IR 05000155/1980001
| ML19309A535 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 02/08/1980 |
| From: | Baker K, Ridgway K, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19309A527 | List: |
| References | |
| 50-155-80-01, 50-155-80-1, NUDOCS 8003310409 | |
| Download: ML19309A535 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-155/80-01 i
Docket No. 50-155 License No. DPR-6 Licensee: Consumers Power Company 212 West Michigan Avenue Jackson, MI 49201 Facility Name:
Big Rock Point Inspection At: Charlevoix, MI Inspection Conducted: January '-11, 1980 lU.$b.6,c;a Inspectors:
K. R. Ridgway #
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A n-w Approved By:
. R. Baker, Acting Chief, J
gg Reactor Projects, Section 3-2 Inspection Summary Inspection on January 8-11, 1980 (Report No. 50-155/80-01)
Areas Inspected: Routine unannounced inspection of the licensee's onsite Quality Assurance Program changes; Procedure System; and followup actions relative to Licensee Event Reports, IE Bulletins, IE Circulars, and open inspection items. The inspection involved 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> onsite by two NRC inspectors.
Results: No items of noncompliance were identified in the six areas (
inspected.
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DETAILS 1.
Persons Contacted
- C J. Hartman, Plant Superintendent
- D. E. DeMoor, Technical Engineer
- R. F. Schrader, Technical Superintendent
- J. A. Rang, Operations-Maintenance Superintendent
- A. C. Sevener, Operations Supervisor J. J. Popa, Maintenance Engineer R. G. May, Shift Supervisor F. J. Valade, Shift Supervisor
- T. C. Bordine, QA Superintendent C. R. Abel, Nuclear Safety Technical Engineer M. J. Malec, Senior Clerk, Document Control Center J. R. Fisher, QA Engineer R. W. Doan, Training Instructor E. McNamara, Training Instructor
- L. Oostermeyer, Senior Secretary The inspectors contacted several other licensee employees, including members of the technical, operations, and administrative groups.
- Denotes those attending the management exit interview on January 11, 1980.
2.
General The plant was restarted on November 6, 1979 following a nine month refueling and maintenance outage. The reactor was shutdown on the same day to repair a recirculation pump seal and two incore instru-ment flange leaks before restarting on November 9.
The plant ran continiously until December 31 when it was shutdown to implement several short term requirements of the TMI Lessons Learned Task Force (NUREG-0578).
During this inspection, the plant was being prepared for startup after completing the required modifications.
The plant was restarted on January 14, 1980.
3.
Procedures The inspectors reviewed procedures covering the startup and operation of the following six systems:
Nuclear Steam Supply System Shutdown Cooling System Reactor Cooling Water System
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O Turbine Generator System
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Service Water System Instrument Air System The inspectors verified that current, approved startup and operating procedures existed and that the procedures:
a.
met Technical Specification requirements and did not conflict with them.
b.
reflected changes to Technical Specifications implemented by License Amendments 26 through 31.
c.
conformed with, 10CFR50.59(a) review requirements and, 10CFR50.59(b), records of changes.
d.
were adequate for the safe control of systems.
The following procedures were reviewed:
GOP-4, Reactor Trip Recovery Rev. 6,1/9/80 GOP-5, Power Operation Rev. 2, 2/14/77 SOP-29, Nuclear Steam Supply System Rev. 10, 1/18/80
SOP-5, Shutdown Cooling System Rev. 6, 8/20/79 SOP-7, Reactor Cooling Water System Rev. 2, 1/20/78 SOP-13, Turbine Generator System Rev. 6, 3/22/79 SOP-20, Service Water System Rev. 1, no date
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i SOP-27, Service and Instrument Air System Rev. 3, 8/21/79 APL 1.2 N.S.S.S. Annunciator tabulation #1 Rev. 4, 1/9/80 i
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APL-1.3 N.S.S.S. Annunciator tabulation #2 Rev. 6, 1/9/80
APL 1.5 Turbine and. Generator System Annunciatcrs Rev. 7, 12/18/79 ONP 2.2 Loss of Instrument Air System Rev. 4, 7/13/78 ONP 2.30 Loss of Reactor Cooling Water System Rev. 3, 8/24/79 ONP 2.26 Loss of. Service Water Rev. 3, 8/24/79 l
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ONP 2.19 Loss of Feed-Water System Rev. 2, 10/13/77 a
ACP 1.4 Operations Department Administration Rev. 177, 1/9/80 Proc 16.18 Engineering Manual, Shift Technical Advisor, 12/29/79 No items of noncompliance were identified.
