View source for 3F0586-23, Forwards Rev 0 to Administrative Instruction AI-704, Reactor Trip Review & Analysis, Revising 851125 Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review.Procedure for Restart Evaluations Incorporated Into AI-704

{{Adams
| number = ML20155J975
| issue date = 05/21/1986
| title = Forwards Rev 0 to Administrative Instruction AI-704, Reactor Trip Review & Analysis, Revising 851125 Response to Generic Ltr 83-28,Item 1.1 Re post-trip Review.Procedure for Restart Evaluations Incorporated Into AI-704
| author name = Widell R
| author affiliation = FLORIDA POWER CORP.
| addressee name = Stolz J
| addressee affiliation = NRC OFFICE OF NUCLEAR REACTOR REGULATION (NRR)
| docket = 05000302
| license number = 
| contact person = 
| document report number = 3F0586-23, 3F586-23, GL-83-28, NUDOCS 8605270264
| package number = ML20155J977
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, UTILITY TO NRC
| page count = 2
}}

=Text=
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{s          0e, Power C 0 R P O R Ai1O N May 21, 1986 3F0586-23 Mr. John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing B Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Subj ect: Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 Generic Letter 83-28, Item 1.1 Post Trip Review

==Dear Sir:==

Florida Power Corporation (FPC) {{letter dated|date=November 25, 1985|text=letter dated November 25, 1985}} (3F1185-27) provided responses to a NRC {{letter dated|date=October 24, 1985|text=letter dated October 24, 1985}} (3N1085-13) concerning the subject post trip review used by FPC. We are revising the {{letter dated|date=November 25, 1985|text=November 25, 1985 letter}} with this submittal.
Item 1 The criteria for determining the need of independent assessment of the events following a trip are required.
Response 1 FPC utilizes AI-704, Reactor Trip Review and Analysis (an information copy is attached), to gather and analyze data relevant to plant performance before, during, and after a plant trip.                     The reactor trip review program consists of four distinct phases:
: 1.      Post-Trip Review
: 2.      Restart Decision
: 3.      Independent Review
: 4.      Subsequent Evaluation                                                                                 h y ,I I
B605270264 860521 PDR       ADOCK 05000302 P                      PDR GEN ERAL OFFICE 3201 Thirty-fourth Street South. P.O. Box 14042, St. Petersburg, Florida 33733 e 813-866 5151

o t May 21, 1986 3F0536-23 Page 2 After stabilization of the pl ant , the Shif t Operations Technical Advisor (S0TA) completes the data gathering and event analysis portions of Enclosure 1 of AI-704.      When this effort is compl eted , the S0TA and Nuclear Plant Manager / Man-On-Call (NPM/MOC) review and discuss the event.       This review insures that the root cause of the event has been determined (if possible) and should ensure that adequate corrective actions have been proposed to prevent recurrence of the event.        This review is documented as part of AI-704.
Upon compl etion of the NPM/M0C review, the Plant Review Committee (PRC) shall be convened to perform an independent review of the restart evaluation. The PRC Chairman will document the Committee's recommendation to restart the reactor in accordance with AI-704.
Upon completion of the PRC review, the NPM/M0C reviews all sections of the restart report including any PRC recommendations.        When the NPM/M0C is satisfied that all corrective actions required prior to restart are complete and that no outstanding safety concerns remain, he authorizes restart of the reactor.      The Shif t Supervisor On Duty (SS0D) also reviews the evaluation and signs prior to restart.
The final step in the post-trip review process is to perform a subsequent evaluation to satisfy regul atory reporting requirements,          inform other utilities of our experiences, and to document observed plant response for future study.
Item 2 Incorporate these criteria       into the procedure for conducting       restart evaluations.
Response 2 These criteria have been incorporated in AI-704.
Sincerely, Rolfh. Widell Manager, Nuclear Operations Licensing and Fuel Management JWT/ feb xc:    Dr. J. Nelson Grace Regional Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta Street N.W., Suite 2900 Atlanta, GA 30323}}