Text

Corrections of Typographical and Formatting Errors Regarding Amendment No. 133 and the Associated Safety Evaluation
	ML102510852
Person / Time
Site:	Harris
Issue date:	12/28/2010
From:	Vaaler M, Mozafari B; Plant Licensing Branch II
To:	Burton C; Carolina Power & Light Co
	Vaaler, Marlayna, NRR/DORL 415-1998
References
	TAC MD8807
	Download: ML102510852 (43)
	v • d • e

OFFICIAL USE OMlY SECURITY RELATED IMFORMATIO~J UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 28, 2010 Christopher L. Burton, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165 SUB..IECT: SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - CORRECTIONS OF TYPOGRAPHICAL AND FORMATIING ERRORS REGARDING AMENDMENT NO. 133 AND THE ASSOCIATED SAFETY EVALUATION (TAC NO. MD8807)

Dear Mr. Burton:

On June 28, 2010, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 133 to Renewed Facility Operating License No. NPF-63 for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP) [Agencywide Documents Access and Management System (ADAMS) Accession No. ML101130535], in response to your application dated May 29, 2008, as supplemented by letters dated November 14, 2008, December 11,2008, August 13, 2009, August 28,2009, October 9, 2009, February 4, 2010, and April 5, 2010.

The amendment transitioned the existing fire protection program to a risk-informed, performance-based program based on National Fire Protection Association (NFPA)

Standard 805 (NFPA 805), "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition, in accordance with Title 10 of the Code of Federal Regulations, Paragraph 50.48(c).

Members of the NRC and Carolina Power & Light Company (now doing business at Progress Energy Carolinas, Inc.) staff subsequently identified several typographical and formatting errors in the NRC safety evaluation associated with the amendment. Specifically:

Formatting changes to correct font size errors were made on pages 212, 221, 350, 351, 357, 388,410,416,417,427,429,432,469,475,492, and 493 of the safety evaluation.

The word "flowpath" was changed to "flow path" for consistency in the "VFDR Description" field on pages 354, 391, 392, 456, and 494 of the safety evaluation.

Page 46: The sentence "The code of record for the new VEWFDS detection system is NFPA 72, "National Fire Alarm and Signaling Code," 2010 Edition ... " should be changed to read "The code of record for the new VEWFDS detection system is NFPA 72, "National Fire Alarm and Signaling Code," 2007 Edition ... " This is in accordance with the design basis code of record used by the licensee for the VEWFDS, which was subsequently evaluated by the NRC staff.

OFFICIAL USE O~JLY SECURITY RELATED I~JFORMiAiTIO~J

OFFICIAL. USE QNL.¥ SECURITV REL.ATED INFORMA::rIQN C. Burton -2 Page 106: Reference 42 should be changed to read "NFPA 72, "National Fire Alarm and Signaling Code," 2007 Edition, National Fire Protection Association, Quincy, MA" Page 201: The V&V Basis Column should be changed to include NUREG-1805 and NUREG-1824, and the final sentence of the NRC Staff Evaluation of Acceptability Column should be changed to read: "Since (1) the V&V basis for the use of NUREG-1805 is NUREG-1824 and the licensee stated that the correlation was applied within the limits of its applicability, and (2) the V&V of the correlations used for flame spread rate along a cable tray in the fire modeling calculations as published by Lee were subjected to a peer review, published in a widely recognized peer-reviewed journal article or in a conference report, and were applied within the limits of their applicability, the NRC staff finds use of this correlation in the HNP application acceptable."

Page 205: Reference 6 should be changed to read "Lee, BT, "Heat Release Characteristics of Some Combustible Fuel Sources in Nuclear Power Plants,"

NBSIR 85-3195, U.S. Department of Commerce, National Bureau of Standards, Gaithersburg, MD, July 1985 (Attachment 3 to ADAMS Accession No. ML013390436)."

Page 218: RAI 5.15 -- a note should be added to the "Subject" field that reads "(Note that HNP uses a 6.9kV switchgear; however, the guidance above is still applicable)."

Page 265: Fire Zone -- the table states that no suppression is installed, yet under the "R" column, it states that suppression is required. The "Yes" under suppression should be changed to a "No" and not in bold font.

Page 278: Fire Zone _ should be changed t o _ .

Page 306: Third paragraph -- the words "fire fighting" and "can not" should be changed to "firefighting" and "cannot."

Page 312: Open Item 50 -- in the "VFDR Description" field, the component list should end with " _ , " not " _ . "

Page 317: Fire Zone _ should be changed t o _ .

Page 341: Open Item 10 -- in the "Disposition" field, the word "ortable" should be changed to "portable."

Page 342: The final sentence should read "...these VFDRs is zero," not "... this VFDR is zero."

Page 391: Open Item 373 -- in the "Disposition" field, the word "Meggit" should be changed to "Meggitt."

OFFICIAL. USE QNL.¥ SECURITV REL.A::rED INFORMA::rIQ~J

OFFICIAL USE O~JlY SECURITY RELATED I~JFORMATIO~J C.Burton -3 Page 392: Open Item 142 -- in the "Disposition" field, the word "Meggit" should be changed to "Meggitt."

Page 421: The "Evaluation of Fire Suppression Effects ... " header should end with "Fire Area _ , " not "Fire Area _ . "

Page 442: Deviation "Evaluation" field -- the word "ERBS" should be changed to "ERFBS."

Page 456: Deviation "Evaluation" field -- the word "ERBS" should be changed to "ERFBS."

Page 469: Spacing should be changed to move Recovery Actions statement onto page 469.

Page 470: Spacing should be changed to move "Recovery Actions Credited for Defense-in Depth (RA-DID)" header to top of page 470.

Page 490: The "Evaluation of Fire Suppression Effects ... " header should end with "Fire Area ," not "Fire Area "

Page 495: Open Item 19 -- in the "Disposition" field, the word "shange" should be changed to "change."

The NRC staff determined that these typographical and formatting errors were inadvertently introduced. The corrections do not change any of the conclusions in the safety evaluation related to the amendment and do not affect the associated Federal Register notice to the public.

Corrected safety evaluation pages are enclosed. We regret any inconvenience this may have caused. If you have any questions regarding this issue, please contact me at 301-415-3178.

Sincerely,

~L-llL8JfJevJ-~

Brenda Mozafari, Senior Pro~t ~~~ger Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-400

Enclosure:

Corrections to NRC Safety Evaluation for Amendment NO.133 to NPF-63 cc wi enclosure: Distribution via Listserv OFFICIAL USE O~JlY SECURITY RELATED I~JFORMATIO~J

OFFICIAL USE ONL¥ SECURITV RELA-TED I.JFORMA..-TION ENCLOSURE CORRECTED PAGES OF THE SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 133 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-63 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT. UNIT 1 DOCKET NO. 50-400

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- 46 cabinets at HNP during the incipient stage of a fire. The following discussion is based on the information provided by the licensee in LAR Section 4.8.2.4, "Incipient Fire Detection System."

The licensee selected the specific plant electrical cabinets to be monitored by the VEWFDS based on risk insights gained while developing the HNP Fire PRA. The VEWFDS are being provided as an enhancement to the existing plant fire protection program and are intended to either assist in preventing multiple spurious actuations that could result from fire damage within the cabinets, or prevent a fire within the cabinet from progressing to the point at which it could ignite overhead cables, resulting in the development of a hot gas layer (HGL) in the room. The VEWFDS accomplishes the first goal by detecting a fire before it has the opportunity to progress beyond the smoldering incipient stage, thereby preventing damage to more than the initial degrading component or subcomponent.

The code of record for the new VEWFDS detection system is NFPA 72, "National Fire Alarm and Signaling Code," 2007 Edition (Reference 42). NFPA 76, "Standard for the Fire Protection of Telecommunications Facilities" (Reference 43), is also being used as a part of the design basis with respect to transport time in order to ensure that the VEWFDS meets the performance goals for proper credit in the Fire PRA. Specifically, the maximum transport time of 60 seconds for the VEWFDS from NFPA 76 is being used as a design basis rather than the less conservative 120 second time requirement from NFPA 72 for air sampling detection systems.

The VEWFDS is an air sampling type fire detection system that utilizes "cloud chamber" detection technology to continually sample air from different zones. The detector is designed to identify submicrometer, precombustion particles at the earliest state of a fire (incipient stage) before the visible or smoldering smoke stage. According to statements made by the VEWFDS manufacturer for HNP, the cloud chamber design provides high sensitivity, while simultaneously maintaining a high level of discrimination with respect to false alarms. The VEWFDS is intended to detect the incipient stage of a fire and provide an alarm to operations personnel at the very earliest warning levels, before any resulting damage to the surrounding components.

Each individual detection zone layout connected to the VEWFDS (four zones maximum at HNP) will be designed specifically for that zone configuration, with each air sampling piping/tubing layout designed based on the requirements and limitations from the vendor's hydraulic calculations for air flow requirements. This will assure balanced air flow and adequate air transport times in accordance with the design requirements.

