IR 05000266/1981005
| ML19347F773 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/16/1981 |
| From: | Guldemond W, Hague R, Konklin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19347F765 | List: |
| References | |
| TASK-1.A.1.1, TASK-1.A.1.2, TASK-1.A.1.3, TASK-1.A.2.1, TASK-1.C.1, TASK-1.C.2, TASK-1.C.3, TASK-1.C.4, TASK-1.C.5, TASK-1.C.6, TASK-2.B.4, TASK-2.E.4.2, TASK-2.F.2, TASK-3.D.1.1, TASK-TM 50-266-81-05, 50-266-81-5, 50-301-81-04, 50-301-81-4, TAC-44188, TAC-44189, TAC-44538, TAC-44539, NUDOCS 8105260274 | |
| Download: ML19347F773 (12) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-266/81-05; 50-301/81-04 Docket No. 50-266; 50-301 License No. DRP-24; DPR-27 Licensee: Wisconsin Electric Power Company 231 West Michigan Milwaukee, WI 53203 Facility Name:
Point Beach Nuclear Power Plant, Units 1 & 2 Inspection At:
Point Beach Site, Two Creeks, WI Inspection Conducted: March 2-31, 1981
. b Sn>u& n Inspectors.
W. G. Guldemond 1-/4-8/
-b SW /n7 R. L. Hague 4- /4 - F/
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Approved By:
J.
Konklin, Acting"TIiief
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P jects Section 2A
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Inspection Summary Inspection on March 2-6, 9-13, 16-20, 23-27, 30-31, 1981 (Report No.
50-266/81-05; 50-301/81-04)
Areas Inspected: Routine resident inspection of Operational Safety Veri-fication, Monthly Maintenance Observation, Monthly Surveillance Observation, Followup on Licensee Event Reports, IE Bulletin and Circular Followup, Review of Plant Observations, Design, Design Changes, and Modifications, Review of Periodic and Special Reports, Independent Inspection Effort, TMI Action Plan Items, Followup on Regional Requests. The. inspection involved a total of 200 inspector-hours onsite by two inspectors including 46 in-spector-hours on off-shifts.
Results: No items of noncompliance were identified.
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s DETAILS-
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1.
Persons Contacted
- G.-A. Reed, Manager, Nuclear Power Division J. J..Zach, Superintendent Technical Services
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'T. J. Koehler, Operations Superintendent J. C. Reisenbuechler, I&C Engineer-
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W. J. Herrman, Maintenance Superintendent
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R. S. Bredvad, Health Physicist
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- R. E. Link, Assistant to the Manager
- F. A. Zeman, Office Supervisor
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The inspectors also talked with and interviewed members of the Operations,.
Maintenance, Health Physics, and. Instrument-and-Control Sections.
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- Denotes personnel. attending exit interviews.
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2.
Operational' Safety Verification f
The inspector observed control room operations, reviewed applicable logs i
and conducted discussions with control room operators during.the month of March. The. inspector verified the operability of celected-emergency j.
systems, reviewed tagout records and verified proper return to service
of affected components. Tours of both auxiliary buildings and turbine buildings were conducted to observe plant equipment' conditions, including potential fire hazards, fluid leaks, and excessive vibrations and to
i verify that maintenance requests had been' initiated for equipment'in'need i
of maintenance. The inspictor by observation and direct interview verified
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that the physical security plan was being implemented-in accordance with i
the station security plan.
The inspector observed plant housekeeping / cleanliness conditions and verified implementation of radiation protection controls. During the
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month of March, the inspector walked down the accessible portions of-L the safety injection, auxiliary feed, emergency diesel generating systems l
and containment spray systems to verify operability. The inspector
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also witnessed portions of the radioactive waste system controls asso-
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ciated with radwaste shipments and barreling. This included a con-
firmatory radiation measurement of a radwaste shipment and attendance at the briefing of the truck driver.
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These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established under l
technical specifications, 10 CFR, and administrative procedures.
No items of noncompliance or deviations were identified.
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3.
Monthly Maintenance Observation Station maintenance activities of safety related systems and components listed below were observed / reviewed to ascertain that they were conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with technical specifications.
