IR 05000346/1980019
| ML19347A790 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 08/11/1980 |
| From: | Reyes L, Warnick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19347A787 | List: |
| References | |
| 50-346-80-19, NUDOCS 8009300243 | |
| Download: ML19347A790 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT i
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REGION III
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Report No.
50-346/80-19 Docket No.
50-346 License No.
License No. NPF-3 I
Licensee: Toledo Edison Company Edison Plaza 300 Madison Avenue Toledo, Ohio 43652 Facility Name: Davis-Besse Nuclear Power Station, Unit 1 Inspection At: Davis-Besse Site, Port Clinton, Ohio Inspection Conducted: June 16-20, 23-27, 30, July 1-3, 7-11, 1980
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ly., I l l$D Inspector:
L. A. Reyes
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L Approved By:
R. F. Warnick, Chief
11 2TC)
Projects Section 2
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Inspection Summary Inspection on June 16-20, 23-27, 30, July 1-3, 7-11, 1980 (Report No. 50-346/80-19)
Areas Inspected: Routine unannounced inspection of followup on previous Inspection Findings, Containment Integrated Leak Rate Test, TI2515/36, Monthly Surveillance Observation, Monthly Maintenance Observation, IE Bulletin Followup, Onsite Review Committee, Inspection During long Term Shutdown, Licensee Event Reports Followup, and Meeting with the Public l
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8009300243
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and Local Officials. The inspection involved 84 inspector-hours during regular shift and 30 inspector-hours during offshifts by the Resident Inspector.
Results: Of the ten areas inspected, no items of noncompliance or devia-tions were identified in eight areas; three apparent items of noncompli-ance were identified in the other two areas (Deficiencies-failure to keep a log of events during CILRT-Paragraph 9, Deficiency-Failure to document
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inspection of fire extinguishers-Paragraph 10. Deficiency-Failure to properly log the position of locked valves-Paragraph 10).
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DETAILS
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1.
Persons Contacted
- T. Murray, Station Superintendent B. Beyer, Assistant Station Superintendent P. Carr, Maintenance Engineer
- S. Quennoz, Technical Engineer G. Wells, Administrative Coordinator
- D. Miller, Operations Engineer D. Briden, Chemist and Health Physicist J. Hickey, Training Supervisor L. Simon, Operations Supervisor
- G. Daft, Operations QA Manager
- D. Huffman, Administrative Coordinator
- E. Rober, Senior Assistant Engineer
- Denotes those present at the exit interview on June 30, 1980.
The inspectors also interviewed other licensee employees, including members of the technical, operations, maintenance, I&C training and health physics staff.
2.
Previous Inspection Findings (Closed) Unresolved Item (50-346/80-05-01)
The inspector reviewed procedure " Reactor Coolant Pump and Motor Emergency Procedure", EP1202.16, Pev. 4, and determined that appro-
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priate criteria have been included for stopping the RCPS and placing the unit in cold shutdown.
(Closed) Noncompliance (50-346/80-14, Paragraph 3.f)
Failure to establish a fire watch. The inspector reviewed memo M80-1287 which was distributed to all operations personnel. The memo emphasizes the priority of establishing a fire watch within the Technical Specification required time.
(Closed) Noncompliance (50-346/79-19, Paragraph 3.c)
Drawing and Procedure discrepancies. The inspector reviewed Drawing i
M-033, Rev. 35, and Procedure SP.1104.04.14 and verified that as l
built conditions for valve DH-100A were properly reflected. The
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inspector also reviewed Drawings E-547, Rev. 6, and E-49B, SH-25, Rev. 8, and verified that these drawings reflect the installation of relay TDR-2.
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(Closed) Noncompliance (50-346/79-19, Paragraph 5)
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Storage of flammable materials in switchgear room B.
The inspector verified during his plant tours that the control of flammable mat-erials in switchgear Room B was appropriate.
(Closed) Noncompliance (50-346/79-28, Paragraph 6.c)
Failure of the SRB to review vi,4ations to technical specifications.
The inspector verified that Tae Technical Engineer reviews the NRC Inspection Reports when received at the station and that a Deviation Report is written for violations of Technical Specifications. All Deviation Reports are reviewed by the SRB.
