IR 05000335/1998014

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Discusses Notice of Violation & Exercise of Discretion Re Insp Rept 50-335/98-14 & 50-389/98-14 Concerning FP&L Analysis Methodology Associated with fire-induced Circuit Failure.Review Completed & Determination Provided
ML17241A494
Person / Time
Site: Saint Lucie  NextEra Energy icon.png
Issue date: 10/05/1999
From: Reyes L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Plunkett T
FLORIDA POWER & LIGHT CO.
References
50-335-98-14, 50-389-98-14, EA-98-513, NUDOCS 9910210102
Download: ML17241A494 (9)


Text

October 5, 1999

SUBJECT:

NOTICE OF VIOLATIONAND EXERCISE OF DISCRETION (NRC INSPECTION REPORT NOS. 50-335/98-14, 50-389/98-14)

Dear Mr. Plunkett:

By letter dated June 23, 1999, the NRC informed Florida Power and Light Company (FP8L) of our continuing review of your response of April29, 1999, to our Notice of Violation (Notice) and Exercise of Discretion issued on March 31, 1999, concerning activities conducted at the St. Lucie facility. The issue in question involves an FP8L analysis methodology associated with fire-induced circuit failures, as discussed below. The NRC has completed its review of the issue, and this letter serves to provide our determination in this matter.

In your April29, 1999, response, FP&L agreed with the NRC's characterization of the issue cited in the Notice, the issues dispositioned as non-cited violations, and the Exercise of Discretion related to the potential for fire to cause a breach at a high-low pressure interface due to multiple spurious actuations of equipment.

However, FP8 L disagreed with the NRC's characterization of the first subpart of the violation for which Enforcement Discretion was also exercised.

This violation involved an FP8L analysis methodology which, contrary to the requirements of 10 CFR Part 50, Appendix R, Section III.L.7, assumed only one spurious equipment operation to occur as a result of fire in any area, without any further consideration of the number, type, or specific location of potentially affected cables and circuits. FP8L stated that its licensing bases for St. Lucie Units 1 and 2 do not require consideration of multiple spurious actuations of equipment in the event of a fire, other than for high-low pressure interfaces.

The NRC and FP8 L also discussed the violation at issue during an open, predecisional enforcement conference conducted on January 7, 1999.

During this conference, FP8L disagreed that this issue constituted a violation, stating that the original St. Lucie Safe Shutdown Analysis assumed that any and all spurious equipment operations occurred one at a time in accordance with NRC Generic Letter 86-10.

Following the conference, the NRC determined that this issue constituted a violation of 10 CFR 50, Appendix R, Section III.L.7. However, the NRC exercised discretion to not issue a Notice for the Severity Level III violation, because of the outstanding questions about existing staff guidance and the underlying regulatory requirement concerning fire-induced circuit failures, the low risk significance, and FP8L's actions to promptly perform the required analysis, evaluate the effect of this condition on the facility, and complete the required corrective actions.

r'Q, 9910210102 991005 PDR ADQCK 05000335

PDR

FP8L FPBL's April29, 1999, letter did not provide any new information beyond that presented during the conference of January 7, 1999, or during the Fire Protection Functional Inspection and the follow-up inspection conducted in October and November 1998.

Notwithstanding this fact, NRC has carefully considered the bases for your denial and re-examined the regulatory and licensing bases for the violation. Based on this evaluation, we have concluded, for the reasons presented in Enclosures 1 and 2 to this letter, that the violation occurred as stated.

In summary, the bases for this conclusion are (1) the Agency's formal, regulatory position on the scope of the 10 CFR Part 50, Appendix R, Section III.L.7requirement, and (2) our determination that consideration of multiple spurious operation of equipment in the event of a fire is within the licensing basis of St. Lucie, and the St. Lucie licensing basis does not exempt Units 1 and 2 from this requirement.

The Agency's formal position on this issue was communicated to the industry in a March 11, 1997, letter from Mr. Samuel J. Collins, Director, Office of Nuclear Reactor Regulation, to Mr. Ralph E. Beedle, Senior Vice President and Chief Nuclear Officer, Nuclear Energy Institute (NEI). This letter is provided as Enclosure 2.

Your April29, 1999, letter also stated that the NRC Staffs position that the effects of fire induced multiple spurious actions must be analyzed is not consistent with the NRC's previously issued guidance for implementation of fire protection requirements.