The following items were considered during this review:
the limitirg conditions for operation were met while components or systems were re-moved from service; approvals were obtained prior to initiating the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or calibrations were performed prior to returning components or systems to service; quality control records were maintained; activities were accomplished by qualifie.1 personnel; parts and materials used were properly certified; radiological controls were imple-ment.ed; and, fire prevention controls were implemented.
Work requests were reviewed to determine status of outstanding jobs and to assure that priority is assigned to safety related equipment mainten-ance which may affect system performance.
The following maintenance activities were observed / reviewed:
Replacement of R-Id Radiation Detector Following completion of maintenance on the 4D diesel generator (relay replacement), the inspector verified that these systems had been returned to service properly.
No items of noncompliance or deviations were identified.
4.
Monthly Surveillance Observation The inspector observed technical specifications required surveillance testing on the REI 6.0; Quarterly Flux Mapping for Unit 1 and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for opera-tion were met, that removal and restoration of the affected components i
were accomplished, that test results conformed with technical specifica-tions and procedure requirements and were reviewed by personnel other
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than the individual directing the test, and that any deficiencies identi-fied during the testing were properly reviewed and resolved by appropriate manag2 ment personnel.
The inspector also witnessed portions of the following test activ-ities:
PTS 2 Redundant Systems Test on 4D diesel generator No items of noncompliance or deviations were identified.
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5.
Licensee' Event Reports Followup All. Licensee Event Reports received to date have been closed out in
- previous inspection reports.
6.
'IE Bulletin Followug For the Ib Bulletin listed below the inspector verified that the written response was within the time period stated in the bulletin, that.the written. response included the information required to be reported, that the written response included adequate corrective action commitments-based on information presentation in the bulletin and the. licensee's response,-
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that licensee management forwarded copies of the written response to the
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-appropriate onsi';e management _ representatives, that information discussed
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in the licensee's written response was accurate, and that corrective action taken by the licensee was as described in the written response.
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l 80-06 Engineered Safety Feature Reset Controls No items of noncompliance or deviations were identified.
7.
IE Circular Followup I
All outstanding circulars were reviewed.
It was determined that none could be closed oct during the reporting period.
8.
Review of Plant Operations a
During the month of March the inspector reviewed the following activities:
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Training i
The inspector. attended one of the licensee's operator qualification
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Jectures on emergency planning and verified that lesson plan-objec-tives were met.
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Security l
The inspector observed that three individuals achieved acceptable -
scores during the conduct of weapons and physical fitness tests.
c.
Licensee Action Concerning Identified Problems l
The inspector reviewed corrective actions taken by the licensee pertaining to recurring failures and resolution of identified discrepancies involving safety-rel.ated components.
No items of noncompliance or deviations were identified.
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9.
Plant Trips Following the Unit I trip on March 31, 1981 at 0051 the inspector
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. ascertained the status of the reactor and safety systems by observa-tion of control room indicators and discussions with licensee personnel concerning plant parameters, emergency system status and reactor coolant-chemistry. The inspector verified the establishment of proper communica-tions and reviewed thc corrective actions taken by the licensee.
All systems responded as expected, and the plant was returned to operation on March 31, 1981 at 0940.
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No items of noncompliance or deviations were identified.
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Design, Design Changes, and Modifications The inspectors reviewed selected modifications not requiring approval by the Office of Nuclear Reactor Regulation to verify that the changes were reviewed and approved in accordance with 10 CFR 50.59. Also verified
.I were that the design changes were reviewed and approved in accordance'
with Technical Specifications and established QC/QA procedures, that the-l changes were controlled by established procedures, that tests of the
changes were conducted and the results reviewed, and that drawings and procedures. were changed as appropriate.
The following modifications were reviewed:
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Reset. Circuitry Modification Safeguards
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Fire Protection - Install Hose Reels Inside Containment.
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For the Reset Circuitry Modification, changes to maintenance procedures, l
drawings, and logs had not been documented in the modification package.
This was pointed out to the licensee who took immediate action to have the required documentation made.
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I No items of noncompliance or deviations were identified.
11.
Review of Periodic end Special Reports
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The inspectors reviewed the licensee's " Annual Results and Data Report l
1980".'