4.
Quality Assurance Program There have been no changes in the Consumers Power QA Program Policy (Volume I) since the last inspection.
Volume II, " Procedures for Design and Construction" has been completely revised and split into two volumes. Volume II is to be used for the Midland Project and all major modifications prior to 1980. Volume IIA of the same title covers all major modifications on which work begins on or after January 1, 1980 and the Palisades steam generator repair project.
The inspector did not review these revisions.
Several procedure changes have been made in Volume III of the QA Manual, " Procedures for Operations". These changes were reviewed to determine that they were in conformance with the Program Policy and 10 CFR 50, Appendix B and to verify that the changes were being implemented. Procedure changes review were:
QAPP 2-54 Rev. 2, Training for Operations QAPP 2-56 Rev. O, Fire Protection QAPP 2-57 Rev. O, Packaging and Shipping of Type A Quantities of RAM.
QAPP 3-51 Rev. 1, Design Control QAPP 4-51 Rev. 2, Procurement QAPP 7-51 Rev. 2, Supplier Evaluation and Selection QAPP 9-51 Rev. 1, Control of Special Processes I
QAPP 12-53 Rev. O, Control of HP, Laboratory and Test Equipment QAPP 12-52 Rev. O, Reporting Nonconformances QAPP 16-52 Rev. 3, Action Items QAPP 20-52 Rev. 1, Reporting to Governcent Agencies The following QA Department procedures fo Nuclear Operations were issued or revised during 1979 and reviewed during this inspection:
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QADP I-2 Rev. O, Responsible Areas for QA Operations Personnel
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QADP VI-3 Rev. O, Procedures and Document Control QADP XVI-1 Rev. ?, Corrective Action Followup and Trend Analysis QaDP XVII-1 Rev. 1, Collecting, Storage and Maintenance of Records QADP XVIII-1 Rev. 3, Audit Schedule QADP XVIII-2 Rev. 2, Conducting and Reporting Audits During a previous inspection, 1! it was noted that procedures QAPP 5-1 and QADP 5-51 did not address the Technical Specification Re-quirement (10-6.5.1.6 and 6.8) that the Plant Review Committee review all plant modifications, procedures, and procedure changes that affect safety systems or equipment.
Procedure QAPP 5-1, Department Procedures was revised and issued on January 1, 1980. The Technical Specification requirements were not addressed in this revision. Procedure QAPP 5-51, Development of Documents Controlling Quality-Related Activities During Operations, is being revised and will be issued in February 1980. The licensee advised the inspector that this revised procedure would refer to the Technical Specification requirement for Plant Safety Committee review.
This will continue to be held as Open Inspection Item (OII) No. 321.
No items of noncompliance were identified.
5.
Review of Licensee Event Reports (LER's)
The inspector reviewed the following LER's to determine if the reports were correct, properly evaluated, and the proposed cor-rective actions were appropriate and that they were completed as stated in the LER.
a.
(Closed) LER 50-155/79-22, a safety analysis made by the NSSS vendor following the TMI incident revealed that the reactor vessel and steam drum liquid level instruments, which initiate safety system trips, would not function under certain specific accident conditions. The instruments were modified under Spec-ification Field Change, SFC-79-036, " Removal of Temperature Compensation on Yarway Level Sensors." The modifications re-o quired changes in the Technical Specifications _for safety cir-cuit trip set points. This change was reviewed by NRR and approved in License Amendment No. 31 before the plant was re-1/. IE Report No. 050-155/78-11 i
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i started in November, 1979. During a previous inspection the inspector questioned the use of 250 F as the temperature limit of the reference leg during a LOCA. The licensee has initiated a review of the use of the 250 F basis. This is considered open inspection Item No. 362 and will be reviewed during a subsequent inspection.
b.