The NRC has taken steps to improve the industry's understanding of the requirement, most notably with issuance of the Agency's formal, regulatory position on the scope of the 10 CFR Part 50, Appendix R requirements (Enclosure 2). While the NRC acknowledges that certain questions about differing staff and licensee interpretations of the existing guidance and regulatory requirements remain, the NRC ultimately concluded that St. Lucie was in violation of the requirement.

However, the NRC gave appropriate consideration to unresolved questions, and concluded that the Exercise of Discretion to not issue a Notice was appropriate.

After the NRC issued the Notice and Exercise of Discretion to FP8L, it revisited existing enforcement guidance regarding violations involving fire-induced circuit failures. The Agency's position on this matter was communicated in

.a letter dated July 21, 1999, from Mr. Collins to Mr. Joseph Colvin, President and Chief Executive Officer, NEI. This letter is provided as Enclosure 3.

In this letter, the NRC staff identified additional situations in which the exercise of discretion may be appropriate, and noted that it did not intend to revisit past cases in which enforcement actions have been dispositioned.

The staff has reviewed the revised enforcement guidance and concluded that it does not alter the action taken in the St. Lucie case.

No response to this letter is required.

Should you have any further questions regarding this issue, please contact Steve West, Chief, Fire Protection Engineering and Special Projects Section, Office of Nuclear Reactor Regulation, at 301-415-1220.

i FP8L In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures willbe placed in the NRC Public Document Room.

Sincerely, Original signed by J. Johnson for Luis A. Reyes Regional Administrator Docket Nos. 50-335, 50-389 License Nos. DPR-67, NPF-16 Enclosures:

1. NRC Evaluations and Conclusion 2. Samuel J. Collins letter of March 11, 1997 3. Samuel J. Collins letter of July 21, 1999

i FP&L cc w/encls:

J. A. Stall Vice President St. Lucie Nuclear Plant 6351 South Ocean Drive Jensen Beach, FL 34957 R. G. West Plant General Manager St. Lucie Nuclear Plant Electronic Mail Distribution

J. Kammel Radiological Emergency Planning Administrator Department of Public Safety Electronic Mail Distribution Douglas Anderson County Administrator St. Lucie County 2300 Virginia Avenue Ft. Pierce, FL 34982 E. J. Weinkam Licensing Manager St. Lucie Nuclear Plant Electronic Mail Distribution John Gianfrancesco, Manager Administrative Support 8 Special Projects Florida Power & Light Company Electronic Mail Distribution Mark Dryden Administrative Support 8 Special Projects Florida Power 8 Light Company Electronic Mail Distribution Rajiv S. Kundalkar Vice President - Nuclear Engineering Florida Power 8 Light Company Electronic Mail Distribution M. S. Ross, Attorney Florida Power 8 Light Company Electronic Mail Distribution WilliamA. Passetti Bureau of Radiation Control Department of Health Electronic Mail Distribution Joe Myers, Director Division of Emergency Preparedness Department of Community Affairs Efectronic Mail Distribution

FPBL Distribution w/encls:

WTravers, EDO FMiraglia, DEDR CPaperiello, DEDMS SCollins, NRR JZwolinski, NRR BKeeling, OCA EJulian, SECY HBell, OIG Enforcement Coordinators RI, RIII, RIV WBeecher, OPA KClark, Rll TRoss, Rll SRudisail, RII LWert, Rll KLandis, Rll BMallett, Rll VMcCree, Rll GWiseman, Rll WGleaves, NRR CPeterson, NRR PMadden, NRR SWest, NRR RTrojanowski, Rll OE:EA File (BSummers, OE)

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EVALUATIONSAND CONCLUSION By letter, dated March 31, 1999, the NRC transmitted a Notice of Violation (Notice) and Exercise of Discretion for various issues associated with the Fire Protection Functional Inspection conducted in March and April 1998.

On April 29, 1999, Florida Power and Light Company (FP8L) provided a response in which it agreed with the NRC's characterization of all but one of the issues associated with the Notice, the non-cited violations, and the Exercises of Discretion.

FP8L disagreed with the NRC's determination that the issue involving an FP&L analysis methodology which assumed only one spurious equipment operation to occur as a result of fire in any area without any further consideration of the number, type, or specific location of potentially affected cables and circuits, constituted a violation of 10 CFR Part 50, Appendix R, Section III.L.7.

Although the NRC determined that a violation occurred, the NRC exercised discretion to not issue a Notice for this Severity Level III violation, because of the outstanding questions about existing staff guidance and the underlying regulatory requirement concerning fire-induced circuit failures, the low risk significance, and FP8L's actions to promptly perform the required analysis, evaluate the effect of this condition on the facility, and complete the required corrective actions.