The review was conducted to ascertain whether the information
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reported by the licensee was technically adequate and satisfied the applicable reporting requirements established in 10 CFR, the facility
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license, and Technical Specifications.
Included <n the report were highlights of operation of both Unit 1 and Unit for 1980, facility
changes, tests and experiments, number of person 1el and man-rem exposure by work and job function, and steam generator tube inservice inspection results.
l No items of noncompliance or deviations were identified.
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Independent Inspection Effort-
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During the course of the inspection period the inspectors reviewed
licensee activities in the fe' lowing areas to ascertain that they were
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conducted in accordance with regulatory requirements and the Technical
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Specifications:
changes to procedures, qualification of Duty and Call
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Technical Advisors and radiological surveys.
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The inspectors reviewed all procedure changes, both' temporary and
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permanent, for the period January.1,1980 to. February.1,.1981 to verify that proper approvals and reviews had been-applied to the _.
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changes and that proper documentation of the changes had been retained.
i A sampling of temporary changes to major procedures were reviewed
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to determine technical adequacy and justification of the changes.
Based on these reviews; it was determined that the licensee's program-
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for controlling procedure changes is satisfactory.
In two-instances temporary changes to major procedures were not reviewed by the Manager's Supervisory Staff within the required two weeks. These instances care
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discovered by the licensee and instructions were promulgated to all station personnel involved in procedure changes reminding them of the
required timeliness for approval-of procedural changes. To further control procedure changes the licensee has instituted the use of a new
procedure change form which documents the required reviews and safety l
evaluations.
A review of the licensce's Duty and Call Technical Advisor training program and records indicates, as stated in their February 26, 1981 letter from C. W. Fay to H. R. Denton, that all assigned personnel
have completed the training program as described in the letter with.
the exception of a 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> course on mitigating core damage. Some material on this subject has been incorporated in their training.
However, a more extensive 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> course is being arranged to be taught onsite by Westinehouse. The exact date of completion is dependent on t
scheduling this course.
During a routine tour of the ccntrolled side of the facility, the
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i inspector noted through independent surveys of indicated " hot spots"
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that most readings'obtained were significantly less than the posted dose rates. While overposting is not a significant problem, the inspector did question the method of establishing " hot spots" and if any program was in effect to periodically re-evaluate them.
Some of the postings which indicated up to ten times the measured dose rate were nearly a year old.
In discussions with the Health Physicist, it was determined that no routine program for re-evaluation of " hot spots" exists. However, the licensee did commit to inclusion of " hot spot" surveys as part of the weekly routine survey. Administrative forms have been prepared to this end.
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13.
TMI Action Plan Inspection Requirements The inspectors reviewed liccesee actions in accordance with Revision 1 of Temporary Instructions 2515/42, 43, and 44. The attached tables present the current status of implementation of TMI Action Plan require-ments called for by the referenced temporary instructions.
No items of noncompliance or deviations were identified.
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14. Followup on Regional Requests On March 23, 1981, the inspectors received a memorandum from Region III requesting data to support completion of Manual Chapter 61727B on RCS leakage. This information was forwarded to Region III by memorandum dated March 23, 1981.
On March 23, 1981, the inspectors received a request from Region III to update the computer tracking system for all TMI~ Action Plan items.
This information was forwarded to Region III on March 24, 1981.
No items of noncompliance or deviations were identified.
15.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) throughout the month and at the conclusion of the inspection period and summarized the scope and findings of the-inspection activities.
The licensee acknowledged these findings.
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TMI ACTION PLAN STATUS
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PROCEDURES AND STAFFING
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TASK SUBJECT STATUS I.A.1.1 STA INTERIM STAFFING COMPLETE.
STA's RAVE BEEN ON DUTY SINCE 1/1/80 IN ACCORDANCE WITH A S. BURSTEIN (WE) TO H. R. DENTON (NRC) LETTER DATED 12/31/79.