During initial setup, the licensee will determine the system alert and alarm settings for each detection zone as part of the installation and pre-operational testing of the VEWFDS. Guidance from NFPA 72 and the VEWFDS equipment manufacturer will be used to establish the alert and alarm thresholds during final commissioning of the system. Once established, the licensee will maintain the alert and alarm settings under the existing plant configuration control process (i.e.,

the engineering change process), which nominally includes all program change controls in addition to the engineering calculation justification process.

The licensee stated that the VEWFDS detectors will all be connected to a new fire alarm control panel (FACP) located in the auxiliary relay room adjacent to the main control room (MCR). The new FACP will be connected to the MCR annunciators such that indications of problems with the detection system, very early warning alerts, and actual fire condition alarms will be identified and available to the operators in the control room. Control room operators will respond to the OJ;J;ICIAI:: US!!! O~II::¥ S!!!CURIT¥ R!!!I::AT!!!I;;) 1~IJ;ORMA:TIO~1

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34. Generic Letter 1986-10, "Implementation of Fire Protection Requirements," dated April 24, 1986, Supplement 1, "Fire Endurance Test Acceptance Criteria for Fire Barrier Systems Used to Separate Safe Shutdown Trains Within the Same Fire Area," dated March 25,1994, U.S. Nuclear Regulatory Commission, Washington, DC

35. NEI 00-01, "Guidance for Post-Fire Safe Shutdown Circuit Analysis," Revision 2, Nuclear Energy Institute, Washington, DC, December 2007 [ADAMS Accession No. ML091770265]

36. NEI 00-01, "Guidance for Post-Fire Safe Shutdown Circuit Analysis," Revision 1, Nuclear Energy Institute, Washington, DC, January 2005 [ADAMS Accession No. ML050310295]

37. Letter from Marlayna Vaaler, U.S. Nuclear Regulatory Commission, to Christopher L. Burton, Progress Energy, dated August 6, 2009, "Shearon Harris Nuclear Power Plant, Unit 1 - Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, 'Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants' (TAC No.

MD8807)" [ADAMS Accession No. ML092170715]

38. Letter from Marlayna Vaaler, U.S. Nuclear Regulatory Commission, to Christopher L. Burton, Progress Energy, dated January 14, 2010, "Shearon Harris Nuclear Power Plant, Unit 1 - Second Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, 'Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants' (TAC No. MD8807)" [ADAMS Accession No. ML100130254]

39. Draft NEI 04-06, "Guidance for Self-Assessment of Circuit Failure Issues," Revision L, Nuclear Energy Institute, Washington, DC, March 2005 [ADAMS Accession No. ML050760219]

40. Regulatory Issue Summary 2004-03, "Risk-Informed Approach for Post-Fire Safe-Shutdown Circuit Inspections," Revision 1, U. S. Nuclear Regulatory Commission, Washington, DC, dated December 29,2004 [ADAMS Accession No. ML042440791]

41. NUREG-1852, "Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire," U. S. Nuclear Regulatory Commission, Washington, DC, October 2007 [ADAMS Accession No. ML073020676]

42. NFPA 72, "National Fire Alarm and Signaling Code," 2007 Edition, National Fire Protection Association, Quincy, MA

43. NFPA 76, "Standard for the Fire Protection of Telecommunications Facilities," 2009 Edition, National Fire Protection Association, Quincy, MA

44. NUREG/CR-6850, "EPRI/NRC-RES, Fire PRA Methodology for Nuclear Power Facilities," Volumes 1 and 2, U. S. Nuclear Regulatory Commission, Washington, DC, September 2005 [ADAMS Accession Nos. ML052580075 (volume 1) and ML052580118 (volume 2)]

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HNP NFPA 805 Safety Evaluation Attachment C: Fire Risk Evaluation Tables Attachment C4: Table 3.4-4, V&V Basis for Fire Model Calculations of Other Models Used at HNP Calculation Application at HNP V&V Basis NRC Staff Evaluation of Acceptability The method used for calculating flame spread rate is a departure from NUREG/CR-6850, where a methodology is employed that is dependent on the thermo-physical properties of specific heat, thermal conductivity, density, and "ignition temperature," as well as the phenomenological values of incident heat flux from the flame to the fuel (cable) surface and the "heated fuel distance" (which is selected by engineering judgment).

Because the thermo-physical properties for Kerite fire-rated cables are not available in published sources, nor is alternate research available, an empirically-based method with the single variable of heat release rate Flame Spread Rate was selected to calculate the flame spread rate.

NUREG-1805 Along a Cable Tray

NUREG-1824 NUREG-1805 and IMC 0609 data was used, in conjunction with (HNP-M/ horizontal flame spread correlations as documented in Lee, 1985, to MECH-1195) correlate bench-scale data to moderate-scale tests in terms of an area Lee, 1985 spread rate for a single cable tray array.

Since (1) the V&V basis for the use of NUREG-1805 is NUREG-1824 and the licensee stated that the correlation was applied within the limits of its applicability, and (2) the V&V of the correlations used for flame spread rate along a cable tray in the fire modeling calculations as published by Lee were subjected to a peer review, published in a widely recognized peer-reviewed journal article or in a conference report, and were applied within the limits of their applicability, the NRC staff finds use of this correlation in the HNP application acceptable.

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HNP NFPA 805 Safety Evaluation Attachment C: Fire Risk Evaluation Tables References for Table 3.4-4

1. NUREG-1805, "Fire Dynamics Tools (FDT S ) Quantitative Fire Hazard Analysis Methods for the U. S. Nuclear Regulatory Commission Fire Protection Inspection Program," U.S. Nuclear Regulatory Commission, Washington, DC, December 2004.

2. NUREG-1824, "Verification & Validation of Selected Fire Models for Nuclear Power Plant Applications," U.S. Nuclear Regulatory Commission, Washington, DC, May 2007.

3. NUREG/CR-6850, "EPRI/NRC-RES Fire PRA Methodology for Nuclear Power Facilities," U.S. Nuclear Regulatory Commission, Washington, DC, September 2005.

4. Peacock, R.D., Jones, W.W., Reneke, P.A., and Forney, G.P., "CFAST - Consolidated Model of Fire Growth and Smoke Transport (Version 6) User's Guide," NIST Special Publication 1041, National Institute of Standards and Technology, Gaithersburg, MD, December 2005.

5. Yokoi, S., "Study on the Prevention of Fire Spread Caused by Hot Upward Current," Report Number 34, Building Research Institute, Tokyo, Japan, 1960.

6. Lee, B.T., "Heat Release Characteristics of Some Combustible Fuel Sources in Nuclear Power Plants," NBSIR 85-3195, U.S. Department of Commerce, National Bureau of Standards, Gaithersburg, MD, July 1985 (Attachment 3 to ADAMS Accession No. ML013390436).

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HNP NFPA 805 Safety Evaluation Attachment C: Fire Risk Evaluation Tables Attachment C5: Table 3.4-5, Resolution of Fire Risk Assessment Requests for Additional Information NRC Staff Evaluation of RAI Response RAI Subject Subject Area and Basis for Acceptability LAR Attachment X, Page X-45:

The response to F&O FSS-A2-2 states that "F&O FSS-A2-2 The focused scope peer review verified the source of the suggests that the screening approach (referring to the methodology for determining the time necessary to reach a approach for determining time for reaching a damaging hot damaging hot gas layer temperature, as well as the basis for the gas layer temperature) is incorrect and may be very NUREG/CR 15.0 conclusion of correctness and non-over-conservatism in the conservative. It is concluded after a review of the calculations 6850 Deviations screening approach.

for determining time for hot gas layer reaching damaging temperatures that the approach is correct."

This resolves the NRC staffs concern.

Provide the basis for this conclusion of correctness and non-over-conservatism.

LAR Attachment X, Page X-46: The licensee stated that MCR abandonment would be expected before all functions would be lost, and that abandonment is time From the response to F&O FSS-B1-1, it appears that a pre-existing critical since if it occurs too early there could be adverse risk HNP assumption that no spurious actuations occur within 10 minutes implications and if it occurs too late, functions could be lost and not of a fire may have implicitly been retained in the MCR abandonment recovered.

study, and that this assumption was not carried into the Fire PRA.

The licensee indicated that no credit is taken for abandoning the If this assumption was implicitly retained in the MCR abandonment study, discuss how the MCR abandonment analysis for the Fire PRA MCR except due to environmental conditions inside the MCR. For compensates for this. the loss of environmental conditions, a 0.1 probability is assumed.

Main Control 16.0 It also appears that the analysis for MCR abandonment addresses Accordingly, the HNP Fire PRA model should be conservative in Room only degradation/loss of functions due to fire effects within the MCR. that no alternate means of monitoring, activation, etc., of potentially available components would be credited upon loss of the MCR Discuss how degradation/loss of functions in the MCR due to fire function in scenarios for which the Fire PRA does not take credit for outside the MCR (even if there are no resulting environmental fire MCR abandonment.

effects within the MCR) has been addressed. Has abandonment of the MCR under these conditions been considered?

Effectively, this implies a maximum penalty (conservatism) given In addition, if enough spurious actuations occurred within the first 10 the conditions that would render the MCR "useless."

minutes to cause degradation/loss of functions within the MCR, would non-procedural MCR abandonment be considered? This resolves the NRC staffs concern.

