFERENCE VOLUME CHAMBER REMOVAL COMPLETE B-033 B-034 CONTROL ROOM AIR CONDITIONING COMPLETE A-035B 22 FHSR UPDATE STUDY ACTIVE A-036 ENVIRONMENTAL QUALIFICATION OF ELECTRICAL COMPLETE EQUIPMENT (EEQ)
B-036A 13 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 PIPING AND SAFE END INTEGRITY COMPLETE B-040 CLASSIFICATION OF STRUCTURES, SYSTEMS, & COMPONENTS COMPLETE B-041 B-042 ONGOING ISI COMPLETE MECHANICAL SNUBBERS COMPLETE
-B-043 B-044 20 VERIFICATION OF BS&B VALVE DATA ACTIVE ECCS TEST TERMINAL BOX CANCELLED B-045 REVISED REACTOR VESSEL PRESSURE / TEMPERATURE LIMITS COMPLETE
-B-046 SPENT FUEL POOL CLEANUP COMPLETE B-047 CLEANUP DEMINERALIZER SYSTEM PUMP REPLACEMENT COMPLETE B-048 INVESTIGATION B-048A CLEANUP DEMINERALIZER SYSTEM PUMP BYPASS COMPLETE VENTILATION SYSTEMS COMPLETE B-049 MSIV BACKUP VALVES - LEAK TESTING COMPLETE B-050Al BN-050A2 5 CONTAINMENT ISOLATION - ONLINE TESTING OF MSIV ACTIVE BN-050B CONTAINMENT ISOLATION - LEAK TEST OF SERVICE AND COMPLETE INSTRUMENT AIR CONTAINMENT ISOLATION - ISOLATION VALVES IN COMPLETE B-050C HEATING, COOLING, OR SERVICE WATER B-050D CONTAINMENT ISOLATION - ADD CONTROL CIRCUIT TO COMPLETE TREATED WASTE VALVE (CV-4049)
M10287-0084A-nXCl-NLO4
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ISSUE ISSUE NUMBER RANK ISSUE DESCRIPTION STATUS CONTAINMENT ISOLATION - AIR LOCK TESTING -
COMPLETE B-050E
'SEP TOPIC VI-4
~
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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 24 DESIGN CODES, CRITERIA AND LOAD COMBINATIONS ACTIVE HELB - SEP TOEIC III-5.A COMPLETE B-052 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 CONTROL ROOM HABITABILITY - NUREG-0737 COMPLETE
~B-057 B-057A CONTROL ROOM HABITABILITY - SEAL DOORS COMPLETE POST ACCIDENT SAMPLING COMPLETE ~
B-058 MSLB OUTSIDE. CONTAINMENT COMPLETE B-059-REVISED SECURITY PRINTS COMPLETE B-060 EQUIPMENT IDENTIFICATION CANCELLED B-061 REVISE DRAWINGS (SYSTEM CHECKSHEET VERIFICATION)
COMPLETE.
B-062 CONTAINMENT PURGE AND VENT COMPLETE B-063 CONTAINMENT ILRT COMPLETE B-064 TEST CARD READER COMPLETE B-065
~
- B-066 RADWASTE MONITOR FLUSH TIMER CANCELLED ISOLATION OF RPS FROM NONSAFETY SYSTEMS COMPLETE B-067 DC SYSTEM MONITORING COMPLETE B-068 ACID AND CAUSTIC TANK PROBLEMS COMPLETE
~B-069 EMERGENCY DG PANEL VENTILATION COMPLETE
'B-070 CHANGE PIPING IN CHEM LAB HOT HOOD CANCELLED B-071 FACILITY MODIFICATIONS - WAREHOUSE COMPLETE B-072 B-073 CONTROL OF HEAVY LOADS COMPLETE REACTOR COOLANT SYSTEM - HIGH POINT VENTS COMPLETE B-074 ALTERNATE SHUTDOWN SYSTEM COMPLETE A-075A RADIANT ENERGY SHIELDS COMPLETE A-075B MIO287-0084A-BX01-NLO4
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ISSUE : IS' SUE
, ' NUMBER. RA'K ISSUE ~ DESCRIPTION STATUS I -075C
. ASSOCIATED CIRCUITS COMPLETE-A B-076 CONTAINMENT HIGH RANGE MONITOR COMPLETE 7
[
iB-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-
' POSITION INDICATION OF PORV'S COMPLETE
.B-081 B-082
.1 RDS RELIABILITY IMPROVEMENTS ACTIVE
~ FULL STROKE TESTING OF REACTOR DEPRESSURIZATION-CANCELLED B-083 VALVE SCRAM DUMP TANK VALVE - LACK OF REDUNDANCY (STUDY)
COMPLETE
'B-084.
