ML050540626

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License Amendment Request to Eliminate the Requirements for the Hydrogen Recombiners (TS 3.6.7) and the Requirements for Hydrogen Monitors (TS 3.3.3), Using the Consolidated Line Item Improvement Process
ML050540626
Person / Time
Site: Catawba  Duke Energy icon.png
Issue date: 02/14/2005
From: Jamil D
Duke Power Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML050540626 (10)
v • d • e


Text

Duke D.M. JAMIL UW Power. Vice President A Duke Energy Company Duke Power Catawba Nuclear Station 4800 Concord Rd. / CNO1VP York, SC 29745-9635 803 831 4251 803 831 3221 fax February 14, 2005 U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION: Document Control Desk

Subject:

Duke Energy Corporation Catawba Nuclear Station Units 1 and 2 Docket Nos. 50-413 and 50-414 License Amendment Request to Eliminate the Requirements for the Hydrogen Recombiners (Technical Specification 3.6.7) and the Requirements for Hydrogen Monitors (Technical Specification 3.3.3), Using the Consolidated Line Item Improvement Process

Reference:

Letter from Duke Energy Corporation to the NRC, same subject, dated May 27, 2004 The reference letter transmitted Duke Energy Corporation (Duke) proposed license amendment request (LAR) for the Facility Operating Licenses and Technical Specifications (TS) for Catawba Nuclear Station Units 1 and 2. The proposed amendment eliminated the TS 3.6.7 requirements for the Hydrogen Recombiners and the TS 3.3.3 requirements for Hydrogen Monitors. Conforming changes were also made to all associated Bases affected by this LAR and these Bases changes were included in the submittal package. The change was consistent with NRC approved Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-447, Rev. 1 (Elimination of Hydrogen Recombiners and Change to Hydrogen and Oxygen Monitors).

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www. dukepower. corn

U.S. NRC Page 2 February 14, 2005 On April 29, 2004, the NRC issued License Amendments 213 and 207 for Catawba Units 1 and 2, respectively.

Subsequently, on January 13, 2005, the NRC issued License amendment 218 and 212 for Catawba Units 1 and 2, respectively. These amendments modified the TS Table of Contents, TS and Bases for 3.3.3 and the Bases only for 3.6.8. Consequently, these amendments revised the pages contained in the reference letter. The affected pages are being remarked and resubmitted to reflect the currently issued pages.

The resubmittal of the affected TS and Bases pages does not result in changes to the technical discussion associated with the reference letter. Additionally, there are no changes needed to the originally transmitted No Significant Hazards Consideration Analysis or Environmental Analysis.

There are no NRC commitments contained in this letter or its attachment.

Pursuant to 10 CFR 50.91, a copy of this amendment request is being sent to the appropriate State of South Carolina official.

Inquiries on this matter should be directed to A. Jones-Young at (803) 831-3051.

Very truly yours, D. M. Jamil Site Vice President ATTACHMENT

U.S. NRC February 14, 2005 Page 3 D. M. Jamil, being duly sworn, affirms that he is the person who subscribed his name to the foregoing statement, and that all matter~s' and facts set forth herein are true and correct to the best of his knowledge.

Subscribed and sworn to me:

_, Notary Public My commission expires: 7-/lo- P-o 2-

. . ^SEAL

U.S. NRC February 14,2005 Page 4 xc (with attachments):

W. D. Travers U. S. Nuclear Regulatory Commission Regional Administrator, Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, GA 30303 S. E. Peters NRC Project Manager U. S. Nuclear Regulatory Commission Mail Stop 0-8 H12 Washington, DC 20555-0001 E. F. Guthrie Senior Resident Inspector U. S. Nuclear Regulatory Commission Catawba Nuclear Site H. J. Porter Division of Radioactive Waste Management South Carolina Bureau of Land and Waste Management 2600 Bull Street Columbia, SC 29201

ATTACHMENT 1 PROPOSED TECHNICAL SPECIFICATION and BASES CHANGES (MARK-UP)

7"! ."

TABLE OF CONTENTS (continued) 3.4 REACTOR COOLANT SYSTEM (RCS).... 3.4.1-1 3.4.1 RCS Pressure, Temperature, and Flow Departure from

'Nucleate Boiling (DNB) Limits. .3.4.1-1 3.4.2 ' RCS Minimum Temperature for Criticality ............. ............. 3.4.2-1 3.4.3 RCS Pressure and Temperature (Pt)Limits . . .... 3.4.3-1 3.4.4'. RCS Loops-MODES I and 2 . .3.4.4-1 3.4.5 RCS Loops -MODE 3 ....... '3.4.51 ..