(Closed) Unresolved Item (50-346/79-22, Paragraph 10)
Containment Hydrogen Annalyzers. The licensee has initiated Faci-lity Change Request 79-373 to change the range and add zeroing capabilities to the Hydrogen annalyzers. Current schedule for
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installation is January, 1981 as per requirements of TMI Lessons Learned Items.
3.
Monthly Maintenance Observation Station maintenance activities of safety related systems and com-ponents listed below were observed / reviewed to ascertain that they wer-conducted in accordance with approved procedures, regulatory I
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c and industry codes or standards and in conformance with technical specifications.
The following items were considered during this review: the limit-ing conditions for operation were met while components or systems were removed from service; approvals were obtained prior to initia-
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ting the work; activities were accomplished using approved procedures and were inspected as applicable; functional testing and/or cali-brations were performed prior to returning ttaponents or systems to service; quality control records were maintained; activities were accomplished by qualified personnel; parts and materials used were properly certified; radiological controls were implemented; and, fire prevention controls were implemented.
Work requests were reviewed to determine status of outstanding jobs
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and to assure that priority is assigned to safety related equipment maintenance which may affect system performance.
The following maintenance activities were observed / reviewed:
Replacement of fuel assembly holddown springs.
Following completion of maintenance on the upper end fitting hold-down springs, the inspector verified that applicable systems had been returned to service properly.
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No items of noncompliance or deviations were identified.
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4.
Monthly Surveillance Observation The inspector observed technical specifications required surveil-lance testing on the Safety Features Actuation System and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specifications and procedure requirements and were re-viewed by personnel other than the individual directing the test,
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and that any deficiencies identified during the testing were proper-ly reviewed and resolved by appropriate management personnel.
The inspector also witnessed portions of the following test activ-ities: Communications between Control Room and Containment for core
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alterations.
During the review of the Safety Features Actuation Test it was determined that in the event of a loss of offsite power, followed by SFAS trips within 50 seconds, the output modules to be blocked by the sequencer would trip before the block signal from the sequencer would block the output module. This could cause the diesel gener-ator to be overloaded by the equipment starting early.
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The licensee reported this deficiency on July 9, 1980. Facility Change Request 80-181 has been initiated to correct this condition.
The sequencers have been declared inoperable and the unit will be limited to Mode 5 as required by Technical Specification. This item will remain unresolved unti1 the modification and satisfactory j
testing of the Emergency Diesel Generators Sequencers have been
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completed. (50-346/80-19-01)
No items of noncompliance or deviations were identified.
5.
Licensee Event Reports Followup Through direct observations, discussions with licensee personnel, and review of records, the following event reports were reviewed to determine that reportability requirements were fulfilled, immediate corrective action was accomplished, and corrective action to pre-vent recurrence had been accomplished in accordance with technical specifications.
LER's 79-88.79-123, 79-124,79-126, 80-03, 80-04, 80-06, 80-01, 80-23, 80-29, 80-43, 80-44, 80-45.
No items of noncompliance or deviations were identified.
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6.
IE Bulletin Followup
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For the IE Bulletins listed below the inspector verified that the written response was within the time period stated in the Sulletin, 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, that licensee management forwarded copies of the written response to the appropriate onsite management representatives, that information discussed in the licensee's writ-ten response was accurate, and that corrective action taken by the licensee was as described in the written response.
IE Bulletin 80-04, " Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition." The licensee's analysis indicated no enemitments to item 3 of the B'tlletin were required. The licensee
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analysis will be forwarded to NRR for further review.
IE Bulletin 80-12 " Decay Heat Removal System Operability."
No items of noncompliance or deviation were identified.
7.
IE Circular Followup
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For the IE Circulars listed below, the inspector verified that the Circular was received by the licensee management, that a review for applicability was performed, and that if the circular were applic-able to the facility, appropriate corrective actions were taken or were scheduled to be taken.-
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IE Circular 79-17 " Contact Problem in SB-12 Switches on General Electric Company metal clad Circuit Breakers."
No items of noncompliance or deviations were identified.
8.
