ML20217E043
| ML20217E043 | |
| Person / Time | |
|---|---|
| Site: | Crystal River |
| Issue date: | 04/16/1998 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Richard Anderson FLORIDA POWER CORP. |
| References | |
| 50-302-98-02, 50-302-98-2, EA-98-109, NUDOCS 9804270167 | |
| Download: ML20217E043 (43) | |
See also: IR 05000302/1998002
Text
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' EA 98-109 ! Florida Power Corporation l Crystal River Energy Complex l Mr. Roy A. Anderson (SA2A) ' Sr. VP. Nuclear Operations ,
ATTN: Mgr.. Nuclear Licensing 1 ' 15760 West Power Line Street i Crystal River FL 34428-6708 l SUBJECT: NRC INSPECTION REPORT NO. 50-302/98-02 ! Dear Mr. Anderson: This letter refers to an NRC inspection conducted January 26 - 30. 1998. at your Crystal River facility. The inspection was to review outstanding issues associated with a recent Emergency Operating Procedures inspection. The inspection report was formally transmitted to you by letter dated March 16. j 1998. An open predecisional enforcement conference was conducted in the Region II office on April 2.1998, with members of your staff to discuss an ' apparent violation involving the failure to perform an adequate safety evaluation for procedural and Final Safety Analysis Report (FSAR) changes involving the low pressure injection (LPI) crossover method of long-term core . cooling. Specifically, the issue concerned changes to the procedures and the ' FSAR that deleted use of the LPI crossover method. which the NRC believed was an unreviewed safety question. A list of meeting attendees. NRC slides. and
a copy of your presentation materials are enclosed. j Based on the information developed during the inspection and the information your staff provided during the meeting the NRC has determined that no i violation of NRC requirements occurred. ! At the predecisional enforcement conference. your staff identified weaknesses in the 10 CFR 50.59 evaluation process for the change to the FSAR: however, they contended that no violation of 10 CFR 50.59 occurred because the subject changes did not involve an unreviewed safety question. Under 10 CFR 50.59, an ' unreviewed safety question is involved (as a result of a change) if the consequences of an accident previously evaluated in the Safety Analysis Report may be increased. You correctly interpreted this to mean an increase in l radiological consecuences for those design-basis events evaluated in the SAR. In this case, the cesign-basis events are the spectrum of loss-of-coolant accidents. including the assumption of a single failure. In order for the l change that deleted the use of the LPI crossover method to result in an l increase in consequences. multiple failures in the core cooling systems would have to occur. Such multiple failures are beyond those which the plant is required to withstand, and which are evaluated as part of the design basis in the SAR. Therefore, an unreviewed safety question was not involved. and the apparent violation is withdrawn. 9G04270167 980416 ~ } DR ADOcK 0500 2 i WY
- , . , FPC 2 In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice." a copy of this letter and its enclosures will be placed in the NRC Public Document Room. Sincerely. (0RIGINAL SIGNED BY L. A. REYES) Luis A. Reyes Regional Administrator Docket No.- 50-302 License No.- DPR-72 Enclosures: 1. List of Attendees 2. FPC Presentation Materials 3. NRC Presentation Materials cc w/encls: John P. Cowan, Vice President R. Alexander Glenn Nuclear Production (NA2E) Corporate Counsel Florida Power Corporation Florida Power Corporation Crystal River Energy Complex MAC - ASA 15760 West Power Line Street P. O. Box 14042 Crystal River. FL 34428-6708 St. Petersburg. FL 33733-4042 C. C. Pardee. Director Attorney General Nuclear Plant Operations (NA2C) Department of Legal Affairs Florida Power Corporation The Capitol Crystal River Energy Complex Tallahassee. FL 32304 15760 West Power Line Street Crystal River. FL 34428-6708 Bill Passetti Office of Radiation Control Robert E. Grazio, Director Department of Health and Nuclear Regulatory Affairs (SA2A) Rehabilitative Services Florida Power Corporation 1317 Winewood Boulevard ' 0 ystal River Energy Complex Tallahassee, FL 32399-0700 15760 West Power Line Street Crystal River. FL 34428-6708 Joe Myers. Director Division of Emergency Preparedness James S. Baumstark. Director' Department of Community Affairs Quality Programs (SA2C) 2740 Centerview Drive Florida Power Corporation Tallahassee FL 32399-2100 Crystal River Energy Complex 15760 West Power Line Street Crystal River, FL 34428-6708
