ML17265A128
| ML17265A128 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/24/1997 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17264B152 | List: |
| References | |
| 50-244-97-13, NUDOCS 9801050164 | |
| Download: ML17265A128 (3) | |
Text
NOTICE OF VIOLATION Rochester Gas and Electric Company Ginna Nuclear Power Station Rochester, New York Docket No. 50-244 License No. DPR-18 During an NRC inspection conducted from October 27 through November 7, 1997, the following violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
1.
10 CFR Part 50, Appendix B, Criterion Vll, "Control of Purchased
- Material, Equipment, and Services," requires that measures shall be established to assure that purchased services conform to the procurement documents.
Documentary evidence that material conforms to the procurement requirements shall be available at the nuclear power plant site prior to the use of such material.
This documentary evidence shall be retained at the nuclear power plant site and shall be sufficient to identify the specific requirements, such as codes, standards, or specifications, met by the purchased
- material, The Rochester Gas 5 Electric (RGRE) Ginna Station Quality Assurance Program (QAP), as described in Nuclear Directive (ND) ND-QAP and Appendix A to the Quality Assurance Manual, requires that the quality assurance program shall apply to activities such as design and procurement. Step 3.5.5 of ND - Plant Engineering Services, "Control of Procurement Activities," requires that the verification and acceptance of procured services be accomplished in accordance with approved procedures.
Section 5.2.7 of Engineering Procedure (EP)-3-P-154, "Review and Approval of Vendor Drawings, Design and Manufacturing Technical Documents," Revision 0, states that vendor calculations shall not form any portion of the basis for operation and operability of safety related modifications, equipment, systems, parts, or procedures unless formal, final approval has been obtained.
Section 5.2 of EP-3-P-154 requires review by and acceptance of the calculations for use by RGSE.
A formal approval memorandum shall be prepared which is reviewed by a nuclear safety and licensing engineer, with final approval by the engineering manager.
A copy of the written, formal approval memorandum shall be incorporated into each vendor calculation and be considered as part of the calculation.
Contrary to the above, as of November 18, 1997, documentary evidence that vendor-performed calculations that were used to establish the basis for operation and operability of safety-related motor-operated valves conformed to the procurement requirements was not available, and no formal, final approval was obtained or incorporated by memorandum into each vendor calculation.
This is a Severity Level IV Violation. (Supplement I).
980i050ih4 971224 PDR ADQCK 05000244 6
10 CFR Part 50, Appendix B, Criterion III, "Design Control," requires that measures shall be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions.
Section 3.2 of RGRE Engineering Procedure 3-P-121, "Design Criteria", Revision 1, requires that "...design inputs shall be specified and approved on a timely basis and to the level of detail necessary to permit the design activity to be carried out in a correct manner and to provide a consistent basis for making design decisions, accomplishing design verification measures, and evaluating design changes."
Contrary to the above, as of November 18, 1997, measures were not established to assure that the design basis of safety-related motor-operated valves was correctly translated into specifications, drawings, and procedures in that certain motor-operated valve (MOV) design basis thrust calculations were incorrect, as evidenced by the following:
A November 3, 1997, thrust calculation used to establish the torque switch settings of the pressurizer power operated relief valve (PORV) block valves (MOV 515 and 516) did not include an adjustment for load sensitive
- behavior, b.
Friction coefficients from the Electric Power Research Institute MOV Performance Prediction Program were incorrectly used as design inputs to calculate the design basis thrust requirements for the PORV block valves and the reactor coolant pump seal water return containment isolation valve (IVlOV 313), resulting in under-predicting the minimum thrust required to fully seat and seal the valves.
This a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Rochester Gas and Electric Corporation of New York, Inc., 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 I, and a copy to the NRC Resident Inspector, within 30 days of receipt 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: (1) 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.
Where good cause is shown, consideration will be given to extending the response time.
Notice of Violation 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.
However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.
Dated at King of Prussia, PA this 24th day of December, 1997