3.4.6 RCS Loops- MODE44 ............... 3.4.6-1 3.4.7 RCS Loops-MODE 5, Loops Filled 3.4.7-1 3.4.8 RCS Loops-MODE 5,'Loops Not Filed. . . 3.4.8-1 3.4.9 , Pressurizer;  ;.' .. 3.4.9-1 3.4.10 Pressurizer Safety Valves ..... ;.3.4.10-1 3A.11 Pressurizer Power Operated Relief Valves (PORVs) .. 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP) System ..... .3.4.12-1 3.4.13 ' RCS Operational LEAKiA.GEE.... 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage . ..............................

3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation . ..........................3.4.15-1 3.4.16 RCS Specific Activity ................  ;. 3.4.16-1 3.4.17 RCS Loops-Test Exceptions .... 3.4.17-1 3.4.18 Steam Generator (SG) Tube Integrity . ... 3.4.18-1 I 3.5 'EMERGENCY CORE COOLING SYSTEMS (ECCS) .... 3.5.1-1 3.5.1 Accumulators ............. ...  ; ..;.;.;.-.;.3.5.1-1 3.5.2 ECCS-Operating ...... .;.3.5.2-1 3.5.3 ECCS-Shutdown;; ..  ;.:

3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST) .......................... 3.5.4-1 3.5.5 Seal Injection FIow  ;...;. 3.5.5-1 3.6 CONTAINMENT SYSTEMS ................ 3.6.1-1 3.. 1 C.ontainmen

.......... 3.6.1-1 3.6.2 Containment Air Locks ;......., -:3.6.2-1 3.6.3 Containment Isolation Valves . . ................ ..... 3.6.3-1 3.6.4 Containment Pressure ................ .  ; 3.6.4-1 3.6.5 Containment Air Temperature ........................ 3.6.5-1 3.6.6 Containment Spray System ........................ 3.6.6-1 3.6.7 do-I- ~sce bn3681 3.6.8 Hydrogen Skimmer System (HSS) 3.3..6. 81 3.6.9 Hydrogen Ignition System (HIS) . .3.6.9-1 3.6.10 Annulus Ventilation System (AVS) . . ..................... 3.6.10-1 3.6.11 Air Return System (ARS) .. 3.6.11-1 3.6.12 Ice Bed ..... -.;; 3.6.12-1 3.6.13 Ice Condenser Doors . ............... .. 3.6.13-1 3.6.14 Divider Barrier Integrity': ...... 3.6.14.1 3.6.15 Containment Recirculatlon Drains . .. ....................;3.6.15-1 3.6.16 Reactor Building ;' . . .................. 3.6.16-1 3.6.17 . Containment Valve Injection Water System (CVIWS) .3.6.17-1 Catawba Units I and 2 -.tli a Amendment Nos; 241aiJ 2l2

TABLE OF CONTENTS B 3.4 REACTOR COOLANT SYSTEM (RCS) (continued)

B 3.4.9 Pressurizer ... .............B 3.4.9-1 B 3.4.10 Pressurizer Safety Valves ............. . . .B 3.4.10-1 B 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ................ B 3.4.11-1 B 3.4.12 Low Temperature Overpressure Protection (LTOP) System ............ B 3.4.12-1 B 3.4.13 RCS Operational LEAKAGE .................................... . ... B 3.4.13-1 B 3.4.14 RCS Pressure Isolation Valve (PMV) Leakage . .............. B 3.4.14-1 B 3.4.15 RCS Leakage Detection Instrumentation ........................................ B 3.4.15-1 B 3.4.16 RCS Specific Activity . . .............................. B 3.4.16-1 B 3.4.17 RCS Loops-Test Exceptions ........................................ B 3.4.17-1 B 3A.18 Steam Generator (SG) Tube Integrity ............ B 3.4.18-1 B3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)

B3.5.1 Accumulators . . .B 3.5.1-1 B 3.5.2 . ECCS.Operating ..... B 3.5.2-1 B 3.5.3 ECCS-Shutdown . .... ... B 3.5.3-1 B 3.6.4 Refueling Water Storage Tank (RWST) .B 3.5.4-1 B 3.5.5 Seal Injection FlowB. 3.5.5-1 B3.6 CONTAINMENT SYSTEMS B 3.6.1 Containment ................... B 3.6.1-1 B 3.6.2 Containment Air Locks ................... B 3.6.2-1 B 3.6.3 Containment Isolation Valves ................... B 3.6.341 B 3.6.4 Containment Pressure .................... B 3.6.4-1 B3.6.5 Containment Air Temperature ................... B 3.6.5-1 B 3.6.6 Containment Spray System ................... B 3.6.6-1 B 3.67tr elmb............................ B7-1 ..