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HNP NFPA 805 Safety Evaluation Attachment C: Fire Risk Evaluation Tables Attachment C5: Table 3.4-5, Resolution of Fire Risk Assessment Requests for Additional Information NRC Staff Evaluation of RAI Response RAI Subject Subject Area and Basis for Acceptability HNP-F/PSA-0079: Section 5.4.2.1 states that "after the HEAF, a source fire of 69 kilowatts (kW) is assumed to propagate to secondary combustibles."

Section M.6.1 of NUREG/CR-6850 states that for the ensuing fire after the energetic phase, a generic frequency for HEAFs should be assigned and apportioned using the location and ignition source weighting factors.

Section G.7 gives the following guidance for HEAF sources:

(1) 4160V Switchgear: The fire in the switchgear will remain The licensee has provided a reasonable justification for limiting the confined to a single bundle and the distribution with 65 kW and HRR from the secondary fire after the HEAF to the 75 percentile 200 kW as the 75th and 98th percentiles can be assumed if the 5.15 value of 69 kW assuming qualified cable. Fire Modeling cables are qualified; (2) 480V MCC: MCCs of this type with qualified cable are This resolves the NRC staff's concern.

considered to satisfy the criteria established for a 65 kW HRR as the 75th percentile. In contrast, if the cabinet has unqualified cable, and assuming a closed door, a value of 220 kW would be assigned as the 75th percentile.

(Note that HNP uses a 6.9kV switchgear; however, the guidance above is still applicable)

Please provide the basis for the apparent a priori limiting of the propagation of a source fire from an HEAF to the 69 kW HRR (i.e., versus 200 kW).

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HNP NFPA 805 Safety Evaluation Attachment C: Fire Risk Evaluation Tables Attachment C5: Table 3.4-5, Resolution of Fire Risk Assessment Requests for Additional Information NRC Staff Evaluation of RAI Response RAI Subject Subject Area and Basis for Acceptability HNP-F/PSA-0079: Attachment 4 includes Table 3, "Main Control Board (MCB) Fire Consequence Characterization - Successful Fire Suppression." The following minimum groupings appear to generate a CCDP equal to 1.0 (or close ~at th.eir.is.k* *;

significance merits further analysis): (1) _ ; (2).

and (3) The licensee explained that there is consistency between the citing of CCDPs equal to 1.0 in Table 3 and Table 10 of Attachment 4 to Main Control 5.20 However, there are other "non-minimal" groupings contained in HNP-F/PSA-0079.

Room Table 3 (Le., and ), each of which includes at least one cabinet that is also associated with the higher risk This resolves the NRC staffs concern.

significance groupings.

Given the discussion above, please specify which main control room groupings of MCBs actually result from the analyses associated with Table 3.

HNP-F/PSA-0079: Section 4 of Attachment 4 states, in part, that combining the frequency terms for transient combustibles yields:

5.7E-4 x 1.0E-2 x 2.63E-2 = 1.50E-7 per year.

It appears that an MCR transient ignition frequency of 5.7E-4 per The licensee indicated the reference calculation for the updated year is assumed. However, this value is actually the conditional MCR transient ignition frequency as a justification, showing that it is probability of damage given a fire event, per Figure L-1 of bounded by the transient ignition frequency value previously used.

NUREG/CR-6850. Main Control 5.21 While the NRC staff concern is resolved, the staff expects that the Room Bin 7 of Table 6-1 in NUREG/CR-6850 gives the transient ignition licensee will rectify the anomaly post-transition such that the frequency in the control/auxiliary/reactor bUilding as Fire PRA will employ the correct value for the MCR transient 3.9E-3 per year. ignition frequency.

Accordingly, please revise these calculations, if appropriate, using the correct NUREG/CR-6850 value, or prOVide the basis for the value currently assumed for transient ignition frequency.

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Fire Areas Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Deterministic Compliance with NFPA 805 Section 4.2.3 Automatic Suppression Required System? Detection Required System?

Detection Fire Area Fire Zone Zone Description Suppression Provided?

Provided? S D E EC R C S D E EC R C No No No No - No No Yes (T)

No No Yes ESR 99 00395 No No No Yes No No No No No No No Yes No No Yes Yes No No No No No No No Yes No No (T)

No No No No - No No Yes No No No - No No

-- ... .... .... No No No No No No No No No No No No Yes Yes No No No No No No No No No No Legend:

S Abbreviation for Separation Systems required for NFPA 805 Chapter 4 separation criteria D Abbreviation for Deviation Systems required for NRC approved exemptions and deviations E Abbreviation for EEEEs Systems required for the acceptability of existing compliance strategies using EEEEs (Left column documents if required, right column documents the engineering change (EC))

R Abbreviation for Risk Systems determined to be of 'higher significance' by the NFPA 805 Expert Panel C Abbreviation for Change Evaluation Systems required to maintain an adequate balance of defense-in-depth for change evaluations T Abbreviation for Thermal Detection While performing a review of Fire Areas , the NRC staff identified an issue that required the licensee to provide additional information in order to adequately demonstrate compliance with specific portions of the applicable NFPA 805 requirements.

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FireArea_ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Deterministic Compliance with NFPA 805 Section 4.2.3 I

I Automatic Suppression Required System? Detection Required System?

Fire Area I Fire Zone I Zone Description I Suppression Detection I Provided?

Provided? S D E R C S I D I E I R I C

-- 1 1 1 No No I No No 1 No No 1 No No 1 No No 1 No No 1 No No 1 No No I

1 No No 1

1 No No

- 1 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No

- I 1 No 1 No 1 No 1 No 1 No I No 1 No 1 No 1 No I No 1 No 1 No

- 1 1 No 1 No I No 1 No I No 1 No I No 1 No 1 No 1 No 1 No I No

-- _-I 1 1

No No 1

1 No No I

1 No No 1

1 No No I No 1 No 1

I No No 1

1 No No 1

1 No No

- - 1 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No

- -_I 1 1 No 1 No 1 No I No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No

- 1 No 1 No I No

- 278 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No 1 No OJ;j;ICIAb YSEi O~JbY SEiCYRITY REibATEilJ I~Jj;ORMATIO~J

Fire Area _ Attachment 0: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 While performing a review of Fire Area _ , the NRC staff identified several issues that required the licensee to provide additional information in order to adequately demonstrate compliance with specific portions of the applicable NFPA 805 requirements. By letter dated August 6, 2009, the staff requested additional information regarding a number of regulatory and technical issues pertaining to adequately demonstrating that performance-based compliance has been met in accordance with NFPA 805 Section 4.2.4 (in particular, RAI 3-26 and RAI 3-27 of the associated letter address these concerns).

That staff requested that the licensee explain why detection was required for defense-in-depth in this fire area, while suppression was not. In its supplemental letter dated August 28, 2009, the licensee responded by stating that the original safe shutdown strategy for this fire area was to provide 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months protection in the form of MT' fire wrap material for one train of safe shutdown equipment in the area. Fire detection is also required in the fire area for defense-in-depth. However, as outlined above, the VFDR for this fire area is that the MT' ERFBS is rated for 115 minutes (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 55 minutes) rather than the required 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months . Consequently, the degraded MT' fire wrap has been evaluated by the licensee with respect to risk and found to be acceptable. This acceptance is based on the small impact to the non-suppression probability (between 115 and 180 minutes).

The NRC staff finds this acceptable based on the information provided in the LAR and associated RAI response, which states that detection is required for defense-in-depth in order to ensure that manual firefighting efforts are initiated and control of the fire is achieved within the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , 55 minute rating of the MT' fire wrap. Without detection in the room, this cannot be assured. Thus, the staff accepts that defense-in-depth is maintained without a suppression system based on the presence of the MT' fire barrier, and the available detection in the room providing early warning such that fire suppression and control can be achieved manually.

The staff also asked the licensee to discuss the disposition of potential spurious operation of the seal injection filter backwash valves by de-energizing several breakers. The staff requested the licensee describe the administrative controls to be used when the valves needed to be operated while the plant was at power, resulting in the valves being susceptible to spurious operations.

In its supplemental letter dated August 28, 2009, the licensee responded by stating that the modification to change the circuit breaker positions to open had been completed. The only time the seal injection filter backwash valves will be energized and susceptible to fire-induced spurious operation is during filter backwash operations. This is a short duration evolution and the normal configuration will be restored immediately following the evolution.

The NRC staff finds this acceptable based on the information provided in the LAR and associated RAI response, which states that the licensee will use administrative controls to ensure that the seal injection backwash valves will be maintained closed with power removed except for the short duration time when filter backwash operations are required, and also states that procedures have been changed to require restoration of the required state of the valves (closed with power removed) immediately upon completion.

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Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables) manual actions credited

,and_ _ are required to maintain RCS make up.

Based on the proposed modification Planned modification to Because this is an alternate shutdown area, to install an alternate seal injection 350 install an alternate seal these actions are allowable under the system, the NRC staff finds this VFDR injection system.

current licensing basis and a change acceptable.

evaluation is not required.

However, due to time constraints, the actions are not feasible.

The fire risk evaluation for this fire area determined that the additional risk incorporated because of these VFDRs is zero.

Recovery Actions (RAs)

Component 10 Component Name Licensee's Description of Action

- SG

Blowdown Flow Control Valve De-energize _

- 312 at , in Fire Zone _

in order to fail the valve closed.