SCRAM DUMP TANK REDUNDANT VALVES COMPLETE B-084A
. CONTAINMENT OVERPRESSURE - NITROGEN SUPPLY-TO RDS COMPLETE B-085.
ISOLATION VALVES
. BYPASS OF MOV THERMAL OVERLOADS COMPLETE B-086 PIPE BREAK OUTSIDE OF CONTAINMENT COMPLETE B-087 MSLB OUTSIDE CONTAINMENT - RADIOLOGICAL CONSEQUENCES COMPLETE
~ B-088 RCPB LEAKAGE DETECTION COMPLETE ~
B-089 BN-090 CLASSIFICATION OF STRUCTURES, SYSTEMS AND COMPONENTS COMPLETE CONTAINMENT ISOLATION - POST LOCA SYSTEM WALKDOWNS COMPLETE.
B-091 CONTAINMENT IS0 aTION - CLOSED SYSTEMS COMPLETE B-092 EMERGENCY RESPONSE 1ACILITIES (UPGRADE TSC)
COMPLETE B-093 B-094A POST TRIP REVIEW - DATA & INFORMATION CAPABILITIES COMPLETE POST TRIP REVIEW - DATA & INFORMATION CAPABILITIES COMPLETE
.B-094B
-INSTALLATION OF FILTERS IN INSTRUMENT AIR LINE COMPLETE
-B-095 INSTALLATION OF ISOL VALVE UPSTREAM OF CV-4027 COMPLETE
-B-096 B-097 REPLACEMENT OF VIP-5 WITH MOTOR OPERATED VALVE COMPLETE REVISIONS'TO 125-VOLT DC DRAWINGS COMPLETE B-098 EQUIPMENT CLASSIFICATION - RPS COMPONENTS COMPLETE B-099 BN-100 VENDOR INTERFACE AND MANUALS COMPLETE POST MAINTENANCE TESTING - RPS COMPONENTS COMPLETE B-101 MIO287-0084A-BX01-hLO4
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ISSUE
-ISSUE
~
' NUMBER RANK' ISSUE DESCRIPTION STATUS EQUIPMENT CLASSIFICATION - ALL SAFETY RELATED COMPLETE B-102 L-
-; EQUIPMENT.
i B-103-
' POST MAINTENANCE TESTING - ALL SAFETY RELATED COMPLETE EQUIPMENT B-104 20-CORE SPRAY PUMP SUCTION STRAINER BLOCKAGE ACTIVE B-105 REACTOR DEPRESSURIZATION SYSTEM HANGER REPLACEMENT COMPLETE B-106
~23 REMOVE TURBINE GRATING' ACTIVE.
