ML030760083

License Amendment, Containment Ventilation Isolation System

ML030760083
Person / Time
Site:	Harris
Issue date:	03/12/2003
From:	Chandu Patel NRC/NRR/DLPM
To:	Scarola J Carolina Power & Light Co
Patel C P, NRR/DLPM, 415-3025
References
TAC MB6227
Download: ML030760083 (9)

Text

March 12, 2003 Mr. James Scarola, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Code: Zone 1 New Hill, North Carolina 27562-0165

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - ISSUANCE OF AMENDMENT RE: CONTAINMENT VENTILATION ISOLATION SYSTEM (TAC NO. MB6227)

Dear Mr. Scarola:

The Nuclear Regulatory Commission (NRC) has issued Amendment No. 113 to Facility Operating License No. NPF-63 for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). This amendment changes the Technical Specifications (TS) in response to your application dated August 28, 2002.

The amendment revises TS 3/4.9.9, Containment Ventilation Isolation System, to allow the same administrative controls for this TS as were approved previously by the NRC in Amendment No. 104 to the HNP TS for TS 3/4.9.4, Containment Building Penetrations, to provide consistency between the two TS.

A copy of the related Safety Evaluation is enclosed. Notice of Issuance will be included in the Commission's regular bi-weekly Federal Register notice.

Sincerely,

/RA/

Chandu P. Patel, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-400

Enclosures:

1. Amendment No. 113 to NPF-63

2. Safety Evaluation cc w/enclosures:

See next page

March 12, 2003 Mr. James Scarola, Vice President Shearon Harris Nuclear Power Plant Carolina Power & Light Company Post Office Box 165, Mail Code: Zone 1 New Hill, North Carolina 27562-0165

SUBJECT:

SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 - ISSUANCE OF AMENDMENT RE: CONTAINMENT VENTILATION ISOLATION SYSTEM (TAC NO. MB6227)

Dear Mr. Scarola:

The Nuclear Regulatory Commission (NRC) has issued Amendment No. 113 to Facility Operating License No. NPF-63 for the Shearon Harris Nuclear Power Plant, Unit 1 (HNP). This amendment changes the Technical Specifications (TS) in response to your application dated August 28, 2002.

The amendment revises TS 3/4.9.9, Containment Ventilation Isolation System, to allow the same administrative controls for this TS as were approved previously by the NRC in Amendment No. 104 to the HNP TS for TS 3/4.9.4, Containment Building Penetrations, to provide consistency between the two TS.

A copy of the related Safety Evaluation is enclosed. Notice of Issuance will be included in the Commission's regular bi-weekly Federal Register notice.

Sincerely,

/RA/

Chandu P. Patel, Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-400

Enclosures:

1. Amendment No. 113 to NPF-63

2. Safety Evaluation cc w/enclosures:

See next page Distribution:

PUBLIC A. Howe OGC R. Giardina PDII-2 Rdg. E. Dunnington G. Hill (2) ACRS H. Berkow C. Patel R. Dennig P. Fredrickson, RII Accession Number ML030760083 *No major changes to SE OFFICE PM:PDII/S2 LA:PDII/S2 TSS/RORP* OGC SC/PDII-2 NAME CPatel EDunnington RDennig CBray AHowe DATE 2/24/03 02/21/03 1/2/03 2/25/03 03/12/03 OFFICIAL RECORD COPY

CAROLINA POWER & LIGHT COMPANY, et al.

DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 113 License No. NPF-63

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment by Carolina Power & Light Company, (the licensee), dated August 28, 2002, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2. Accordingly, the license is amended by changes to the Technical Specifications, as indicated in the attachment to this license amendment; and paragraph 2.C.(2) of Facility Operating License No. NPF-63 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, as revised through Amendment No. 113 , are hereby incorporated into this license.

Carolina Power & Light Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Allen G. Howe, Chief, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: March 12, 2003

ATTACHMENT TO LICENSE AMENDMENT NO. 113 FACILITY OPERATING LICENSE NO. NPF-63 DOCKET NO. 50-400 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages 3/4 9-11 3/4 9-11 B 3/4 9-3 B 3/4 9-3

--- B 3/4 9-4

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 113 TO FACILITY OPERATING LICENSE NO. NPF-63 CAROLINA POWER & LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-400

1.0 INTRODUCTION

By letter dated August 28, 2002, the Carolina Power & Light Company (the licensee) submitted a request for changes to the Shearon Harris Nuclear Power Plant, Unit 1 (HNP) Technical Specifications (TS). The requested changes would revise TS 3/4.9.9, Containment Ventilation Isolation System, to allow the same administrative controls for this TS as were approved previously by the U.S. Nuclear Regulatory Commission (NRC) in Amendment No. 104 for TS 3/4.9.4, Containment Building Penetrations, to provide consistency between the two TS.

The applicable TS Bases would be revised to document the TS changes and provide supporting information.

