ML20149M124

Notice of Violation from Insp on 860107-17.Violation Noted: Startup Test Procedure TE-SU.ZZ-041, Full Core Shutdown Margin Demostration, Rev 0,reviewed,approved & Issued W/ Listed Deficiencies

ML20149M124
Person / Time
Site:	Hope Creek
Issue date:	03/14/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20149M120	List: ML20149M117 ML20149M124 ML20149M128
References
50-354-86-03, 50-354-86-3, NUDOCS 8802250344
Download: ML20149M124 (1)

Text

. t APPENDIX A NOTICE OF VIOLATION Public Service Electric & Gas Company Docket No. 50-354 Hope C eek Generating Station License No. CPPR-120 During an NRC inspection conducted on January 7 - 17, 1986, a violation of NRC requirements was identified. The violation involved the review, approval and issuance of the startup test procedure relating to initial criticality and full core shutdown margin. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below.

A. 10 CFR 50 Appendix B Criterion XI requires in part that "Test procedures incorporate requirements and acceptance limits contained in applicable design documents and assure that all prerequisites for the test have been met." Regulatory Guide 1.68 Revision 2, which is endorsed by the licen-see's FSAR, indicates in Appendix C that for initial criticality proce-dures, "a critical control rod position should be predicted for anomaly determination, all systems for startup should be aligned and in proper operation, and that technical specification requirements must be met" and generally applicable for all test procedures "that special precautions needed to ensure a reliable test should be highlighted and clearly de*-

cribed in the test procedure."

Contrary to the above, startup test procedure TE-SU.ZZ-041 "Full Core Shutdown Margin Demonstration," Revision 0 was reviewed, approved and issued with the following deficiencies. A prediction of control rod positiens at criticality, based on design documents, was not performed.

The method used to assess conformance with the acceptance criterion for reactivity anomalies was not technically correct. Test prerequisites did not specify the operational condition to perform the test, did not completely address conformance to proposed technical specifications, did not completely specify the required status of the reactor protection system and emergency shutdown system, did not identify the additional protective features provided by removal of the "shorting links," did not identify the reduced setpoints in the source range monitor circuitry, did not identify operator action on high startup rate /short period and did not place limits on control rod withdrawal if criticality is not achieved within predetermined limits. This is a Severity Level V violation (Supplement II).

Pursuant to the provisions of 10 CFR 2.201, Hope Creek Generating Station is hereby reqaired to submit to this office within thirty days of the date of the letter which transmitted this Notice, a written statement or explanation in reply, in:luding: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further i

violations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time.

OFFICIAL RECORD COPY IR HC 86 0003.0.0 03/14/86 8802250344 860314 PDR ADOCK 05000354 0 DCD