ML18153A212
| ML18153A212 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/24/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18152A209 | List: |
| References | |
| 50-280-97-09, 50-280-97-9, 50-281-97-09, 50-281-97-9, EA-97-474, NUDOCS 9801210307 | |
| Download: ML18153A212 (3) | |
Text
NOTICE OF VIOLATION Virginia Electric and Power Company Surry Power Station Docket Nos. 50-280 and 50-281 License Nos. DPR-32 and DPR-37 EA 97-474 During an NRC inspection conducted on August 24 through October 4, 1997, violations of NRC requirements were identified. In accordance with the "General Statement of Policy and Procedures for NRC Enforcement Actions,"
NUREG-1600, the violations are listed below:
A.
10 CFR 50.48 states, in part, that each operating nuclear plant licensed to operate prior to January 1, 1979, shall satisfy the requirements of 10 CFR 50, Appendix R.Section III.G. Both Surry units were licensed prior to January 1, 1979.
10 CFR 50, Appendix R, Section III.G.l.(a) requires fire protection features to be provided for structures. systems and components important to safe shutdown to limit fire damage such that one train of systems necessary to achieve and maintain hot shutdown conditions from either the control room or emergency control station(s) is free from fire damage.
10 CFR 50, Appendix R, Section III.G.2 requires the protection of one redundant shutdown train from fire damage which could result in hot shorts, open circuits or shorts to ground during an Appendix R type fire.
Contrary to the above. from July 1988 for Unit 1 and September 1989 for Unit 2 until August 29, 1997, the licensee failed to provide adequate fire protection features for structures, systems and components important to safe shutdown in that adequate means were not available to isolate the circuits from 120 volt alternating current power panels VBl-I and VB 1-III and panels VB 2-I and VB 2-III. located in the respective Unit 1 and 2 computer rooms in the control room complex. from the uninterruptable power supply (UPS) panels. Electrical faults from a 10 CFR Part 50, Appendix R. fire in the control room complex could cause the loss of power from UPS panels lA-1, lA-2, 2A-1 and 2A-1.
These UPS panels provide power to the Appendix R remote shutdown panels, located in each unit's emergency switchgear room and in the cable spreading room; and, supply power to the Appendix R communication equipment located adjacent to the auxiliary shutdown panels in each emergency switchgear room.
The Appendix R panels contained the instrumentation required for performing a plant shutdown from outside the main control room and included instrumentation for steam generator level, reactor coolant system pressure and temperature, and pressurizer level.
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j B.
Surry Operating License Section 2.I for Units 1 and 2 provides that the licensee is required to implement and maintain the administrative controls identified in Section 6 of the Fire Protection Safety Evaluation.
The Surry Fire Protection Program is described in the Surry Appendix R Report.
Chapter 12, Section C of the Surry Appendix R Report describes the Quality Assurance program that is applicable to the. fire protection program.
Section C.8 states that measures established to ensure that conditions adverse to fire protection, such as failures, malfunctions.
deficiencies. deviations. defective components. uncontrolled combustible materials and noncomformances, are promptly identified, reported and corrected.
Contrary to the above. as of August 29, 1997. the licensee failed to identify fully and correct a noncompliance with Appendix R requirements for the control room associated with a vital bus isolation issue discovered by the licensee in 1992. Specifically, because the licensee failed to recognize the significance of the issue and the fact that the plant was outside the design basis, adequate corrective actions and compensatory measures were not implemented until 1997.
(01023)
These violations constitute a Severity Level III problem (Supplement I).
C.
10 CFR 50.72(b)(l)(ii)(B) requires the licensee to notify the NRC of identified plant conditions that are outside the design basis of the plant. The notification is to be made as soon as practical but within one hour of the occurrence.
Contrary to the above, on September 30, 1997, the licensee failed to notify the NRC, within one hour of the occurrence, of conditions outside the design basis of the plant. Specifically, on this date. the licensee determined that Surry Units 1 and 2 had been outside its Appendix R design basis due to a 120 VAC vital bus isolation issue. Although the licensee concluded that the outside of design basis condition was a past condition. the Units were in fact still outside the design basis and a on*e-hour report was required.
(02014)
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Virginia Electric and Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission. ATTN:
Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region II. and a copy to the NRC Resident Inspector at the Surry facility, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:
Cl) the reason for the violation, or, if contested. the basis for disputing the violation. (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations. and (4) the date when full
compliance will be achieved.
Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken.
Where good cause is shown. consideration will be given to extending the response time.
If you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement. United States Nuclear Regulatory Commission, Washington. DC 20555-001.
Under the authority of Section 182 of the Act. 42 U.S.C. 2232, this response shall be submitted under oath or affirmation.
Because your response will be placed in the NRC Public Document Room (PDR). to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material. you must specifically identify the portions of
- your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Dated at Atlanta, GA this 24th day of December 1997