(Closed) LER 50-155/79-25, On October 30, 1979, during a plant shutdown, a transistor failure caused the normal 35V D.C.
power supply to the vacuum relief controls for the containment isola-tion valves to drop to 16 volts. The failure would have pre-vented the containment isolation supply valves from closing by automatic signal or manual operation. The defective power supply was replaced and containment integrity established in three hours. Administrative controls have been established to monitorthecontainmentpressureindicatorsforthetwocontrg)
systems each shift to detect abnormal conditions.
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NRC-NRR has requested the licensee to address this problem of single failures in the containment isolation system angjthe licensee has committed to respond by February 1, 1980 - with design changes to alleviate the NRC concerns.
c.
(Closed) LER 50-155/79-26, Failure of cell #48 in RDS battery system C to meet Technical Specification specific gravity limit. The cell was replaced.
d.
(Closed) LER 50-155/79-27, Emergency Condenser Outlet Valve,
MO 7053, leaked and loop No. 2 was isolated until the plant was shutdown in January 1980. The valve disc was found to not seat properly and the seat had been erroded. The seat was lapped and a packing change made.
e.
(Closed) LER 50-155/79-28, A design review by the vendor de-termined that containment isolation valves CV4097 and CV4095 might not close under worst LOCA pressure conditions from the fully opened position. The valves were modified to re-strict the valve open position to 45', thereby meeting the design basis.
The inseries isolation check valves are also being tested and results should be available in March, 1980.
f.
(Closed) LER 50-155/79-29, Both plant exhaust fans were out of service for eight minutes. To make repairs on one fan, the other had to be shut down to safely gain access to the defective fan. Technical Specii'ications do not state limiting 2/ IE Report No. 50-155/79-16.
3/ Letter NRR to CECO dated October 10, 1979.
}/ Letter' CECO to NRR dated December 3, 1979.
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conditions of operations for these fans. The licensee plans to initiate a Technical Specification change to clarify this problem.
6.
Followup cf'Enspection and Enforcement Bulletins (Closed) IE Bulletin 79-25, Failures of Westinghouse BFD Relays a.
in Safetv-Related Systems. These relays are not in use at BRP.
b.
(Closed) IE Bulletin 79-28, Malfunction of NAMCO Model EA180
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Limit Switches at Elevated Temperatures. The licensee had determined that eight switches of this type were in use but all had been purchased before the production time period cited it the bulletin.
7.
Followup of Inspection and Inforcement Circulars (IEC)
The inspector reviewed the licensee's evaluation of the following IEC's to determine that any necessary actions had been taken:
IEC 79-09, Occurrences of Split or Punctured Regulator Diaphrams a.
in Certain Selfcontained Breathing Appratus.
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IEC 79-13, Replacement of Diesel Fire Pump Eiarting Contactors.
c.
IEC 79-15, Bursting of liigh Pressure llose and Halfunction of Releif Valve and "0" Ring in Certain Self-Contained Breathing Appratus, d.
IEC 79-17, Contact Problems in SB-12 Switches on General Electric Company Metal Clad Circuit Breakers.
IEC 79-18, Proper Installation of Target Rock Safety-Relief Valves.
c.
f.
IEC 79-19, Loose Locking Devices on Ingersoll-Rand Pump Impellers.
g.
IEC 79-20, Failure of GTE Sylvania Relay Type PM Bulletin 7305, Catalog SU12-11-AC with a 120V AC Coil.
8.
Exit Interview
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The inspector met with the licensee representatives (denoted in
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Paragraph 1) at the conclusion of the inspection. The inspector summarized the scope and findings of the-inspection. The following i
l items were discussed:
a.
Open inspection items still outstanding.
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Several minor procedure deficiencies' in both the QA Program and
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The delay in revising QA Program procedures _QAPP 5-1 and QADP 5-51 to indicate that all safety equipment and safety procedures
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must be-reviewed by the Plant Review Committee (Paragraph 4 and i
0I1-321).
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