FLOOD ANNUNCIATION
' CANCELLED B-107 MAIN STEAM LINE DRAIN ISOLATION
' COMPLETE B-108 4
-BN-109 BACKUP HIGH RANGE STACK MONITOR COMPLETE b
-B-110-17 LIGHTNING PROTECTION ~
ACTIVE
~B-111~
9 REPLACEMENT OF NEUTRON MONITORING INSTRUMENTATION ACTIVE A-112 11 ALTERNATE ROD INJECTION
~ ACTIVE B-113 11 SELIEF VALVE-FAILURES INVESTIGATION ACTIVE B-114 17
- RECIRCULATION PUMP ROOM LIGHTING ACTIVE B-115-3
' CONDENSER MAKEUP WATER / CORE SPRAY INVESTIGATION ACTIVE B-116-9 CLEANUP DEMIN PIT ACCESS HANDRAIL ACTIVE 1
REPLACE DIESEL FIRE PUMP ENGINE COMPLETE B-117
-B-118 13 UNDER WATER FILTERING SYSTEM FOR SPENT FUEL POOL ACTIVE B-119 4
ACID SYSTEM MODIFICATIONS TO ELIMINATE PIPING ACTIVE I
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4 ATTACHMENT 2 Consumers Power Company-Big Rock Point Plant Docket 50-155
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BIG ROCK POINT INTEGRATED PLAN p
OPEN ISSUES February 27, 1987 I
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10 Pages MIO287-0084A-BX01-NLO4
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02/27/87 BIG ROCK POINT PLANT INTEGRATED PLAN.
TYPE ' A ' PROJECTS PLAN SCHEDULED ISSUE ISSUE NUMBER RANK TITLE COMPLETION DATE A -035B 22 FHSR UPDATE STUDY 639 12-31-88 SCOPE:
STATUS:
FINALIZE THE DESIGN AND IMPLEMENTATION INDEXING SYSTEM AND SCHEDULAR EXEMPTION OF A COMPUTERIZED DOCUMENT INDEXING SYSTEM SUBMITTED FOR NRC REVIEH ON 8/27/86.
IT AS k SUBSTITUTE FOR AN UPDATED FHSR, SUBMIT APPEARS THAT A SCOPE CHANGE MAY BE REQUIRED SCHEDULAR EXEMPTION AND RESOLVE NRC TO RESOLVE NRC COMMENTS. HILL NOT START CONCERNS. PROVIDE AN UPDATE TO THE BRP UNTIL AFTER 1987 REFUELING DUTAGE.
FINAL HAZARDS
SUMMARY
REPORT.
A -112 11 ALTERNATE ROD INJECTION 685 00-00-00 SCOPE:
STATUS:
PERFORM ADDITIONAL RISK BASED EVALUATIONS RISK AMAL COMPLETED & PRESENTED TO TRG. ANAL 10 DETERMINE THE EFFICACY OF ALTERNATE ROD SUBMITTED TO NRC 10/1/86 & FOLLOH-UP EXEMP-INJECTION (10CFR50.62).
TION REQUEST ON 12/29/86. CPC0 REQUESTED BRP BE EXEMPT FROM INSTALLING AN ALTERNATE ROD INJECTION SYSTEM OR MODIFIED VERSION.
MAITING ON NRC APPROVAL OF EXEMPTION.
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02/27/87 BIG ROCK POINT PLANT INTEGRAiED PLAN TYPE ' BN ' PROJECTS PLAN SCHEDULED i
ISSUE ISSUE COMPLETION NUMBER RANK TITLE DATE.
BN-005 I6 CONTROL ROOM DESIGN REVIEN 03-0I-87 530 SCOPE:
STATUS:
TOTAL PROJECT SCOPE IS TO REVIEH BRP CONTROL PAST 6 MOS. COMPLETED ALL CRDR TASK ACTIVI-ROOM BASED ON HUMAN FACTORS GUIDELINES PER TIES. SUBMITTED PART I
SUMMARY
REPORT 3/87.
HUREG-0700.
FOR NEXT 6 MOS. ACTIVITY IS TO REPORT INCLUDED EVERYTHING EXCEPT CORRECTIVE i
COMPLETE ASSIGNMENT OF CORRECTIVE ACTIONS TO ACTION FOR BALANCE OF HED'S.
THIS HAS PER REMAINING HED'S, SUBMIT HED'S TO PMC/TRG AND AGREEMENT IN 2/4/87 LETTER TO NRC.
j SUBMIT PART II
SUMMARY
TO NRC.
BN-006 SAF5TY PARAMETER DISPLAY SYSTEM 03-0I-87 634 SCOPE:
STATUS:
HRITE AND SUBMIT SPDS SAFETY ANALYSIS' SAFETY ANALYSIS PACKAGE HILL BE SUBMITTED PACKAGE FOR NRC REVIEH AND APPROVAL.