O~~ICIAb lJili Q~JbY iliCIJRITY RlibATIiO I~J~ORMATIO~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 Automatic Suppression Required System? Detection Required System?

Detection Fire Area Fire Zone Zone Description Suppression Provided?

Provided? S D E R C S D E R C Yes 1 Yes Yes Yes No No No No No No No No (I, AS) (I) (I, AS) (I, AS)

Yes Yes Yes Yes Yes 2 No Yes No No No No No (I, AS) (I) (I, AS) (I, AS)

Legend:

S Abbreviation for Separation Systems required for NFPA 805 Chapter 4 separation criteria D Abbreviation for Deviation Systems required for NRC approved exemptions and deviations E Abbreviation for EEEEs Systems required for the acceptability of existing compliance strategies using EEEEs R Abbreviation for Risk Systems determined to be of 'higher significance' by the NFPA 805 Expert Panel C Abbreviation for Change Evaluation Systems required to maintain an adequate balance of defense-in-depth for change evaluations I Abbreviation for Ionization Detection AS Abbreviation for Air Sampling Detection While performing a review of Fire Area _ , the NRC staff identified several issues that required the licensee to provide additional information in order to adequately demonstrate compliance with specific portions of the applicable NFPA 805 requirements. By letters dated August 6, 2009, and January 14, 2010, the staff requested additional information regarding a number of regulatory and technical issues pertaining to adequately demonstrating that performance-based compliance has been met in accordance with NFPA 805 Section 4.2.4 (in particular, RAI 3-20, RAI 3-23n, RAI 3-28, RAI 3-30, RAI 3-31, RAI3-62, and RAI 3-72 of the associated letter address these concerns).

RAI 3-20 requested that the licensee clarify how the RCS inventory control, boration, and RCP seal integrity functions are being achieved for each fire area, how the availability of at least one charging pump is being assured given the potential for pump damage due to fire, and for which fire areas the new plant equipment is being credited. In its supplemental letter dated August 28, 2009, the licensee responded by stating that on a fire area basis, the means of ensuring that RCS inventory control, reactivity control (boration), and the RCP seal integrity functions are being achieved is detailed in the plant safe shutdown calculation.

A VEWFDS is being installed to monitor risk significant control panels in order to increase defense-in-depth.

2 An automatic suppression system has been provided in the per the approved deviation.

- 317 Of=f=IChA.b Y~1i O~Jb¥ SIiCYRIT¥ RlibATIiO I~Jf=ORMATIO~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 Variations from the Deterministic Requirements (VFDRs)

HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

Engineering change request (ECR) 1876 was generated since no EC addresses this specific issue. In general, portable lighting will be used to perform actions where fixed lighting is not provided.

However, the manual actions Based on the proposed modification in Fire Area will associated with EC 68645, which

_ _access path to Fire Area no longer be required renders the manual action requiring 10 ----

pending completion of is not adequately lighted. the emergency lighting as no longer EC 68645, which will allow necessary, the NRC staff finds this

. .be credited instead VFDR acceptable.

of (and its associated manual actions).

In addition, EC 67742 is complete, which renders the manual action to de-energize the smoke purge fan as no longer necessary.

EC 68645 is removing the The manual action credited to de-energize cables for from the fire area, such that a flow Based on the proposed modification and open _ is required to establish path of water to the. SG is associated with EC 68645, which the credited path of auxiliary feedwater.

assured. All other conditions results in _ remaining free of 128 for using the. SG for decay fire damage given a fire in this area, Under the current licensing basis, this heat removal are met for this the NRC staff finds this action is considered unallowable and a area. Therefore, will VFDR acceptable.

change evaluation is required. no longer be required to maintain hot standby.

- 341 G~~ICI,L\b b1S~ G~Jb¥ S~Gblj;lIT¥ j;l~b,L\T~Q I~J~Gj;lIVlATIO~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

EC 58779 evaluated the Based on the performance-based availability of diesel evaluation (change evaluation) backed liahting for the performed, which documents that room. One Conduit _ will not be within the con~)was zone of influence of a significant

~on is applied to found to be not protected.

ignition source once the VEWFDS is

_ in this fire area.

installed in the ACP, the NRC staff 131 A change evaluation for finds this VFDR acceptable.

The concern is that emergency lighting for this conduit was performed the _ room might be lost. which showed that this conduit is not in the ZOI of Revision of HNP-M/MECH-1124 to a significant ignition source incorporate the revised change based on the addition of evaluation is an implementation item incipient detection in the (SE Section 2.9; Item 16).

ACP per EC 69501.

Based on the performance-based evaluation (change evaluation)

HNP-M/MECH-1124 will performed, which documents that be revised to document a Cable _ will not be within the change evaluation which zone of influence of a significant This fire area credits hot standby actions to shows that the affected ignition source once the VEWFDS is manually de-energize pressurizer heaters 374 cable is not in the ZOI of a installed in the ACP, the NRC staff that have the potential to operate spuriously significant ignition source finds this VFDR acceptable.

due to cable damage.

based on the addition of incipient detection in the Revision of HNP-M/MECH-1124 to ACP per EC 69501. incorporate the revised change evaluation is an implementation item (SE Section 2.9; Item 16).

The fire risk evaluation for this fire area determined that the additional risk incorporated because of these VFDRs is zero.

- 342 Qj;j;ICI.A.b: USIi Q~Jb¥ SIiCYRIT¥ RlibAflibl I~Jj;OR~ATIQ~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 Variations from the Deterministic Requirements (VFDRs)

HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

These cables are not within the ZOI of a fixed ignition source. Accordingly, the associated MT' barrier is acceptable because it is not subject to fire damage.

The MT' ERFBS is credited for 115 minutes (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and 55 minutes), in lieu of the 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months necessitated by the Based on (1) the MT' ERFBS fire deterministic requirements.

barrier not being within the zone of The MT' ERFBS is credited as a 3-hour The risk evaluation for plant influence of a fixed ignition source, fire barrier in this area, but is not a fully changes in this area was (2) the barrier fire duration being rated 3-hour fire barrier.

assessed quantitatively for based on appropriate testing, (3) the acceptability using the 30 proposed modifications to bring the The change evaluation process is delta-CDF and delta-LERF fire barrier up to the tested determining whether the installed fire criteria from NEI 04-02, configuration, and (4) the calculated barrier provides an adequate level of Section 5.3.5, and RG 1.205. change in risk meeting the associated protection for the hazards in the fire area .

acceptance requirements. the NRC The associated change in risk staff finds this VFDR acceptable.

is below the RG 1.205 acceptance criteria. As such, the change in risk due to the MT' ERFBS reduced rating has a negligible contribution to the change in CDF results.

This is due to the difference in the probability of non suppression between 115 min. and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months being low.

- 350 or;r;ICIAb leJiSE ONbY iSECIeJRITY REbATE!;) I~Jr;ORMATIO~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open I VFDR Description I Component Disposition NRC Evaluation Item No. (Cables)

The delta-CDF and (continued) delta-LERF results are lower than the threshold which requires NRC notification per

- CONTINUED the standard fire protection license condition included in

- CONTINUED RG 1.205. Based on (1) the MT' ERFBS fire barrier not being within the zone of A MT' ERFBS is credited as a 3-hour fire The change process ta~ets influence of a fixed ignition source,

( f d) I barrier in this area, but is not a fully rated associated with the MT (2) the barrier fire duration being con mue 3 - h our f Ire barner.

. ERFBS are not within the based on appropriate testing, (3) the zone of influence of 30 significant ignition sources proposed modifications to bring the I The change evaluation process is and so are considered to be fire barrier up to the tested evaluating whether the current fire barrier free of fire damage, and configuration, and (4) the calculated provides an adequate level of protection for therefore considered change in risk meeting the associated the hazards in the fire area.

acceptable "as-is." acceptance requirements, the NRC staff finds this VFDR acceptable.

EC 69765 will modify the

-

MT' ERFBS consistent with the tested configuration for the fire resistance assumed.

These cables (and associated instrument lines) are not within the zone of influence of a significant ignition source. Based on the target relationship to the I Cir_ Ar__ I I zone of influence of the ignition 203 I source(s), the NRC staff finds this The existing deviation does not take into VFDR acceptable.

account that there is less than 20 feet of seoaration between the mechanical end of umo _ and the closest pump.

- 351 -

OFFICIAb LJ£I!! O~JbY £I!!CLJ~ITY RiibATI!!Q I~JFO~MATIO~J

Fire Area _ Attachment 0: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

Cables _ and _ are This fire area contains cables for both not within the zone of

_ and _ , the RWST supply influence of an ignition source.

valves to the CSIP.

Because the cables are not The hot standby manual action credited for subject to fire damage,

_ is required to establish a flow path Valve_will be Based on the target relationship to the from the RWST to the common charging available when required. zone of influence of the ignition 115 pump suction header. This flow path is source(s), the NRC staff finds this required for operation of the credited Cables _ and _ are VFDR acceptable.

source of borated water to the RCS. not within the zone of influence of a significant ignition source.

Under the current licensing basis, this action is considered unallowable and a Accordingly, V a l v e _

change evaluation is required. remains available if power is lostto_.