Onsite Review Committee The inspector examined the onrite review functions conducted during the period January 2 through June 6, 1980 to verify conformance with technical specifications and other regulatory requirements. This review included:
changes since the previous inspection in the charter and/or administrative procedure governing review group activities; review group membership and qualifications; review group meeting frequency and quorum; and, activities reviewed including proposed technical specification changes, noncompliance items and corrective action, proposed facility and procedure changes and proposed tests and experiments conducted per 10 CFR 50.59, and others required by technical specifications.
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The inspector attended the onsite review committee meeting held ca July 10, 1980.
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No items of noncompliance or deviations were identified.
i 9.
Containment Integrated Leak Rate Test a.
Procedure Review The inspector reviewed procedure ST5061.01, " Containment Inte-grated Leak Rate Test," and verified that the procedure was technically adequate and consistent with regulatory require-ments.
b.
Instrumentation
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The inspector reviewed the calibration data associated with performing the CILRT. A multipoint calibration of all instru-mentation was performed. Correction values were generated based on the difference between measurements of resistance from a NBS verified resistance box and actual resistance measured.
All corrections were placed as an array or equation into the CILRT computer.
The following instrumentation was used in the CILRT:
Tyge Quantity Serial Number RTDs
86518-86520
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30401-30403
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30973 Flowmeter
8004H 07760
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Pressure Gauge
667-1,2 Dewcells
626, 632, 545A, 593, 592 The calibration certificate for one of the dewcells was not available at this time. The licensee was expecting the cali-bration certificate from the vendor who had indicated that the calibration was performed and the certificate was being mailed to the licensee. This item is unresolved until the inspector reviews the calibration certificate of the dewcell. (50-346/-
80-19-02)
c.
Witness of Test The inspector witnessed portions of the preparations and pump-6-w
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up for the CILRT on June 9, 7^
1980 and verified that:
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Appropriate revision of procedure was in use by test personnel.
Test prerequisites were met.
Proper plant systems were in service.
d.
Direct Observation of Valve Lin.up; The inspector verified by direct visual observations that valve lineups were completed in accordance with the test procedure.
The inspector determined that valves DH-11 and DH-12 on pene-tration 29 cannot be tested as per the requirements of 10 CFR 50, Appendix J, Sections III.A.I.d and III.c.
This item is
unresolved pending the submittal by the licensee of a request for an exemption for testing valves DH-11 and DH-12 as required by Appendix J. (50-346/80-19-03)
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Blowdown and Containment Inspection The inspector verified that blowdown was within Technical Specification radioactivity release limits. The inspector also conducted an independent post CILRT containment inspection for equipment degradation after blowdown and did not identify any degradation.
f.
CILRT Valve Lineup Penalties Valve configurations noted below deviated from the normal CILRT
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valve lineup. As a result, the local leak rate test results will be added as a penalty to Las at the 95% confidence level.
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Makeup-System 2.
Containment Pressurization System 3.
Fuel transfer tubas The local leah rate test for the above listed systems has not been conf eted.t this time. This item is unresolved l
pealing completion of the local leak rate test by the licensee and review of the test results by the inspector.
(50-346/80-19-04)
g.
CILRT Data Evaluation The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> CILRT was started on June 12, 1980, at 0145. The-7-
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inspector independently monitored and evaluated leak rate data to verify the licensee's calculations of the leak rate. There was acceptable agreement between the inspector's and licensee's,
leak rate calculations as indicated in the following summary
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(units are in weight percent per day):
Measurement Licensee Inspector Leakage rate measured (Lam)
0.065 0.0648 during CILRT Lam at 95% confidence level 0.071 0.0714 Appendix J Acceptance Criterion at 95% confidence level = 0.75 La =
0.75 (0.5) =0.375.
As indicated above, Lam at the 95% confidence level was less than the maximum allowable by 10 CFR Part 50, Appen-dix J.
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h.