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I.A.I.1 STA TRAINED PER LL CAT "B" ALL TRAINING EXCEPT THAT REQUIRED FOR MITIGATING CORE DAMAGE WAS COMPLETE AS OF 3/1/81. THE LICENSEE IS STILL ATTEMPTING TO ESTABLISH A TRAINING PROGRAM FOR MITIGATING CORE DAMAGE. PER A 12/23/80 LETTER FROM C. W. FAY (WE) TO H. R. DENTON (NRC) THIS REQUIREMENT WILL BE SATISFIED NO LATER THAN 10/1/81.
I.A.1.2 SHIFT SUPERVISOR RESPONSIBILITIES COMPLETE I.A.1.3 SHIFT MANNING COMPLETE. THE PROCEDURES ARE CONTAINED IN THE POINT BEACH NUCLEAR PLANT ADMINISTRATIVE POLICIES AND PROCEDURES MANUAL SECTION 4.3.3 DATED 1/5/81
'.A.2.1 MODIFY TRAINING COMPLETE. THE TRAINING PROGRAM WAS SUBMITTED IN A 8/7/80 LETTER FROM C. W. FAY (WE) TO H. R. DENTON (NRC).
I.C.1 SHORT TERM ACCIDENT AND COMPLETE PROCEDURE REVIEW (ITEM 1)
I.C.1 SHORT TERM ACCIDENT AND PROCEDURE REVIEW (ITEMS 2b C 3b)
TPESE ITEMS ARE PENDING REVIEW OF;THE WESTINGHOUSE OWNERS GROUP SUBMITTAL TO THE NRC.
I.C.2 SHIFT RELIEF / TURNOVER COMPLETE
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I.C.3 SHIFT SUPERVISOR RESPONSIBILITIES COMPLETE I.C.4 CONTROL ROOM ACCESS COMPLETE I~.C.5 PROCEDURE FOR OPERATING COMPLETE. THE PROCEDURES ARE CONTAINED IN THE POINT BEACH NUCLEAR PLANT EXPERIENCE FEEDBACK ADMINISTRATIVE POLICIES AND PROCEDURES MANUAL SECTION 3.15.7 DATED 12/19/80 I.C.6 VERIFICATION OF OPERATING COMPLETE.THE PROCEDURES ARE CONTAINED IN THE POINT BEACH NUCLEAR PLANT ACTIVITIES ADMINISTRATIVE POLICIES AND PROCEDURES MANUAL SECTION 4.14 DATED 6/20/80
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TMI ACTION PLAN STATUS
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IIARD'dARE
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TASK SUBJECT STATUS II.B.1 RCS VENTS PER NUREG 0737 THIS ITEM IS COMPLETE THROUGli THE DESIGN PHASE
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II.B.2 PLANT SilIELDING Tile DESIGN REVIEWS HAVE BEEN COMPLETED USING THE SOURCE TERMS PROVIDED IN NUREG 0578. Il0 WEVER, NUREG 0737 CHANGED Ti!E SOURCE TERM ASSUMPTIONS j
AND T!!E LICENSEE IS EVALUATING THE IMPACT ON Tile PREVIOUS REVIEWS. PER A 12/23/80 LETTER FROM C. W. FAY (WE) TO 11 R. DENTON (NRC) THE LICENSEE IIAS COMMITTED TO COMPLETE PLANT MODIFICATIONS BY 6/1/82 SUBJECT TO EQUIPMENT AVAILABILITY.
II.D.3
&! RECT INDICATION OF RELIEF AND COMPLETE. TECilNICAL SPECIFICATIONS WERE SUBMITTED IN FEBRUARY, 1981.
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, y; II.E.1.2 AUXILARY FEEDWATER SYSTEM COMPLETE. ORIGINAL PL ANT DESIGN.