Multiple spurious actuations could result in This scenario requires cross-connecting the chilled water headers, multiple spurious placing the system at risk.

actuations of the listed valv~.g.,_ Based on the target relationship to the This fire area credits a hot standby action to and_). zone of influence of the ignition 116 split the two chilled water headers source(s), the NRC staff finds this (Exception ).

These cables are not VFDR acceptable.

within the zone of This action is considered unallowable influence of a significant (pending additional research) and will ignition source.

require a change evaluation.

- 354 Of=f=ICIAb YSc O~Jb¥ SEiCYRIT¥ REibATEi(;) I~Jf=QRMATIQ~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open I VFDR Description I Component I Disposition I NRC Evaluation Item No. (Cables) 370 The potential exists for loss of RCP seal integrity in this fire area due to the simultaneous loss ~al I cooling (Exception ).

EC 70350 will provide an additional source of RCS makeup/seal injection in Based on the proposed modification to install an alternate seal injection system, the NRC staff finds this VFDR the event water flow to the acceptable.

This issue is being addressed in the seals is interrupted.

change evaluation for this fire area.

Exception is Further analysis shows that applied to and addresses the the. train water and iIiiIiiiICYis service potential that a fire in Fire Area _ Based on (1) the installed HEMYC' can disable _ and cause a loss of available. The cables for ERFBS, (2) the proposed the credited emergency service water train. tare wrapped with modifications to bring the fire barriers HEMYC ERFBS in conduits up to the tested configuration, and 150 and I A buffer area review determined that (3) the target relationship to the zone separation is less than 20 feet from the These conduits are not within of influence of the ignition source(s),

redundant train equipment. the zone of influence of a the NRC staff finds this significant ignition source, VFDR acceptable.

This issue is being addressed in the and the HEMYC' ERFBS is change evaluation for this fire area. acceptable.

348 The potential exists for loss of RCP seal integrity in this fire area due to the simultaneous loss ~al I cooling (Exception ).

EC 70350 will provide an additional source of RCS makeup/seal injection in Based on the proposed modification to install an alternate seal injection system, the NRC staff finds this VFDR the event water flow to the acceptable.

This issue is being addressed in the I I seals is interrupted.

change evaluation for this fire area.

- 357 OJ;j;ICIAb Y£Ei Q~Jb¥ £EiGY~IT¥ ~EibATEiQ I~Jj;O~~4ATIO~J

Fire Area _ Attachment 0: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

The change evaluation demonstrated that the HEMYC' ERFBS as tested provide adequate protection, as detailed below.

The HEMYC' ERFBS is credited for 25 minutes, in lieu of the 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months necessitated by the deterministic requirements.

The risk evaluation for plant changes in this area was Based on (1) the barrier fire duration The HEMYC' ERFBS credited in this area assessed quantitatively for being based on appropriate testing, is not a fully rated 1-hour fire barrier.

acceptability using the (2) the proposed modifications to delta-CDF and delta-LERF bring the fire barrier up to the tested 317 The change evaluation process is criteria from NEI 04-02, configuration, and (3) the calculated determining whether the installed fire Section 5.3.5, and RG 1.205. change in risk meeting the associated barriers provide an adequate level of acceptance requirements, the NRC protection for the hazards in the fire area. The associated change in risk staff finds this VFDR acceptable.

is below the RG 1.205 acceptance criteria. As such, the chan~e in risk due to the HEMYC ERFBS reduced rating has a negligible contribution to the change in CDF results.

This is due to the difference in the probability of non suppression between 25 minutes and 60 minutes being low.

- 388 Gj;j;ICIAb lJili G~Jb¥ iliGIJRIT¥ RlibATcg I~Jj;GRMATIQ~J

Fire Area _ Attachment 0: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

The change evaluation showed that the affected cable is not within the zone of influence of a significant ignition source.

EC 71147 is installing Meggitt cable down past the top row of breakers in order to limit the potential for spurious actuation of the valve's breaker and associated MCC stack.

Based on (1) the installed Meggitt Fire modeling demonstrated cable, (2) the analysis performed by The hot standby manual action credited for that any non-fire rated cable in the licensee which demonstrates that

_ is required to establish a flow path the top cable run and in the first row of the MCC could be only fires in the breaker cubicle or the for charging pump minimum-flow.

damaged. This is documented column below the breaker can cause spurious actuation of _ , (3) the in a site-specific calculation.

This flow path is required for the credited 373 Thus, this component is creation of a transient combustible train. charging pump. susceptible to spurious exclusion zone, (4) a calculation actuation only from a fire in its demonstrating that a chiller lube oil Under the current licensing basis, this breaker cubicle or the column below the breaker.

fire will not create a hot gas layer, and action is considered unallowable and a (5) the commitment to install the change evaluation is required.

To reduce the probability that a alternate seal injection system, the transient could impact the NRC staff finds this VFDR acceptable.

cable, a transient combustible exclusion zone was created.

In addition, a calculation documents that a chiller lube oil fire in Fire Area will not result in an HGL.

EC 70350 will provide seal injection and RCS makeup if the running CSIP is damaged.

- 391 OJ;j;ICIAb blSIi O~lb¥ ~IiCURIT¥ RlibA:TIiQ 1~Ij;ORMATIO~1

Fire Area _ Attachment 0: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

The change evaluation showed that the affected cable is not within the zone of influence of a fixed ignition source.

The change evaluation will be updated to show that the cable is not within the zone of influence of a significant ignition source.

EG 71147 is installing Meggitt cable down past the top row of Based on (1) the installed Meggitt breakers in order to limit the potential for spurious actuation cable, (2) the analysis performed by of the valve's breaker and the licensee which demonstrates that The hot standby manual action credited for associated MGG stack. only fires in the breaker cubicle or the

_ is required to establish a flow path column below the breaker can cause for charging pump minimum-flow. Fire modeling demonstrated that any non-fire rated cable in the spurious actuation of _ . and (3) the commitment to install the top cable run and in the first row This flow path is required for the credited 142 of the MGG could be damaged. alternate seal injection system, the train. charging pump. This is documented in a NRC staff finds this VFDR acceptable.

site-specific calculation. Thus, Under the current licensing basis, this this component is susceptible to spurious actuation only from a Updating the change evaluation to action is considered unallowable and a fire in its breaker cubicle or the document that Cable _ is not change evaluation is required. column below the breaker. within the 201 of a significant ignition To reduce the probability that a source is an implementation item transient could impact the cable, (SE Section 2.9; Item 21).

a transient combustible exclusion zone was created.

In addition, a calculation documents that a chiller lube oil fire in Fire Area will not result in an HGL.

EG 70350 will provide seal injection and RGS makeup if the running GSIP is damaged.

- 392 OJ;j;ICIAb IJ~Ei O~Jb¥ ~EiCY~IT¥ ~EibATEig I~Jj;O~~4,c\TION

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables) the top row of the MCC, and by running Meggitt cable down past the top row of breakers such that the cables are not at risk except for a single breaker.

Fire modeling demonstrated

- CONTINUED that any non-fire rated cable in the top cable run and in the Exception ~ addresses the first row of the MCC could be - CONTINUED

-.a.

potential for to spuriously open, which damaged. This is could fill the pressurizer, thereby resulting in a documented in a site-specific Based on (1) the installed Meggitt solid Res. calculation. cable, (2) the relocation of the A new manual action is proposed to mitigate the breakers out of the top row of the Thus, one of the MOV circuits spurious actuation. ARs 134694 and 137435 MCC, (3) the fire model analysis (continued) will remain free of fire address this issue. damage in the event of a fire performed by the licensee, (4) the inMCC results of the change evaluation 97 Because this action is not associated with the concluding that the change is credited train, it is considered to be for the fire acceptable from a risk, defense-in The change evaluation also affected train, and would therefore be considered allowable under the current licensing basis. showed that this configuration depth, and safety margin standpoint, provides adequate defense and (5) the commitment to install the Thermal barrier cooling is available, such that the in-depth and safety margin. alternate seal injection system, the running charging pump could be secured in order NRC staff finds this VFDR acceptable.

to prevent solid plant conditions, thereby allowing Should either _ or_

more ti me to close _ . spuriously open, the running CSIP can be secured. The spuriously opened valve could then be manually closed using portable lighting.

EC 70350 will provide an additional source of RCS makeup/seal injection.

- 410 -

OlPlPlGIAb USEi Q~Jb¥ SEiGIJRIT¥ REibATEiQ I~JIPQRMATIQ~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

(continued) influence of a fixed ignition - CONTINUED

- CONTINUED source and will remain free of fire damage. Based on (1) the relationship between (continued)

~ issue in this area is closing either the target(s) and the zone of influence In addition, EC 70350 will

_ _ or _ in order to prevent of the ignition sources and (2) the 170 provide another source of introduction of the VCT cover gas to the RCS makeup and seal commitment to install the alternate suction of the _ pumps. injection that is not seal injection system, the NRC staff dependent on the CSIP. finds this VFDR acceptable.

The change evaluation demonstrated that the MT' ERFBS as tested provide adequate protection. The affected cables are not within the zone on influence of a fixed ignition source.

