IR 05000280/1979063
| ML18136A376 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 11/21/1979 |
| From: | Elrod S, Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18136A373 | List: |
| References | |
| 50-280-79-63, 50-281-79-83, NUDOCS 8001150060 | |
| Download: ML18136A376 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 Report Nos. 50-280/79-63 and 50-281/79-83 Licensee:
Virginia Electric and Power Company Richmond, Virginia 23261 Facility:
Surry Units 1 and 2 Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 Summary Inspection on September 24-28, 1979 Areas Inspected Virginia 1-} l-~/1 79 Date Signed il.~td This routine, unannounced inspection involved 38 inspector-hours onsite in the areas of Bulletin/Circular followup and followup of outstanding item Results Of the two areas inspected, no apparent items of noncompliance or deviations were identified in one area; one apparent item of noncompliance was found in one area (Infraction-Failure to follow procedures for making a design cliange (280/79-63-01; 281/79-83-01).
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800115006$
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DETAILS Persons Contacted Licensee Employees
- W. L. Stewart, Station Manager
- J. L. Wilson, Superintendent Operations
- R. F. Saunders, Superintendent Maintenance
- D. A. Christian, Engineering Supervisor
- F. L. Rentz, Resident Q. C. Engineer W. Kibler, Electrical Supervisor J. Moody, Fire Marshal Other licensee employees contacted included technicians, operators, and office personne NRC Resident Inspector
- D. J. Burke, Resident Inspector
- Attended exit intervie.
Exit Interview The inspection scope and findings were summarized on September 28, 1979 with those persons indicated in Paragraph 1 abov The items described in Paragraphs 5-7 of this report were discusse With respect to the item of noncompliance described in paragraph 7, the plant manager stated that a design review would be made of the fire pump engine modificatio.
Licensee Action on Previous Inspection Findings Not inspecte.
Unresolved Items Unresolved items were not identified during this inspectio.
Review of NRC IE Circulars and Bulletins The following IE Circulars and Bulletins were reviewed with licensee management to determine applicability and appropriateness of action taken: IE Circular 79-09 (Closed).
This Circular concerned occurrances of split or punctured diaphrams in Scott Air Pack II/IIA Self Contained Breathing Apparatus (SCBA).
It was determined that Surry Power Station does not use Scott Air Pack SCBAs (280/281/79-CI-09).
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IE Circular 79-11 (Open).
This Circular concerned design and construc-tion interface problems between Construction Permit holders and their Architect/Engineer (AE) contractor As such, it was not addressed to Surr In light of the extensive contracted AE activities at Surry related to steam generator repair and seismic reanalysis of piping and supports, plant management agreed to review this Circular for the principles involve This item will be further addressed in a subse-quent inspection (280/281/79-CI-11). IE Circular 79-12 (Closed).
This Circular concerned potential failure of Emergency Diesel turbochargers upon a repeat rapid start within certain time limits after previous operation at full temperatur Pending development of an engine modification by the manufacturer, the licensee has modified plant procedures to incorporate recommendations of the Circular (280/281/79-CI-12). IE Circular 79-13 (Closed).
This Circular concerned replacement of the starter contactors for certain models of Cummins brand fire pump diesel engine Surry's fire pump diesel engine is not one of the affected model~ (280/281/79-CI-13).
The starting contactors were, however, replaced with the replacement contactor referenced in Circular 79-1 An item of noncompliance associated with this action is discussed in paragraph 7.
IE Circular 79-15 (Closed).
This Circular concerned bursting of high pressure hose and malfunction of relief valve "O" rings in Survivair Mark I Self Contained Breathing Apparatus (SCBA).
It was determined that Surry Power Station does not have any of the subject SCBAs
.(280/281/79-CI-15).
IE Circular 79-16 (Closed-not applicable).
This Circular, addressing excessive radiation exposures to a radiographer and memb~rs of the general public, was addressed to radiography licensees arid did not specifically applicable to Surr The inspector provided a copy to the plant management for information (280/281/79-CI-16).
IE Circular 79-17 (Closed).
This Circular concerned a contact problem in SB-12 switches on General Electric Company Metalclad circuit breakers. It was determined that the subject circuit breakers are not installed at Surry Power Station (280/281/79-CI-17).