B 3.6.8 Hydrogen Skimimer System (HSS) ...................... B 3.6.8-1 B 3.6.9 Hydrogen Ignition System (HIS) ....................... B 3.6.9-1 B 3.6.10 Annulus Ventilation System (AVS) ....................... B 3.6.10-1 B 3.6.11 Air Return System (ARS) ...................... B 3.6.1 1-1 B 3.6.12 Ice Bed ...................... B 3.6.12-1 B 3.6.13 Ice Condenser Doors .:..... B 3.6.13-1 B 3.6.14 Divider Barrier Integrity ..................... B 3.6.14-1 B 3.6.15 Containment Recirculation Drains ..................... B 3.6.1 5-B 3.6.16 Reactor Building ..................... B 3.6.16-1 B 3.6.17 Containment Valve Injection Water System (CViWS) ...................... B 3.6.17-1 B 3.7 PLANT SYSTEMS B 3.7.1 Main Steam Safety Valves (MSSVs) ........................ B 3.7.1-1 B 3.7.2 Main Steam Isolation Valves (MSIVs) ........................ B 3.7.2-1 B 3.7.3 Main Feedwater Isolation Valves (MFIVs), Main Feedwater Control Valves (MFCVs), their Associated Bypass Valves, and the Tempering Valves .......................................... B 3.7.3-1 B 3.7.4 Steam Generator Power Operated Relief Valves (SG PORVs) ....... B 3.7.4-1 B 3.7.5 Auxiliary Feedwater (AFW) System .......................................... B 3.7.5-1 B 3.7.6 Condensate Storage System (CSS) .......................................... B 3.7.6-1 Catawba Units i and 2 li Revision No./

Il PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 The PAM instrumenrtation for each Function in Table 3.3.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

The Hyr-99 " iJ~s~trFG Wre Aot Fejlrid.n 44D

- --- - JU

ce..q ACTIONS

- -NOTE---

Separate Condition entry is allowed for each Function. I CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in Table 3.3.3-1 required channels for the channel.

inoperable.

B. One or more Functions B.1 Restore required channel 30 days with one required to OPERABLE status.

channel inoperable.

C. One or more Functions C.1 Restore'required channel 30 days with one required to OPERABLE status.

channel inoperable.

AND Diverse channel OPERABLE.

(continued)

CATAWBA UNITS I AND 2 3.3.3-1 CAAmendment Nos. 2

PAM Instrumentation B 3.3.3 BASES APPLICABILITY (continued)

-ydrog gen-iMterentrequired4e4be PER8LABfEin DCE3E.

i-ACTIONS A Note has been added Inthe ACTIONS to clarify the application of I Completion Time rules. The Conditions of this Specification may be entered Independently for each Function listed on Table 3.3.3-1. When the Required Channels InTable 3.3.3-1 are specified (e.g., on a per steam line, per loop, per SG, etc., basis), then the Condition may be entered separately for each steam line, loop, SG, etc., as appropriate.

The Completion Time(s) of the Inoperable channel(s) of a Function will be tracked separately for each Function starting from the time the Condition was entered for that Function.

A.1 Condition A applies to all PAM instrument Functions. Condition A addresses the situation when one or more required channels for one or more Functions are inoperable. The Required Action is to refer to Table 3.3.3-1 and take the appropriate Required Actions for the PAM instrumentation affected. The Completion Times are those from the referenced Conditions and.Required Actions.

B.1 Condition B applies when one or more Functions have one required channel that is Inoperable. Required Action A.1 requires restoring the inoperable channel to OPERABLE status within 30 days. The 30 day Completion Time is based on operating experience and takes into account the remaining OPERABLE channel, the passive nature of the Instrument (no critical automatic action is assumed to occur from these instruments), and the low probability of an event requiring PAM instrumentation during this interval.

Catawba Units 1 and 2 B 3.3.3-12 Revision No./1

HSS B 3.6.8 BASES.

APPLICABILITY (continued)

-In MODE 3 or 4, both the hydrogen production rate and the total hydrogen produced after a LOCA would be less than that calculated for the DBA LOCA. Also, because of the limited time in these MODES, the probability of an accident requiring the HSS is low. Therefore, the HSS is not required In MODE 3 or 4.

In MODES 5 and 6, the probability and consequences of a LOCA or steam line break (SLB) are reduced due to the pressure and temperature limitations Inthese MODES. Therefore, the HSS Is not required Inthese MODES.

ACTIONS A.1 With one HSS train inoperable, the inoperable train must be restored to OPERABLE status within 30 days. In this Condition, the remaining OPERABLE HSS train Is adequate to perform the hydrogen mixing function. However, the overall reliability Is reduced because a single failure In the OPERABLE train could result in reduced hydrogen mixing capability. The 30 day Completion Time Is based on the availability of the other HSS train, the small probability of a LOCA or SLB occurring (that would generate an amount of hydrogen that exceeds the flammability limit), the amount of time available after a LOCA or SLB (should one occur) for operator action to prevent hydrogen accumulation from exceeding the flammability limit, and the availability of the-hydrogen--

-reembinere and, hydrogen ignitors.

B.1 If an inoperable HSS train cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. The allowed Completion Time of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power conditions in an orderly manner and without challenging plant systems.

Catawba Units 1 and 2 B 3.6.8-3 Revision No.,

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