Based on (1) the MT' ERFBS fire Accordingly, the associated MT' barrier is acceptable barrier not being within the zone of The MT' ERFBS is credited as a 3-hour because it is not subject to influence of a fixed ignition source, fire barrier in this area, but is not a fully fire damage. (2) the barrier fire duration being rated 3-hour fire barrier.

based on appropriate testing, (3) the 316 The MT' ERFBS is credited proposed modifications to bring the The MT' ERFBS does not provide a for 115 minutes (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and fire barrier up to the tested 3-hour f~ri~rotectionof power 55 minutes), in lieu of the configuration, and (4) the calculated Cables~, and _ in 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months necessitated by the change in risk meeting the associated Conduit deterministic requirements.

acceptance requirements, the NRC staff finds this VFDR acceptable.

The risk evaluation for plant changes in this area was assessed quantitatively for acceptability using the delta-CDF and delta-LERF criteria from NEI 04-02, Section 5.3.5, and RG 1.205.

- 416 Qj;j;ICIAb YS~ O~Jb¥ S~CYRIT¥ R~bAT~Q I~Jj;ORMATIO~J

Fire Area _ Attachment 0: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

The associated change in risk is below the RG 1.205 acceptance criteria. As such, the change in risk due to the MT' ERFBS reduced rating has a negligible contribution to the change in CDF results.

This is due to the difference in the probability of non suppression between 115 . CONTINUED*

min. and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months being low.

CONTINUED*

The delta-CDF and Based on (1) the MT' ERFBS fire delta-LERF results are lower barrier not being within the zone of The MT' ERFBS is credited as a 3-hour (continued) than the threshold which influence of a fixed ignition source, fire barrier in this area, but is not a fully (continued) requires NRC notification per (2) the barrier fire duration being rated 3-hour fire barrier.

the standard fire protection based on appropriate testing, (3) the 316 license condition included in proposed modifications to bring the The MT' ERFBS does not provide a RG 1.205. fire barrier up to the tested 3-hour protection of power configuration, and (4) the calculated Cables , , and _ in The change process ta~ets change in risk meeting the associated Conduit . associated with the MT acceptance requirements, the NRC ERFBS are not within the zone of influence of staff finds this VFDR acceptable.

significant ignition sources and so are considered to be free of fire damage, and therefore considered acceptable "as-is."

EC 69765 will modify the MT' ERFBS consistent with the tested configuration for the fire resistance assumed.

- 417 OFiFiICIAb Yiili O~JbY iiliCYRITY RlibATIiO I~JFiORMATIO~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 Fire Area The licensee analyzed this fire area using the fire risk evaluation approach in accordance with NFPA 805 Section 4.2.4.2, but also applied deterministic simplifying assumptions in order to credit those portions of the facility design that meet the deterministic requirements of NFPA 805 Section 4.2.3. The licensee identified the structures, systems, and components (SSCs) necessary to meet the nuclear safety performance criteria (NSPC) in this fire area.

Evaluation of Fire Suppression Effects on the Nuclear Safety Performance Criteria for Fire Area _

The licensee stated in LAR Attachment C, "NEI 04-02 Table B Fire Area Transition," that damage to plant areas and equipment from the accumulation of water discharged from sprinkler systems and hose lines is minimized by the provision of floor drainage systems. Floor water surcharge is estimated to be insignificant since excess water can overflow to adjacent areas. Runoff is directed to the floor drainage transfer tank or the storm drainage system, as detailed in HNP FSAR Section 9.3.3. Therefore, fire suppression activities are not expected to adversely affect achievement of the nuclear safety performance criteria.

Based on the information provided by the licensee in the NFPA 805 LAR, the NRC staff finds the licensee's evaluation of fire suppression effects on the NSPC acceptable because the results of the licensee's analysis indicate that fire suppression activities will not adversely impact achievement of the nuclear safety performance criteria.

Fire Area Deviations Based on the information provided in the LAR, the licensee credited three previously approved deviations from the existing fire protection requirements. The licensee utilized the process described in LAR Section 4.2.2.2.2, "Results of the Licensing Action Review," to carry forward these deviations, which requires a determination of the basis of acceptability and a determination that the basis of acceptability is still valid.

Deviation Basis and Continuing Validity Evaluation The deviation was approved based on low combustible loadi~g .in the Deviation from NUREG-0800 BTP Based on the previous staff fire area the lack of concentrations of cable trays, and the eXlstmg CMEB 9.5-1, approval of this deviation and the protectidn provided for the safe shutdown equipment.

Section C.5.b(2), for providing full statement by the licensee that the area wide suppression and basis remains valid, the NRC staff The conditions forming the basis for the previous NRC staff approval of detection. finds this deviation acceptable.

this deviation have not changed.

- 421 OJ;j;ICIAb blSIi O~JbY SIiCblRITY RlibATIiQ I~Jj;ORMATIO~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

- CONTINUED -

Fire modeling demonstrated ExcePtion~ that any non-fire rated cable addresses the potential for to in the top cable run and in spuriously open, which could fill the the first row of the MCC pressurizer, thereby resulting in a could be damaged. This is solid RCS. documented in a site-specific calculation.

A new manual action is proposed to Thus, at least two of the - CONTINUED mitigate the spurious actuation. AR 159304159304(EC 58779) and AR 80304 document (continued) three MOV circuits will remain free of fire damage Based on (1) the installed Meggitt

.a.

inadequate task lighting a t " and . . . cable, (2) the relocation of the supply in the event of a fire in the column of one breaker's breakers out of the same vertical Because this action is not associated with cubicle. stack, (3) the fire model analysis the credited train, it is considered to be for performed by the licensee which (continued) the fire affected train, and would therefore The change evaluation also demonstrates that two of the three be considered allowable under the current showed that this MOV circuits will remain free of fire 159 licensing basis. configuration provides damage, (4) the results of the change adequate defense-in-depth evaluation concluding that the change Thermal barrier cooling is not available, and safety margin. is acceptable from a risk, defense-in such that the running charging pump is depth, and safety margin standpoint, required to maintain RCP seal integrity. Should e i t h e r " , _ , and (5) the commitment to install the or _ spuriously open, alternate seal injection system, the A hydraulic study is needed to specify the the running CSIP can be time available to adequately perform this NRC staff finds this VFDR acceptable.

secured. The spuriously manual action. opened valve could then be manually closed using EC 67772 is evaluating a modification that portable lighting.

would preclude spurious operation of this valve for a fire anywhere except at the EC 70350 will provide an valve breaker. At most, one of the valves additional source of RCS

(. ., _ , or _ ) may need to be makeup/seal injection.

manually closed.

- 427 or;r;ICIAb lJSEi O~JbY SEiCURITY REibATEiQ INr;ORMATIO~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

- CONTINUED - Fire modeling demonstrated that any non-fire rated cable ExcePtion~ in the top cable run and in addresses the potential for to the first row of the MCC spuriously open, which could fill the could be damaged. This is pressurizer, thereby resulting in a documented in a solid RCS. site-specific calculation.

Thus, at least two of the - CONTINUED A new manual action is proposed to mitigate the spurious actuation. (continued) three MOV circuits will remain free of fire damage Based on (1) the installed Meggitt in the event of a fire in the cable, (2) the relocation of the supply Because this action is not associated with column of one breaker's breakers out of the same vertical the credited train, it is considered to be for cubicle. stack, (3) the fire model analysis the fire affected train, and would therefore performed by the licensee which (continued) be considered allowable under the current The change evaluation also demonstrates that two of the three licensing basis.

showed that this MOV circuits will remain free of fire 160 configuration provides damage, (4) the results of the change Thermal barrier cooling is not available, adequate defense-in-depth evaluation concluding that the change such that the running charging pump is and safety margin. is acceptable from a risk, defense-in required to maintain RCP seal integrity.

depth, and safety margin standpoint, Should either", _ , and (5) the commitment to install the A hydraulic study is needed to specify the or _ spuriously open, alternate seal injection system, the time available to adequately perform this the running CSIP can be NRC staff finds this VFDR acceptable.

manual action. secured. The spuriously opened valve could then be EC 67772 is evaluating a modification that manually closed using would preclude spurious operation of this portable lighting.

valve for a fire anywhere except at the valve breaker. At most, one of the valves EC 70350 will provide an

( _ , _ , or _ ) may need to be additional source of RCS manually closed. makeup/seal injection.

- 429 OF"F"ICIAb U~i O~lb¥ ~iCYRIT¥ Rib,t\TiQ 1~IF"ORMATIG~1

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables) column and are not located in the top row. Thus, one cubicle will remain free of fire

- CONTINUED damage in the event of a fire (continued) in the column of the other

- CONTINUED breaker's cubicle. Based on (1) the fire modeling calculation performed by the licensee (continued) 5

_ and _ could spuriously open, resulting in the loss of RWST inventory to the containment sump. .& This fire area is a transient no storage location. The change evaluation also showed that this configuration provides which demonstrates that one of the valves will remain free of fire damage, (2) the fact that the fire area has been designated as a transient combustible This issue is being addressed in the change evaluation for this fire area.

.& adequate defense-in-depth and safety margin.

