ML20199F675
| ML20199F675 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 01/26/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20199F652 | List: |
| References | |
| NUDOCS 9802040077 | |
| Download: ML20199F675 (1) | |
Text
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NUCLEAR RECULATCRY COMMISSION
\\..... /j WASHINGTON, D.C. 300eHe01 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION QUALITY ASSURANCE PROGRAM DESCRIPTION CHANGE ILLINOIS POWER COMPANY CLINT.QN POWER STATION DOCKET NO. 50-481 1.0 EVALUATION in a [[letter::U-602887, Forwards Proposed Change to CPS USAR Which Will Impact Commitments Made in CPS QAP Description for NRC Review & Approval|letter dated December 9,1997]], the Illinois Power Company submitted a proposed change to the Clinton Power Station (CPS) Updated Safety Analysis Report (USAR) which will impact commitments made in the CPS Quality Assurance Program Description (QAPD). The change concerns qualifications for personnel filling the position of Assistant Plant Manager -
Operations. Currently, USAR Figure 13.13, CLINTON POWER STATION ORGANIZATION, contains a requirement for the position of Assistant Plant Manager Operations to have had a CPS Senior Reactor Operator (SRO) license. CPS is proposing a change to USAR Figure 13.1 3, deleting the SRO license requirement such that the QAPD will be consistent with the requirements contained in CPS's Technical Specifications. Also, CPS is requesting an exception to Regulatory Guide 1.8, Revision 2 which conditionally endorses ANSI /ANS 3.1 1978. ANSI /ANS 3.1 1978, Section 4.2.2, Operations Manager states, "...the operations manager shall hold a Senior Reactor Operator's license...." CPS's proposed exception states,
'The operations manager or at least one operations middle manager shall hold an SRO license for Clinton Power Station.' CPS TS 5.2.2, item f, requires that "The operations manager or at least one operations middle manager shall hold an SRO license for Clinton Power Station." TS 5.5.2, item f, is consistent with NUREG 1434, ' Standard Technical Specifications General Electric Plants, BWR/6 Revision 1."
2.0 CONCLUSlQN The proposed QAPD exception described above constitutes a reduction in commitment in the QAPD previously approved by the NRC; however, this exception continues to satisfy the provisions in NUREG-0800," Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants.' The proposed changes in the QAPD provide consistency with the current TS. In a letter dated December 2,1994, the NRC approved TS 5.2.2, item f, as described in Amendment 95 to Facility Operating License No. NPF-62 Clinton Power Station, Unit 1, with an enclosed Safety Evaluation Report. Therefore, the proposed revision to CPS's QAPD, dated December 9,1997, continues to comply with the quality aswrence criteria of Appendix B to 10 CFR Part 50 and is accepteble.
PrincipalContributor: M. Bugg Date: January 26, 1998 9002040077 900126 PDR ADOCK 05000461 P