FOR NRC REVIEN AND APPROVAL BY MARCH I.
1987.
4 DECLARE SPDS OPERATIONAL.
SPDS OPERATIONAL DATE HILL BE DETERMINED
- AFTER IT IS DETERMINED IF ADDITIONAL HARDWARE MILL BE REQUIRED. REFERENCE ISSUE BN-0G5 i
BN-Ol*A I3 RESOLUTION OF SEISMIC ISSUES 88 REF OUT 699 SCOPE:
STATUS:
PERFORM 110DIFICATIONS TO UPGRADE "0.0G" HEAK SIX PROPOSED SEISMIC UPGRADE MODIFICATIONS LINK COMMITMENTS.
HERE RANKED BY THE TRG AT THE OCTOBER 8,I985 TRG MEETING. PROJECT SCOPE AND SCHEDULE HAVE BEEN INTIATED.
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i-02/27/87 BIG ROCK POINT PLANT INTEGRATED PLAN i
TYPE ' BN ' PROJECTS i
PLAN SCHEDULED ISSUE ISSUE CDNPLETION NUMBER RANK TITLE DATE-l BN-025 19 HIND AND TORNADO LOADING 00-00-00 638 SCOPE:
SEP TOPIC III-2 AND III-4A.
UPDATE ANALYSIS.
STATUS:
RISK ANALY. PERFORMED AND SUBMITTED 2/13/87.
I REFLECTING INTEGRATION HITH NEN QUALIFIED COMMITMENTS MADE TO INSTALL PORTABLE PUMPS
{
ALTERNATE SHUIDOHN PANEL BUILDING. PROCURE
& PROVIDE OPERATORS GUIDANCE ON HHEN TO MAN AND INSTALL PORTABLE PUMPS.
THE ASD BL DG. DUE TO HEATHER CONDITIONS.
SCHEDULE TO BE DEVELOPED FOR NEXT UPDATE.
I i
BN-052 7
EMERGENCY OPERATING PROCEDURES UPGRADE 88 REF OUT 531
' i SCOPE:
STATUS:
DRAFT E0P FLOH CHARTS. BEGIN OPERATOR TRAIN-PGP SUBMITTED ON 12/30/86 AND CURRENTLY 1
ING.
IMPLEMENT AND COMPLETE VALIDATION AND BEING REVIEHED BY PRC.
DRAFTING OF E0P'S-VERIFICATION PROGRAM. INCORPORATE NRC SCHEDULED To START IN MID-MARCH. COMPLETION COMMENTS. COMPLETE OPERATOR TRAINING.
OF PROJECT BY THE END OF THE 1988 REFUELING j
OUTAGE IS ANTICIPATED.
BN-050A2 5
CONTAINMENT ISO - ON-LINE TEST OF MSIV 12-31-86 1
495 4
l SCOPE:
STATUS:
PROVIDE ON-LINE TEST CAPABILITY FOR THE MAIN A PROCEDURE TO TEST THE MSIV HAS BEEN STEAM ISOLATION VALVE.
IMPLEMENTED. IN ADDITION, NUCLEAR SAFETY DEPARTMENT EVALUATING DESIR-ABILITY OF INSTALLING SECOND VALVE USING 1
PRA TECH. NDH INVESTIGATING CHANGES IN l
VALVES DONNSTREAM OF MSIV.
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02/27/87 BIG RDCK POINT PLANT INTEGRATED PLAN TYPE ' BN ' PROJECTS PLAN SCHEDULED ISSUE ISSUE COMPLETION NUMBER RANK TITLE DATE BN-051 24 DESIGN CODES, CRITERIA AND LOAD COMBINATIONS 00-00-00 640 SCOPE:
STATUS:
REVIEH HORK PERFORMED ON STRUCTURAL ELEMENTS.