In addition, EC 70350 would provide seal injection and exclusion zone, and (3) the commitment to install the alternate seal injection system, the NRC staff finds this VFDR acceptable.

RCS makeup from a source independent of the RWST.

The fire risk evaluation for this fire area determined that the additional risk incorporated because of these VFDRs is zero.

Recovery Actions (RAs)

The licensee did not identify any recovery actions required for this fire area.

Recovery Actions Credited for Defense-in-Depth (RA-DID)

Component ID Component Name Licensee's Description of Action

-- HEATEXCHAN~OW CONTROL (

RCSLOOPTORHRPUMPI ISOLATION (.)

)

Manually control RHR flow by locally throttling _

per existing procedures.

Manually open _ in Fire Zone * .

and _

- 432 OJ;FICIAb leJiE! O~lb¥ iE!CIeJRIT¥ RE!bATE!bl 1~Ij;QRMATION

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 Deviation Basis and Continuing Validity Evaluation Based on (1) the installed HEMYC' ERFBS, (1) the The deviation was approved based on the train. cables being establishment of the fire barrier Deviation from NUREG-0800, protected by a 1-hour rated fire barrier with an automatic detection and rating based on required fire BTP CMEB 9.5-1, Section C.7.c, suppression system. testing, and (3) the determination for both trains of cables in the that the fire area is acceptable rooms. The conditions forming the basis for the previous NRC staff approval of from a risk, defense-in-depth, and this deviation have not changed. safety margin standpoint, the NRC staff finds this deviation acceptable.

Variations from the Deterministic Requirements (VFDRs)

HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

This fire area is a transient no storage location.

The only fixed ignition Based on (1) the relationship between The hot standby manual action credited for source near these cables the target(s) and the zone of influence

_supports use of the credited train.

is Auxiliary Transfer of the ignition sources, (2) the fact motor driven AFW-Eump which supplies Panel * . that the fire area has been designated steam generator * .

183 as a transient combustible exclusion EC 69501 will install a zone, and (3) the proposed Under the current licensing basis, this VEWFDS in Auxiliary installation of a VEWFDS in Auxiliary action is considered unallowable and a Transfer Panel., which Transfer Panel., the NRC staff change evaluation is required.

will render the affected finds this VFDR acceptable.

cables not within the ZOI of a significant fixed ignition source.

- 442 or;r;ICIAb YSIi O~JbY SIiCYRITY RCbATIiQ I~Jr;ORMATIO~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 Deviation Basis and Continuing Validity Evaluation Based on (1) the installed HEMYC' ERFBS, (1) the The deviation was approved based on the train. cables being establishment of the fire barrier Deviation from NUREG-0800, protected by a 1-hour rated fire barrier with an automatic detection and rating based on required fire BTP CMEB 9.5-1, Section C.7.c, suppression system. testing, and (3) the determination for both trains of cables in the that the fire area is acceptable rooms. The conditions forming the basis for the previous NRC staff approval of *from a risk, defense-in-depth, and this deviation have not changed. safety margin standpoint, the NRC staff finds this deviation acceptable.

Variations from the Deterministic Requirements (VFDRs)

HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

This fire area is a transient no storage location.

The only fixed ignition source Based on (1) the relationship between The hot standby manual action credited for near these cables is Auxiliary Transfer Panel * .

the target(s) and the zone of influence

_ is required to establish a flow path of the ignition sources, (2) the fact for the charging path minimum flow.

EC 69501 will install a that the fire area has been designated VEWFDS in Auxiliary as a transient combustible exclusion This flow path is required for the credited 117 Transfer Panel., which will zone, (3) the proposed installation of train. charging pump. render the affected cables not a VEWFDS in Auxiliary Transfer within the ZOI of a significant Panel., and (4) the commitment to Under the current licensing basis, this fixed ignition source. install the alternate seal injection action is considered unallowable and a In addition, if the running system, the NRC staff finds this VFDR change evaluation is required.

CSIP were to fail, EC 70350 acceptable.

will provide an additional source of RCS makeup and seal injection.

- 456 Q~~ICIAb lJ5E! Q~Jb¥ 5IiClJ~IT¥ ~libATlig I~J~Q~1\.4ATIQ~J

Fire Area _ Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

This fire area is a transient no storage location.

The change evaluation showed that the affected cables are not within the zone of influence of a significant ignition source.

Based on (1) the relationship between

!!IIIiIII the target( s) and the zone of influence For The issue is the potential mUlyous (Conduit ) is of the ignition sources, (2) the fact opening of either _ or , wrapped with HEMYC', that the fire area has been designated which is not a fully rated concurrent with the spu_ning of the as a transient combustible exclusion 1-hour fire barrier. The RCS head vent valves ( ). zone, (3) the designed mass flow limit 295 containment penetration junction box ( _ ) , to less than the makeup capacity of a The HEMYC' ERFBS credited in this fire located on the containment single charging/safety injection pump, area for _ is not a fully rated 1-hour wall, is unwrapped. and (4) the calculated change in risk fire barrier. meeting the associated acceptance In addition, the RCS head requirements, the NRC staff finds this vents are designed to limit VFDR acceptable.

the mass flow rate of reactor coolant through the vessel head vent to less than the makeup capacity of a single charging/safety injection pump in the event of a line break or inadvertent operation.

The fire risk evaluation for this fire area determined that the additional risk incorporated because of these VFDRs is zero.

Recovery Actions (RAs)

The licensee did not identify any recovery actions required for this fire area.

- 469 OJ;j;IGIAl USE O~JlY SEGblRITY RClATEQ I~Jj;ORMATIO~J

Fire Area _ Attachment 0: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 Recovery Actions Credited for Defense-in-Depth (RA-DID)

Component 10 Component Name Licensee's Description of Action

-- I HEAT EXCHANIiiIIIOW CONTROL (

RCS LOOP TO RHR PUMP.

ISOLATION (.)

)

Manually control RHR flow by locally throttling _

per existing procedures.

Manually open _ in Fire Zone * .

and _

-- I I

RCS LOOP TO RHR PUMP.

ISOLATION VALVE ( . ) CIV HEAT EXCHANGER.

BYPASS FLOW CONTROL Manually open _ in Fire Zone * .

Manually control RHR flow by locally throttling _

per existing procedures.

and _

-- I I

HEAT EXCHANIiiIIIOW CONTROL (

ACCUMULATOR _

DISCHARGE VALVE

)

Manually control RHR flow by locally throttling _

De-energize~_(_).

per existing procedures.

Locallyshut_~

and _

-- I I

ACCUMULATOR _

DISCHARGE VALVE ACCUMULATOR_

DISCHARGE VALVE De-energize _ , at breaker _

Locally shut_in ~

, at breaker in Fire Zone

(_).

r-).

Align pump using _ ,

~

_ _ _ _ _ _ _ _ _ _ _ Section 8.1.

2 MOVs to be opened and a tell-tale drain valve to be shut not necessary until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the event.

Pull the solid state prote~m (SSPS) fuses at the SSPS Cabinets in Fire Area _ _ prior to loss of DC power.

Pull the SSPS fuses at the SSPS Cabinets in Fire Area _ prior to loss of DC power.

- 470 OF"F"ICIAb Y£~ O~Jb¥ £~CURIT¥ R~bAT~9 I~JF"ORMP:TIO~J

Fire Area _ Attachment 0: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables) negligible contribution to the change in CDF results.

This is due to the difference in the probability of non suppression between 25 minutes and 60 minutes being low.

CONTINUED*

The delta-CDF and delta-LERF

CONTINUED* results are lower than the Based on (1) the relationship between (continued) threshold which requires NRC the target(s) and the zone of influence notification per the standard fire The HEMYC' ERFBS credited in this area protection license condition of the ignition sources, (2) the barrier (continued) is not a fully rated 1-hour fire barrier. included in RG 1.205. fire duration being based on appropriate testing, (3) the proposed 364 The change evaluation process is The change process targets modifications to bring the fire barrier associated with the HEMYC' determining whether the installed fire ERFBS are not within the zone Up to the tested configuration, and barriers provide an adequate level of of influence of significant ignition (4) the calculated change in risk protection for the hazards in the fire area. sources and so are considered meeting the associated acceptance to be free of fire damage, and requirements, the NRC staff finds this therefore considered acceptable VFDR acceptable.

"as-is."

EC 69764 will modify the HEMYC' ERFBS to be consistent with the tested configuration for the fire resistance assumed.

The 1-hour rated ERFBS on Cable _

for _ may not be adequate.

The change evaluation Based on the relationship between showed that the affected the target(s) and the zone of influence 8 The change evaluation process is cables are not within the of the ignition sources, the NRC staff determining whether the installed fire zone of influence of a finds this VFDR acceptable.

barriers provide an adequate level of significant ignition source.

protection for the hazards in the fire area.

- 475 Of=f=ICIAb Ye~ O~Jb¥ e~CYRIT¥ R~bAT~O I~Jf=ORM,L\TIO~J

Fire Area Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 Fire Area The licensee analyzed this fire area using the fire risk evaluation approach in accordance with NFPA 805 Section 4.2.4.2, but also applied deterministic simplifying assumptions in order to credit those portions of the facility design that meet the deterministic requirements of NFPA 805 Section 4.2.3. The licensee identified the structures, systems, and components (SSCs) necessary to meet the nuclear safety performance criteria (NSPC) in this fire area.