The NRC's evaluations and conclusion regarding the licensee's arguments are as follows:

Summa of the License

'

s onse By letter dated April29. 1999. FP8L stated the following: "FPL respectfully disagrees with the first subpart of the apparent violation involving spurious operation analysis and protection methods for safe shutdown capability. The licensing bases of St. Lucie 1 and 2 do not require consideration of multiple spunous actuations of equipment in the event of a fire, other than for high-low pressure interfaces Further, the Staffs position that the effects of fire induced multiple spurious actuations must be analyzed is not consistent with previously issued guidance for implementation of NRC fire protection requirements.

Accordingly no violation occurred."

NRC Evaluation of the i

n

'

s onse This issue, along with other fire protection issues, was discussed at an open, predecisional enforcement conference held with FP&L on January 7, 1999.

During the conference, FP8L also expressed its disagreement with the NRC's determination that the failure to consider multiple spurious actuations of equipment. for other than high-low pressure interfaces, constituted a violation of 10 CFR Part 50. Appendix R,Section III.L.7. Although the FP&L letter of April29, 1999, did not present any additional information regarding this issue beyond that discussed at the conference and previously considered by the NRC, a re-evaluation of the regulatory and licensing basis for the violation was performed.

The potential for multiple fire induced circuit failures to impair safe shutdown capability is within the scope of 10 CFR 50, Appendix R, Section III.L.7, and as such licensees are required to consider these potential circuit failures in their fire protection programs.

The NRC has clearly Enclosure

communicated this position to the industry through various means including a March 11, 1997, letter from Mr. Samuel J. Collins, Director, Office of Nuclear Reactor Regulation, to.

Mr. Ralph E. Beedle, Senior Vice President and Chief Nuclear Officer, Nuclear. Energy Institute (Enclosure 2).

The NRC's position was most recently presented to the industry in a letter dated July 21, 1999, from Mr. Collins to Mr. Joseph Colvin, President and Chief Executive Officer, NEI.

This letter is provided as Enclosure 3.

In this letter, the NRC staff identified additional situations in which the exercise of discretion may be appropriate, and noted that it did not intend to revisit past cases in which enforcement actions have been dispositioned.

Given this regulatory conclusion, the staff carefully reviewed the St. Lucie licensing basis to determine ifit was consistent with the requirements of 10 CFR Part 50, Section III.L.7. The St. Lucie licensing bases for fire protection is contained in Section 2.C.3 of the operating license, and states the following:

"The licensee shall implement and maintain in effect all provisions of the approved fire protection program as described in the Updated Final Safety Analysis Report for the facility (the fire protection program and features were originally described in licensee submittals L-83-514 dated October 7, 1983, L-83-227 dated April 22, 1983, L-83-261 dated April 25, 1983, L-83-453 dated August 24, 1983, L-83-488 dated September 16, 1983, L-83-588 dated December 14, 1983, L-84-346 dated November 28, 1984, L-84-390 dated December 31, 1984, and L-85-71 dated February 21, 1985) and as approved in by NRC letter dated July 17, 1984 and supplemented by NRC letters dated February 21, 1985, March 5, 1987, and October 4, 1988 subject to the following provision:

The licensee may make changes to the approved fire protection program without prior approval of the commission only ifthose changes would not adversely affect the ability to achieve and maintain safe shutdown'in the event of a fire."

In licensee submittal L-83-227 dated April22, 1983, the licensee stated that:

"With regard to circuits of equipment whose spurious operation could impact safe shutdown capability or violate primary or secondary pressure boundary, FP8L has treated these circuits identically as those of hot and cold shutdown equipment.

"AIIpower, instrumentation and control cable of spurious equipment (as well as that of hot and cold shutdown equipment) has been traced throughout the power plant to identify the cable functions routed through each fire area.

Note that spurious valves are assumed to move to worst case positions unless the breakers associated with the valves are locked open during power operation, or the cables are protected."

Based on the staffs review of the licensing basis, the NRC has determined that the St. Lucie design bases description is consistent with the requirements and expectations of 10 CFR Part 50, Appendix R, Section III.L.7, and it does not exclude or exempt St. Lucie from considering multiple spurious actuations of equipment in the event of a fire.

Enclosure

NRC Conclusion For the above reasons, the NRC staff concludes that the violation occurred as stated.

Enclosure 1