REVISE ISSUE RESOLUTION TO BE PRESENTED TO REVIEH ORIGINAL PLANT STRUCTURAL DESIGN /
TRG FOR RANKING IN MARCH 1987.
ANALYSES TO IDENTIFY POTENTIAL STRUCTURES FOR MODIFICATION.
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02/27/87 BIG ROCK POINT PLANT INTEGRATED PLAN TYPE ' B ' PROJECTS PLAN SCHEDULED ISSUE ISSUE COMPLETION NUMBER RANK TITLE DATE B -Olla 2
RECOMMENDATIONS FOR TURBINE BYPASS SYSTEM 07-01-87 704 i
SCOPE:
STATUS:
CHECK INTEGRITY OF CONNECTION BETHEEN INTEGRITY OF CONNECTIDH BETHEEN HYDR CYL - AND HYDRAULIC CYLINDER AND MAIN VALVE STEM.
MAIN VALVE STEM VERFIIED AS TIGHT. HYDRAULIC l
PURGE AIR FROM HYDRAULIC PIPING AFTER SYSTEM TEST PROCEDURE IN PRELIMINARY DRAFT.
REPAIRS. DEVELOP TEST PROGRAM FOR HYDRAULIC TRANSDUCER CDUPLING TO VALVE STEM VERIFIED AS SYSTEM. CHECK TIGHTNESS OF TRANSDUCER COUPL--
TIGHT. SERVO-AMP GAIN HILL ONLY BE ADJUSTED ING TO VALVE STEM. ADJ. SERVD-AMP. GAIN.
AS A FINAL RESORT.
B -016 5
SECONDARY SYSTEM INSTABILITIES 557 00-00-00 SCOPE:
STATUS:
PERFORM ANALYSIS OF CONDENSER-HOTHELL/ FEED-ANALYSIS IS COMPLETE. RECOMMENDATIONS ARE HATER SYSTEM CHARACTERISTICS. PROVIDE NDH BEING EVALUATED.
RECOMMENDATIONS TO PREVENT LOSS.0F FEEDHATER UPON PLANT LOAD REJECTION.
l B -018 8
HIGH PRESSURE RECYCLE 636 88 REF OUT I
SCOPE:
STATUS:
i IMPLEMENTATION THROUGH UPGRADED EMERGENCY ConPLETE, PENDING FINAL IMPLEMENTATION OF OPERATING PROCEDURES.
E0P'S.
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1 02/27/87 i
BIG ROCK POINT PLANT INTEGRATED PLAN TYPE ' B ' PROJECTS PLAN' SCHEDULED 4
ISSUE ISSUE COMPLETION NUMBER RANK TITLE DATE I
B -036A 13 EEQ PROGRAM ENHANCEMENTS 07-01-88 713 SCOPE:
-STATUS:
REVIEH & REVISE THE ADMI
N. PROCEDURE
S TO SEVEN OF 51 EXISTING EEQ FILES REVISED.
PROVIDE ADDITIONAL EEQ PROGRAM CONTROL.
CURRENT EEQ EFFORTS ARE ON REFUELING REVISE EXISTING EEQ FILES TO PROVIDE MORE OUTAGE PROJECTS.
CONSISTENT FORMAT HITH NEN LOCA PROFILE AND COMPONENT SHEETS (COMPUTER FORM).
i i
i B -044 20 VERIFICATION OF BS&B VALVE DATA 12-31-87 l
422 SCOPE:
STATUS THIS IS AN ONGOING PROJECT. VALVE OPERATING DUE TO ALARA CONSIDERATIONS, THE REMAINING DATA IS NEEDED FOR 28 0F 56 VALVES.
DATA HILL BE COLLECTED HHEN VALVE MAINTENANCE 4
i IS REQUIRED.' VALVE DATA HAVE BEEN GATHERED FOR 28 VALVES. INSTRUMENT DATA SHEETS UPDATED. AS DATA IS GATHERED, SHEETS HILL BE-UPDATED. NO CHANGE IN COMPLETION DATE.
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B -082 1
RDS RELIABILITY IMPROVEMENTS i
489 87 REF OUT SCOPE:
STATUS:
1.