Supplemental Test Data Evaluation After the satisfactory completion of the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> test on June 12, 1980, a known leakage of 0.378 weight percent / day was induced. The inspector independently monitored and evaluated leak rate data to verify the licensee's calculation of the supplemental leak rate. There was acceptable agreement between -
the inspector's and licensee's leak rate calculations as indi-cated in the following summary (units are in weight percent per day):
j Measurement
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Measured leakage (Lc)
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rate during supplemental test 0.394 0.3945 Lc @ 95% confidence level 0.4290 Induced leakage rate (Lo) = 0.378 Appendix J. Acceptance Criterion: 0.3178 4 Le < 0.5678 As indicated above, the supplemental test results satisfied the requirements of 10 CFR Part 50, Appendix J.
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Iog of Events After the completion of the CILRT and verification test the inspector noticed that the log of events was not kept through the completion of the test. The CILRT procedure, ST5061.01, as-8-l
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well as ANSI N45.4-1972 require that a dated log of events and pertinent observations be made during the test. This is an ites
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of noncompliance.
Subsequent to the inspector findings the licensee implemented corrective action by making r-ntries into the log using infor-nation from the computer pr!.ntouts and from the personnel running the test. The inspector has no further questions on the
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log of events at this time.
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Drawings During the verification of valves line-up versus as built drawings the inspector determined that drawing M-023 Indicated Valve CV-125 at Pennetration 33. This valve should be shown in the drawing as valve CV-127 and is shown correctly on other perti-nent drawings. This item is unresolved pending the revision of the drawing by the licensee and the review of the revised
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drawing by the inspector.
(50-346/80-19-05)
No other items of noncompliance or deviations were identified.
10.
Inspection During Long Tr.rm Shutdown The inspector observed control room operations, reviewed applicable logs and conducted discussions with control room operators during the period of May 16 through June 11.
The inspecter verified sur-veillance tests required during the shutdown were accomplished, reviewed tagout records, and verified applicability of containment integrety. Tours of containment, auxiliary, and turbine building acces-sible areas, including exterior areas were made to make independent assessments of equipment conditions, plant conditions, radiological
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controls, safety, and adherence to regulatory requirements and to verify that maintenance requests had been initiated for equipment in need of maintenance. The inspector observed plant housekeeping / clean-liness conditions, including potential fire hazards, and verified implementation of radiation protection controls. The inspector by observation and direct interview verified that the physical security plan was being implemented in accordance with the station security plan. The inspector reviewed the licensee's jumper / bypass controls to verify there were no conflicts with technical specifications and verified the implementation of radioactive waste system controls.
The inspector witnessed portions of the radioactive waste systems controls associated with radwaste shipments and barreling.
During the plant tours on June 20 and 27, 1980, the inspector noticed that several fire extinguishers did not have the inspection tags signed for the month of June or had their tags missing. This is contrary to procedure ST 5016.04 which requires the inspector of fire-9-
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extinguishers to sign the inspection tag during the monthly inspection. This is an item of noncompliance.
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On June 17, 1980 at approximately 7:00 a.m. the inspector determined that valves AF 599 and AF 608 were in the open position and the lock valve log indicated they were closed. This is contrary to procedure AD 1839.02 which requires that when locked valves are repositioned the appropriate log entries are completed in the locked valve log.
This is an item of noncompliance.
No other items of noncompliance or deviations were identified.
11.
TI2515/36 Verification of License Application Submittals for Licensee Training Staff Personnel The inspector identified the training instructors involved in train-ing on systems, integrated plant response, transients, and simulators courses at Davis-Besse and determined that those persons are holders of SRO licenses.
No items of noncompliance or deviations were identified.
12.
Meeting with the Public and Local Officials At a request of an Ottawa County Commissioner the Resident Inspector attended a meeting on July 2, 19E*, to discuss liquid discharges from the Davis-Besse facility. The meeting was attended by local citizens concerned about liquid discharges following a newspaper article on the loss of instrument power event that occurred on April 19, 1980. The inspector answered questions related to plant opera-tions and liquid discharges from the Davis-Besse Facility and pro-
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vided his office telephone number and the Region III telephone number for future contact.
13.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. The unresolved items disclosed during the inspection are discussed in paragraphs 4 and 9.
14.
Exit Interview
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The inspector met with licensee representatives (denoted in Para-graph 1) on June 16 and July 11, 1980 and summarized the scope and findings of the inspection activities.
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