. . .. 1 FPC 3 Distribution w/encls: T. Johnson. RII L. Raghavan NRR P. Harmon. RII L. Mellen. RII i J. Bartley. RII ' l J. Lieberman. OE B. Summers. OE (2)
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. . , FPC 3 cc w/encls-(cont *d): Chairman Board of County Commissioners Citrus County 110 N. Apopka Avenue Inverness. FL 34450-4245 Robert B. Borsum Framatome Technologies 1700 Rockville Pike. Suite 525 Rockville. MD 20852-1631 Distribution w/encls: T. Johnson, RII L. Raghavan. NRR P. Harmon RII L. Mellen RII J. Bartley. RII J. Lieberman. OE B. Summers. OE (2) ( R BCIC NRC Resident Inspector U.S. Nuclear Regulatory Commission 6745 N. Tallahassee Road Crystal River. FL 34428
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- . . , LIST OF ATTENDEES l Florida Power Corooration W. Pike, Compliance Manager - FPC I i R. Grazio. Director. Nuclear Regulatory Affairs ] ' P. Fieming. Principal Engineer i S. Greenlee. Manager. Design Engineering ' J. Cowan, Vice President, Nuclear Operations S. Bernhoft. Manager. Licensing , l V. Bamstark. Director. Engineering ' T. Taylor. Acting Plant Manager l I. Wilson, Manager. Nuclear Plant Operations' l R. Glenn. Corporate Counsel - FPC Scientech J. Olshinski INPO S. Hastie j i Nuclear Requlatory Commission J. Johnson. Deputy Regional Administrator. Region II (RII) J. Jaudon. Director, Division of Reactor Safety (DRS), RII L. Plisco, Director. Division of Reactor Projects (DRP). RII A. Boland. Director, Enforcement and Investigation Coordination Staff (EICS), RII B. Mallett. Deputy Director. DRS. RII i W. Rogers, Senior Reactor Analyst. DRS RII ' C. Evans. Regional Counsel. RII L. Wiens Project Manager. Nuclear Reactor Regulation (NRR) S. Ninh, Senior Project Engineer, DRP RII S. Sparks, Senior Enforcement Specialist. EICS, RII R. Schin. Engineering Inspector. DRS. RII T. Reis. Enforcement Coordinator, Office of Enforcement. NRR E. McKenna. Office of Nuclear Reactor Regulation ENCLOSURE 1
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' ' , , . , ISSUE TO BE DISCUSSED i 10 CFR 50.59 Changes, tests and experiments, states in part that "The holder of a license ... may make changes ... in the safety analysis report ... without prior Commission approval, unless the proposed change ... involves ... an unreviewed safety question....A proposed change, test, or experiment shall be deemed to involve an unreviewed safety question if the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety previously evaluated in the safety analysis report may be increased ..." Updated Safety Analysis Report, Section 6.1.2.1.2, Low Pressure injection (LPI), states "The LPI System is provided with a crossover line to permit one LPI string flow of 3,000 gpm to be split equally, thus providing a minimum of 1,500 gpm flow to both core flooding injection nozzles simultaneously should a core flooding line or one LPI pump fail. 1 Long-term core cooling is required by 10 CFR 50.46 and 10 CFR 50, Appendix K. Topical Reports BAW-10103A and BAW-10104 constituted ' V part of the method of complying with these. In chapter 10 of both topical reports, one LPI pump operating with crossover line valves open; flow split between the two LPI lines by the control valves, is discussed as a long- term core cooling method. , On July 3,1979 and May 2,1996, procedures were changed removing use of the LPI crossover method for long-term core cooling without recognizing a USQ was involved. Also, on January 2,1998, the safety analysis report was changed deleting discussion of the LPI crossover as a long term cooling method should a core flood tank line break or one LPI pump fail without recognizing a USQ was involved.
[The apparent violation discussed at the PREDECISIONAL enforcement conference is subject to further review and are subject to change prior to any resulting enforcement action] t O ENCL.080RE 3
, ' ' ,, ' l PREDECISIONAL ENFORCEMENT CONFERENCE AGENDA l CRYSTAL RIVER 3 NUCLEAR PLANT 1 m- l APRIL 2,1998,10:30 A.M. NRC REGION 11 OFFICE, ATLANTA, GEORGIA 1 . . l. OPENING REMARKS AND INTRODUCTIONS J. Johnson, Deputy Deputy Regional Administrator ll. NRC ENFORCEMENT POLICY A. Boland, Director Enforcement and Investigation Coordination Staff l 111. SUMMARY OF THE ISSUES J. Johnson, Deputy Deputy Regional Administrator IV. STATEMENTS OF CONCERNS / APPARENT VIOLATIONS J. Jaudon, Director Division of Reactor Safety V. LICENSEE PRESENTATION VI. BREAK / NRC CAUCUS l Vll. NRC FOLLOW UP QUESTIONS Vill. CLOSING REMARKS J. Johnson, Deputy Deputy Regional Administrator l }}