RESEARCH SYSTEM HISTORY.
INSTALLATION OF 4 NEH PILOT VALVES & VALVE 2.
DEVELOP LIST OF POSSIBLE SYSTEM
' TOPS IS IN PROGRESS AND HILL BE COMPLETED IN INPROVEMENTS.
87 REF OUT.
INVESTIGATION OF A METHOD TO 3.
PROGRAM PLAN FOR SYSTEM MODIFICATION.
ALLOW Ft88 8 STPOKE TESTING IN PLACE HILL BE j
4.
INITIATE AND IMPLEMENT FACILITY CHANGES.
COMPLZTED BY 7/31/87.
S.
INVESTIGATE FULL STROKE TEST METHODS.
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02/27/87 BIG ROCK POINT PLANT 4
INTEGRATED PLAN
. TYPE ' B ' PROJECTS i
PLAN-SCHEDULED ISSUE ISSUE
' COMPL ETION NUMBER RANK TITLE DATE i
I
~09-01-87' B -104 20 CORE SPRAY PUMP SUCTION STRAINER BLOCKAGE 521 SCOPE:
STATUS:
INVESTIGATE THE POSSIBILITY OF BACKFLUSHING PRELIMINARY INVESTIGATION IN PROGESS.
BACK-i THE SUCTION STRAINER SCREENS OR ADDING GROUND IHFORMATION IN CONJUNCTION HITH THE INSTRUMENTATION To DETERMINE PUMP BLDCKAGE.
VARIOUS ALTERNATIVES TO RESOLVE THIS ISSUE IS 1
BEING RESEARCHED.
I B -106 23 REMOVE TURBINE GRATING 88 REF OUT 573 4
SCOPE:
STATUS:
MODIFY GRATING INSIDE TURBINE DOOR TO ALLOW TRG HAS RE-RANKED PROJECT. NEH COMPLETION IT TO BE REMOVED TO ACCOMODATE PERSONNEL DATE CONSIDERING EXISTING HORKLOAD AND ACCESS.
PLANT PRIORITY HAS BEEN ESTABLISHED.
I i
i' B -110 17 LIGHTNING PROTECTION 06-30-87 582 PER ORM MODIFICATIONS RECOMMENDED IN MEMO PR MINARY DESIGN PACKAGE GENERATED.
LARK 02-84 (PARAGRAPHS 1,2 AND 3).
PACKAGE HAS BEEN PRC REVIEHED AND APPROVED.
l DETAIL DESIGN IS C0t1PLETE AND HAS BEEN.
SUBMITTED FOR TECHNICAL REVIEH.
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02/27/87 BIG ROCK POINT PLANT INTEGRATED PLAN TYPE ' B ' PROJECTS
-PLAN SCHEDULED ISSUE ISSUE COMPLETION NUMBER RANK TITLE DATE:
B -111 9
REPLACEMENT OF NEUTRON MONITORING SYSTEM 89 REF OUT 662 SCOPE:
STATUS:
FC-599 A & B.
REPLACEMENT OF NEUTRON FC-5998 INSTALLATION COMPLETE. PAPER CLOSE-MONITORING INSTRUMENTS (STARTUP, LOGN AND.
DUT IN PROGRESS. EQUIPMENT DELIVERY FOR POWER RANGE).
CH. 1 - 5 IN 1987; INSTALLATION 88 REF OUT.
EQUIPMENT FOR AREA AND PROCESS MONITORS POSTPONED.
B -113 11 RELIEF VALVE FAILURES INVESTIGATION 06-30-87 549 SCOPE:
STATUS:
' DETERMINE THE INCONSISTENT SET POINT MOST TESTING COMPLETE FOR THIS REFUELING.
MEASUREMENTS OF RV'S.
EVALUATION OF SYSTEM STEAM DRUM RELIEF VALVE PROBLEM IDENTIFIED.
SET POINTS, SET POINT TOLERANCES, TEST STAND OTHER VALVES BEING EVALUATED ON A CASE BY APPARATUS AND SET POINT PROCEDURES.