IE Circular 78-18 (Open).
This Circular concerned damage to electrical cables resulting from a fire test of cable trays conducted by Underwriters Laborator This Circular is considered pertinent to, and will be reviewed in conjunction with, the recently issued Surry Fire Protection Safety Evaluation Report (280/281/78-CI-18).
IE Bulletin 79-11 (Open).
This Bulletin concerned material failure of part of the overcurrent trip devices on Westinghouse brand DB-50 and DB-75 Circuit breakers, and with periodic overcurrent testing of all
-3-safety-related circuit breaker The licensees written response dated July 13, 1979 indicated that the subject breakers with overcurrent trip device are not used at Surr Similar breakers are used but without the trip devic The inspector considers that aspect of Bulletin 79-11 to be close The licensees original *response to Bulletin 79-11 was inadequate in the area of periodic testing of all safety-related circuit breakers in that a schedule for development of a test program for 480 Volt circuit
,.,
breakers was not provide During this inspection, a supplemental response dated August 13, 1979 was provided to the inspecto This supplemental response committed the licensee to have a test program implement!:!d by November 15, 1979 for Unit No. 1 and by December 1, 1979 for Unit No. This commitment is acceptabl The inspector reviewed progress toward completion of test program developmen The licensee's staff appeared to be quite knowledgeable concerning circuit breaker testing and appeared to be progressing satisfactorily toward test program developmen The major obstacles appeared to be timely receipt from venders of a test machine and of the list of individual circuit breaker setpoint The inspector had no further immediate questions in this area and will review progress during a subsequent inspection (280/281/79-BU-ll). Followup of Outstanding Items During previous inspections 280/79-22 and 280/79-28, the inspector questioned a portion of the methodology used to determine support loads for the seismic reanalysis of safety related piping (280/79-22-03)
.and the use of existing hanger drawings, without verification, for the support analysis (280/79-28-01).
Subsequent inspections at the plant and at the seismic reanalysis contractor's headquarters have shown that these issues were resolve followup items 280/79-22-03 and 280/79-28-01 are close During a previous inspection (280/79-22, 281/79-34), this inspector had observed that administrative control of operator's notes taped to control panels appeared to be inadequat During this inspection, the inspector observed placement of notes while touring the control room and reviewed Standing Order XV which has been.issued on this subjec No problems were observe Since the licensee appears to be adequately controlling these notes, this followup item (280/79-22-02, 281/79-34-02)
is close During a previous inspection (281/79-28), the inspector had questioned whether the licensee's approach to collecting data for radiation exposure reports on the Steam Generator Repair Project met the limiting condition for operation imposed by license amendments 47 and 46 respectively to the operating licenses for Surry Units No. 1 and N.
This subject was further pursued in depth on May 30, 1979 at a meeting at Surry Power Station between NRC personnel from the.Environmental
-4-Licensing Branch, Division of Operating Reactors (the recipients of the report) and the license At that time, the licensee presented his report preparation methodology and proposed revision Subsequently, this inspector has verified with the report recipient that the report is considered acceptabl Item 281/79-28-02 is close During an earlier inspection, 280/79-22, this inspector questioned the conflict between a commitment to make all necessary repairs to safety-related pipe supports prior to Unit No. 1 startup and a stated desire '
to startup early based on favorable conservatism found in initial seismic reanalysi Subsequent events have shown that the repairs necessary for startup were mad Item 280/79-22-04 is close.
Modification of the starting circuit for the Safety Class I diesel-driven fire pump engin Using the replacement part information in IE Circular 79-13, the plant staff replaced, as a maintenance action, the starter contactor on the subject engine on September 21, 1979 (Maintenance report S-0908210831).
Since this diesel engine is not one of those addressed in the Circular, this is a design change to a piece of Safety Class I equipmen Contrary to the requirements of the Nuclear Power Station Quality Assurance Manual, Section 3, no design change was submitted, no design review was made. -This is an item of noncompliance with 10CFR50, Appendix B, criterion V, as implemented by the Nuclear Power Station Quality Assuraqce Manual Sections 5 and 2 (280/79-63-01; 281/79-83-0l).