Evaluation of Fire Suppression Effects on the Nuclear Safety Performance Criteria for Fire Area _

The licensee stated in LAR Attachment C, "NEI 04-02 Table B Fire Area Transition," that this fire area does not have an installed automatic suppression system. In the event of a fire requiring the use of a manual hose station, accumulated water can migrate to adjacent areas equipped with floor drains. Drainage into the adjacent areas will not damage safety-related equipment. Therefore, fire suppression activities will not adversely affect achievement of the nuclear safety performance criteria.

Based on the information provided by the licensee in the NFPA 805 LAR, the NRC staff finds the licensee's evaluation of fire suppression effects on the NSPC acceptable because the results of the licensee's analysis indicate that fire suppression activities will not adversely impact achievement of the nuclear safety performance criteria.

Fire Area Deviations Based on the information provided in the LAR, the licensee credited five previously approved deviations from the existing fire protection requirements. The licensee utilized the process described in LAR Section 4.2.2.2.2, "Results of the Licensing Action Review," to carry forward these deviations, which requires a determination of the basis of acceptability and a determination that the basis of acceptability is still valid.

Deviation Basis and Continuing Validity Evaluation Deviation from NUREG-0800, The deviation was approved based on the conditions on either side of Based on the previous staff BTP CMEB 9.5-1, Section C.5.a, the penetrations, the installed fire protection features, and the physical approval of this deviation and the in that not all penetrations are separation of redundant safe shutdown equipment.

statement by the licensee that the sealed with equivalently rated fire basis remains valid, the NRC staff damper assemblies, door The conditions forming the basis for the previous NRC staff approval of finds this deviation acceptable.

assemblies, or seals. this deviation have not changed.

- 490 G~~ICIAb U£1i G~Jb¥ £IiCURIT¥ RlibATi!i(;) I~J~QRMATIG~J

Fire Area Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 Variations from the Deterministic Requirements (VFDRs)

HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

The change evaluation demonstrated that there is no MT' ERFBS that falls within the ZOI of a significant ignition source. The MT' ERFBS are therefore only subject to the potential impacts of a hot gas layer.

There is no fire scenario Based on (1) the MT' ERFBS fire considered capable of challenging the system's barrier not being within the zone of The MT' ERFBS is credited as a 3-hour minimum performance based influence of a signifcant ignition fire barrier in this area, but is not a fully on a fire rating of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months source, (2) the barrier fire duration rated 3-hour fire barrier.

55 minutes; therefore, no being based on appropriate testing, 14 damage is assumed to occur (3) the proposed modifications to The change evaluation process is to the protected circuits. bring the fire barrier up to the tested determining whether the installed fire configuration, and (4) the calculated barriers provide an adequate level of The MT' ERFBS is credited change in risk meeting the associated protection for the hazards in the fire area. for 115 minutes (1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and acceptance requirements, the NRC 55 minutes), in lieu of the staff finds this VFDR acceptable.

3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months necessitated by the deterministic requirements.

The risk evaluation for plant changes in this area was assessed quantitatively for acceptability using the delta-CDF and delta-LERF criteria from NEI 04-02, Section 5.3.5, and RG 1.205.

- 492 OFFICIAb YSEi O~JbY SEiCURITY REibATEiQ I~JFOR~1ATIO~J

Fire Area Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

The associated change in risk is below the RG 1.205 acceptance criteria. As such, the change in risk due to the MT' ERFBS reduced rating has a negligible contribution to the change in CDF results.

This is due to the difference in the probability of non suppression between 115

- CONTINUED min. and 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months being low.

- CONTINUED The delta-CDF and Based on (1) the MT' ERFBS fire (continued) delta-LERF results are lower barrier not being within the zone of The MT' ERFBS is credited as a 3-hour than the threshold which influence of a signifcant ignition fire barrier in this area, but is not a fully (continued) requires NRC notification per source, (2) the barrier fire duration rated 3-hour fire barrier.

the standard fire protection being based on appropriate testing, 14 license condition included in (3) the proposed modifications to The change evaluation process is RG 1.205. bring the fire barrier up to the tested determining whether the installed fire configuration, and (4) the calculated barriers provide an adequate level of The change process ta~ets change in risk meeting the associated protection for the hazards in the fire area. associated with the MT ERFBS are not within the acceptance requirements, the NRC zone of influence of staff finds this VFDR acceptable.

significant ignition sources and so are considered to be free of fire damage, and therefore considered acceptable "as-is."

EC 69765 will modify the MT' ERFBS consistent with the tested configuration for the fire resistance assumed.

- 493 OjajalCIAl Y~1i O~JlY ~IiCYRITY RlilATcg I~JjaORMATIO~J

Fire Area Attachment D: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open Component VFDR Description Disposition NRC Evaluation Item No. (Cables)

The change evaluation showed that Cable _ is not within the ZOI of a

-and significant ignition source.

Cables are within the ZOI of the The hot standby manual action credited for Transformer ( ),

_ is required to establish a flow path the ~ 480V Auxiliar Based on (1) the relationship between for the charging path minimum flow. SWitchg~), the target(s) and the zone of influence and the of the ignition sources, (2) the This flow path is required for the credited proposed installation of thermal 147 shields above _ , and (3) the train. charging pump.

commitment to install the alternate Under the current licensing basis, this EC 68646 is adding thermal seal injection system, the NRC staff action is considered unallowable and a shields above in finds this VFDR acceptable.

change evaluation is required. order to reduce the overall risk in this fire area.

In addition, if the running CSIP were to fail, EC 70350 will provide an additional source of RCS makeup and seal injection.

EC 68645 will remove the The required manual action for _ is a cables for from the part of the credited train and is necessary area, such that a flow path of Based on the proposed installation of to establish hot standby decay heat water to the. SG is assured. EC 68645, a flow path of water to the removal. All other requirements to use 15

steam generator will be assured.

the. SG for decay heat removal are met for this area. Accordingly, the NRC staff finds this Under the current licensing basis, this Therefore, will no VFDR acceptable.

action is considered unallowable and a change evaluation is required. longer be required to maintain hot standby.

- 494 O~~ICIAb lJS~ Q~Jb¥ S~ClJ~IT¥ ~~bAT~O I~J~Q~~4ATIO~J

Fire Area Attachment 0: Nuclear Safety Capability Assessment Results by Fire Area Performance-Based Compliance with NFPA 805 Section 4.2.4 HNP's Open I VFDR Description Component Disposition NRC Evaluation Item No. (Cables)

The change evaluation showed

_ may spuriously close due to that the cables for are not within the zone of influence Based on (1) the relationship between concurrent intra-cable hot shorts on Cable _ and Cable _ , or due to of a significant ignition source. the target(s) and the zone of influence of the ignition sources, (2) , the an inter-cable hot short on Cable _ . EC 68646 is adding thermal proposed installation of thermal 16 I This could result in a loss of suction to the running charging pump and unrecoverable pump damage.

II shields above four ignition sources that could lead to a hot gas layer.

In addition, EC 70350 will provide alternate RCS makeup shields above the four ignition sources that could lead to a hot gas layer, and (3) the commitment to install the alternate seal injection system, the NRC staff finds this VFDR This issue is being addressed in the ~ in the event that

_ spuriously closes and acceptable.

change evaluation for this fire area.

disables the running CSIP.

The change evaluation showed that exce, for Cables _

and , the affected cables are not within the ZOI of a significant ignition source.

Cables - a a n dare within the ZOI of the Based on (1) the relationship between Cable dam~ cau~urious Transformer ( ), the opening of _ and _ , which 480V Auxiliary Switchgear the target(s) and the zone of influence

, Distribution of the ignition sources, (2) the could result in the loss of RWST inventory Panel_( ), proposed installation of thermal 19 to the containment sump.

.uencer Panel shields above _ , and (3) the

( ), and other commitment to install the alternate This issue is being addressed in the significant sources.

seal injection system, the NRC staff change evaluation for this fire area.

EC 68646 is addin thennal finds this VFDR acceptable.

shields above r in order to reduce the risk in the fire area.

In addition, if the RWST were to drain, EC 70350 will provide an additional source of RCS makeup and seal injection.

- 495 or;r;ICIAb fJS~ O~lb¥ S~CblRIT¥ R~bAT~(J I~Jr;ORMATIO~J

Pkg.: ML102030481 Public Letter and Enclosure' ML102510852 NRR-106 OFFICE LPL2-2/PM LPL2-2/LA LPL2-2/BC LPL2-2/PM NAME MVaaler CSoia DBroaddus BMozafari DATE 9/9/10 9/17/10 12/22/10 12/28/10

v t e Letter Sequence Approval
TAC:MD8807, (Approved, Closed)
Initiation Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request Acceptance, Acceptance, Acceptance, Acceptance Supplement, Supplement Administration Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting Questions 6 August 2009 14 January 2010 Answers 13 August 2009 28 August 2009 9 October 2009 Results Approval, Approval Other: ML090290327, ML091600281, ML100600987
MONTHYEAR2008-07-11 [Table View]

ML102510852

Text

Dear Mr. Burton:

Enclosure:

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