CASE BASIS.
B -114 17 RECIRC, PUMP ROOM LIGHTING 88 REF OUT 696 SCOPE:
STATUSs' INSTALL SEMI-PERMANENT LIGHTING UNDER THE MAINTENANCE ORDER HAS BEEN PERFORMED FOR IN-STEAM DRUM AREA.
SEPARATE ELECTRICAL CIRCUIT STALLATION OF SEMI-PERMANENT LIGHTING FOR NORMAL AHD EMERGENCY LIGHTING IN RCP DIRECTLY UNDERNEATH THE STEAf1 DRUM. SEPARA-ROOM / STEAM DRUM AREA.
TION OF ELECTRICAL CIRCUITS HILL BE PERFORMED DURING 88 REFUELING DUTAGE.
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02/27/87 BIG ROCK POINT PLANT INTEGRATED PLAN TYPE ' B ' PROJECTS 1
PLAN i
SCHEDULED 1
ISSUE ISSUE COMPLETION-NUf4 DER RANK TITLE DATE' L
B -115 3
CONDENSER MAKEUP H2O / CORE SPRAY INVEST.
12-31-87 515 4
SCOPE:
STATUS:
EVALUATE ALTERNATE MAKEUP HATER TO HOTHELL/
PROJECT HAS ASSIGNED. HORK TO BEGIN UPON CORE SPRAY AND PROVIDE RECDMMENDATIONS To TRG
. Cot 1PLETION OF OTHER PROJECTS CURRENTLY IN i
FOR POTENTIAL PLANT MODIFICATION.
PROGRESS.
1 B -116 9
CLEAN-UP DEMIN PIT ACCESS - HANDRAIL 88 REF OUT 697 SCOPE:
STATUS:
PROVIDE A SAFE MEANS OF ACCESSING THE BOTTOM M. O. FOR FABRICATION HAS BEEN ISSUED. DUE OF THE CLEAN-UP DEMIN PIT HHILE AVOIDING TO ALARA CONSIDERATIONS, PHYSICAL DIMENSIONS EQUIPMENT DAMAGE.
COULD NOT BE DBTAINED BEFORE 87 REF OUT TO GUARANTEE THAT PROPOSED DESIGN HAS SUITABLE.
PROJECT IS BEING RESCHEDULED DUE TO LACK OF CRAFTS PEOPLE FOR FABRICATION DURING 87REFOUT 1
i B -118 13 UNDERHATER FILTERING SYSTEM FOR SFP 12-31 705 i
SCOPE:
STATUS:
INSTALL UNDERHATER FILTERING SYSTEM (UHFS)
UHFS IS INSTALLED AND TESTED. PROBLEllS HITH FOR THE SPENT FUEL POOL.
UNDERNATER RADIATION PROBE ENCOUNTERED - NEW j
PROBE ON ORDER. OPERABLE FOR VACUUMING OF FUEL POOL HITH CONTINUOUS MONITORING USING AN R07.
MINOR CHANGES TO SETUP HAVE BEEN RE-QUESTED BUT DELAYED UNTIL AFTER REF. DUTAGE.
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02/27/87 BIG ROCK POINT PLANT INTEGRATED PLAN 1YPE ' 5 ' PROJECTS PLAN.
SCHEDULED-ISSUE ISSUE COMPLETION NUMBER RANK TITLE DATE B -119 4
ACID SYSTEM MOD. TO ELIMINATE PIPING EROSION 00-00-00 729 l
SCOPE:
STATUS:
IMPROVE / CORRECT ACID ADDITION SYSTEM TO PROJECT ASSIONMENT HAS BEEN REASSIGNED THIS ELIf1INATE PERSONNEL SAFETY CONCERNS AND PERIODS HILL REMAIN ON TEMPORARY HOLD PENDING IMPROVE SYSTEM REALIBILITY.
COMPLETION OF OTHER PRIORITY PROJECTS.
SCHEDULE TO BE DEVELOPED BY 6/1/87.
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