AUTOMATIC INITIATION (ITEM la)
II.E.1.2 AUXILARY FEEDWATER SYSTEM COMPLETE. ORIGINAL PLANT DESIGN AUTOMATIC INITIATION (ITEM lb)
II.E.1.2 AUXI LARY' FEEDWATER SYSTEM Tile PRESENT SYSTEM CONSISTS OF A COMEINATION OF STEAM CENERATOR LEVEL FLOW INDICATION INDICATION AND AUXILARY FEED PUMP DISCHARGE ELOW INDICATION. TIIE PUMP DISCIIARGE FLOW INDICATION IS BEING UPGRADED TO SAFETY GRADE. THE SYSTEM IS PRESENTLY BEING MODIFIED TO INCLUDE SAFETY GRADE INDICATION OF FLOW TO EACll STEAM GENERATOR. TilESE MODIFICATIONS ARE TO BE COMPLETE BY 7/1/81 PER A 12/23/80 LETTER FROM C. M. FAY (WE) TO 11. R. DENTON (NRC}. TECIINICAL SPECIFICATIONS COVERING TIIE PRESENTLY INSTALLED SYSTEM WERE SUBMITTED IN FEBRUARY, 1981.
II.E.3.1 EMERGENCY POWER FOR PRESSURIZER COMPLETE. TECilNICAL SPECII'ICATIONS WERE SUBMITTED ON 2/4/81.
IIEATERS II.E.4.1 DEDICATED llYDROGEN PENETRATIONS COMPLETE. ORIGINAL PLANT DESIGN.
II.E.4.2 CONTAINMENT ISOLATION COMPLETE PER NUREG 0737. Tile LICENSEE IS ADDING CONTAINMENT ISOLATION DEPENDABILITY VALVES ON Tile SEAL WATER RETURN AND AUXILARY CilARGING LINES. Tile LICENSEE IIAS TAKEN EXCEPTION TO Tile GUIDELINES ON Tile CONTAINMENT PRESSURE SETPOINT. TiiEY CONTEND TilAT 1 PSI ABOVE Tile NORMAL OPERATING PRESSURE MAY BE INSUFFICIENT TO PRECLUDE INADVERTENT AND UNWANTED CONTAINMENT ISOLATIONS. Il0NEVER, TIIE LICENSEE, IN A 12/23/80 LETTER FROM C. W.
FAY (WE) TO II. R. DENTON (NRC) IIAS COMMITTED TO EVALUATE THE SITUATION.
NO DATE FOR COMPLETING Ti!IS EVALUATION WAS PROVIDE TMI ACTION PIAN STATUS
PROCEDURES AND STAFFING
TASK SUBJECT STATUS
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II.B.4 TRAINING FOR MITIGATING CORE THE LICENSEE IIAS YET TO FINALIZE PLANS FOR THIS TRAINING. TilIS IS DAMAGE EXPECTED TO IIAPPEN AFTER 4/1/81. PER A 12/23/80 LETTER FROM C. W. FAY (WE)
TO II. R. DENTON (NRC) TIIE TRAINING WILL BE COMPLETED BEFORE 10/1/81.
II.E.4.2 CONTAINMENT ISOLATION COMPLETE. Tile CONTAINMENT PURGE SUPPLY AND EX11AUST VALVES ARE DEPENDABILITY ADMINISTRATIVELY SilUT (BY RED TAGGING TIIE CONTROL SWITCllES) EXCEPT IINDER COLD SilUTDOWN CONDITIONS.
II.F.2 IDENTIFICATION OF AND RECOVERY COMPLETE
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FROM CONDITIONS LEADING TO INADEQUATE CORE COOLING
'II.K.3 BCO TASK FORCE ITEM 22 N/A BWR ONLY y
III.D.I.1 PRIMARY COOLANT OUTSIDE COMPLETE. Tl!E PROGRAM HAS BEEN IMPLEMENTED IN ACCORDANCE WITil A 3/14/80 CONTAINMENT LETTER FROM C. W. FAY (KE) TO H. R. DENTON (NRC). TIIE LICENSEE IS CURRENTLY CHANGING TO A YEARLY TESTING SCHEDULE BOC BOTil UNITS COINCIDENT WITI!
REFUELING OUTAGES.
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TMI ACTION PLAN STATUS
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liARDWARE e
TASK SUBJECT STATUE l
II.F.1 ADDITIONAL ACCIDENT MONITORING Tile LICENSEE !!AS COMMITTED TO A 1/1/82 COMPIETION DATE FOR ITEMS 4 S 5 INSTRUMENTATION (ITEMS 4, 5, E6)
CONTINGENT ON EQUIPMENT AVAILABILITY. TIIIS COMMITMENT WAS MADE IN A 12/23/80 LETTER FROM C. W. FAY (WE) TO !!. R. DENTON (NRC). TIIIS SAME LETTER STATES SINCE TilERE IS NO QUALIFIED IIYDROGEN DETECTION EQUIPMENT AVAILABLE, TilAT NO COMMITMENT CAN BE MADE TO i u 6.
II.G.1 POWER SUPPLIES FOR PRESSURIZER COMPLEin. TECllNICAL SPECIFICATIONS WERE SUBMITTED ON 2/4/81.
RELIEF VALVES, BLOCK VALVES AND LEVEL INDICATION (ITEM 1)
II.K.3 BCO TASK FORCE ITEM 9 COMPLETE.PER 6/11/80 LETTER FROM C. W. FAY (WE) TO II. R. DENTON (NRC).
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TMI ACTION PLAN STATUS
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HEALTil PilYSICS/ EMERGENCY PLANNING
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TASK SUBJECT STATUS II.B.3 POST-ACCIDENT SAMPLING (ITEM 1)
TIIE LICENSEE IIAS PROCURED Tile EQUIPMENT AND MADE IT OPERATIONAL FOR AN INTERIM SYSTEM. PROCEDURES FOR Tl!E REQUIRED SAMPLES ARE CONTAINED IN Tile POINT BEACll NUCLEAR PLANT llEALTil PilYSICS ADMINISTRATIVE CONTROL 3 POLICIES AND PROCEDURES MANUAL SECTIONS 17.6.1, 17.6.2, 17.6.3, 17.6.4, AND 17.6.5.
Tile LICENSEE RAS TAKEN EXCEPTION TO Tile REQUIREMENT FCR CitLORIDE ANALYSIS BASED ON T11EIR CONTENTION THAT TilERE IS NO CHLORIDE SOURCE FOR Tile RCS AND Tile DIFFICULTY OF Tile ANALYSIS.
II.F.1 INSTRUMENTATION FOR MONITORING Tile LICENSEE RAS ESTABLISilED INTERIM CAPABILITY. PROCEDURES FOR THE ACCIDENT CONDITIONS REQUIRED DETERMINATIONS ARE CONTAINED IN TIIE POINT BEACil NUCLEAR PLANT llEALTil PilYSICS ADMINISTRATIVE CONTROL POLICIES AND PROCEDURES MANUAL SECTIONS 17.6.4 and 17.6.5.
III.A.I.2 UPGRADE EMERGENCY SUPPORT COMPLETE. TiiE TEMPORARY TECilNICAL SUPPORT CENTER IS Tile CONFERENCE ROOM FACILITIES - SIIORT TERM; TECllNICAL IN TIIE ADMINISTRATIVE BUILDING. PLANT MONITORING INSTRUMENTATION WAS SUPPORT CENTER AND OPERATIONAL MADE OPERATIONAL IN EARLY MARCll,1981. CONSTRUCTION IS UNDERWAY ON THE SUPPORT CENTER NEW PERMANENT TECllNICAL SUPPORT CENTER. Tile ENERGY INFORMATION CENTER IS CURRENTLY DESIGNATED AS Tile OPERATIONAL SUPPORT CENTER.
kk.A.1.2 UPGRALE EMERGENCY SUPPORT-COMPLETE. AN INTERIM EOF HAS BEEN ESTABLISHED-IN THE ENERGY INFORMATION FACILITIES - S110RT TERM; EOF CENTER APPROXIMATELY 200 YARDS FROM-THE PLANT.
III.D.3.3 INPLANT RADIATION MONITORING COMPLETE. SATISFACTORY INTERIM P*'CEDURES ARE IN PLACE AND THE SUPPORTING (ITEM 1)
EQUIPMENT IS OPERATIONAL. ADDITIONAL UPGRADING IS IN PROGRESS. A RECIPROCAL AGREEMENT EXISTS WITli TIIE KEWAUNEE NUCLEAR POWER PLANT FOR USE OF LOW BACKGROUND LARCRATORY FACILITIES.
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III.D.3.3 INPLANT RADIATION MONITORING SEE III.D.3.3 ABOVE.
(ITEM 2)
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