2.0 REGULATORY EVALUATION

NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 2, incorporated Technical Specification Task Force Change Traveler (TSTF)-312 guidance that allows the containment building penetrations specified in Standard Technical Specification (STS) 3.9.4, Containment Penetrations, to remain open during core alterations and movement of irradiated fuel provided specific administrative controls are met. Similar guidance is provided for the Actions of STS 3.3.6, Containment Purge and Exhaust Isolation Instrumentation.

On July 30, 2001, the NRC issued License Amendment No. 104 to the HNP TS that revised TS 3/4.9.4, Containment Building Penetrations, and its associated Bases, to allow all containment building penetrations to remain open during refueling operations provided specific administrative controls are met in accordance with TSTF- 312. The provisions of License Amendment 104 applied specifically to the dampers, and did not apply to automatic signals that control the operation of the dampers. As a result, the requirements of the Containment Ventilation Isolation System (CVIS) are more restrictive than the dampers that CVIS controls.

Specifically, current HNP TS require that if an actuation signal to the dampers is inoperable, the required action is to close each of the containment purge makeup and exhaust penetrations providing direct access from the containment atmosphere to the outside atmosphere.

Operations (i.e., irradiated fuel movement) may continue as long as the penetrations are closed and remain closed. This is more restrictive than TS 3/4.9.4, which allows the penetrations to be

opened under administrative control during movement of irradiated fuel assemblies and core alterations. The proposed change would apply the same administrative controls to TS 3/4.9.9, previously reviewed and approved by the NRC in License Amendment 104, for TS 3/4.9.4 in order to provide consistency between the two specifications and in conformance with TSTF-312 guidance.

3.0 TECHNICAL EVALUATION

The proposed change to TS 3/4.9.9 is that a note

• that states that penetration flow path(s) providing direct access from the containment atmosphere to outside atmosphere may be unisolated under administrative controls is added to Action a. In addition, the Bases for TS 3/4.9.9 are modified to state that the breached penetration shall not be obstructed unless capability for rapid removal of obstruction is provided, and also to indicate that the administrative controls ensure that 1) appropriate personnel are aware of the open status of the penetration flow path during core alterations or movement of irradiated fuel assemblies within containment, and 2) specified individuals are designated and readily available to isolate the flow path in the event of a fuel handling accident. The proposed Bases also state that the allowance for un-isolated penetration flow paths with direct access from the containment atmosphere to the outside atmosphere during fuel movement and core alterations is based on (1) confirmatory dose calculations of a fuel handling accident as approved by the NRC staff, which indicates acceptable radiological consequences, and (2) commitments from the licensee to implement acceptable administrative procedures that ensure, in the event of a fuel handling accident (even though the containment fission product control function is not required to meet acceptable dose consequences) the open penetration can and will be promptly closed. The applicable procedures have been previously revised as part of the implementation of License Amendment No. 104.

HNP performed an alternate source term analysis for fuel handling accidents in containment and the fuel handling building as a part of License Amendment No. 104. The analysis assumes that activity produced by the accident escapes to the outside atmosphere. The NRC reviewed and approved the HNP fuel handling accident analysis.

The NRC, in License Amendment No. 104, approved maintaining containment penetrations (that include containment purge and makeup penetrations) open under administrative controls.

The radiological consequences of a fuel handling accident are not affected by the inoperability of the CVIS and the associated actions, and the previously approved fuel handling accident analysis remains bounding.

In NUREG-1431, Standard Technical Specifications - Westinghouse Plants, Revision 2, which incorporates Technical Specification Task Force Change Traveler (TSTF)-312, the corresponding TS to HNP TS 3/4.9.4 and 3/4.9.9 are Standard TS (STS) 3.9.4 Containment Penetrations and STS 3.3.6 Containment Purge and Exhaust Isolation Instrumentation, respectively. The STS Action for an inoperable containment purge and exhaust isolation instrumentation system during movement of irradiated fuel assemblies specified in STS 3.3.6 is to isolate the penetration or follow the Actions of STS 3.9.4, which would allow the penetration to be opened under the administrative controls specified by STS 3.9.4 (TSTF-312).

The HNP-proposed change is an acceptable alternative to the STS Actions for an inoperable CVIS. Thus, the NRC staff finds the proposed change acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the State of North Carolina official was notified of the proposed issuance of the amendment. The State official had no comments.

5.0 ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (67 FR 61676). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.

6.0 CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributor: R. J. Giardina Date: March 12, 2003

Mr. James Scarola Shearon Harris Nuclear Power Plant Carolina Power & Light Company Unit 1 cc:

Mr. William D. Johnson Mr. Robert J. Duncan II Vice President and Corporate Secretary Director - Site Operations Carolina Power & Light Company Carolina Power & Light Company Post Office Box 1551 Shearon Harris Nuclear Power Plant Raleigh, North Carolina 27602 Post Office Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165 Resident Inspector/ Harris NPS c/o U. S. Nuclear Regulatory Commission Mr. Robert P. Gruber 5421 Shearon Harris Road Executive Director New Hill, North Carolina 27562-9998 Public Staff NCUC 4326 Mail Service Center Ms. Karen E. Long Raleigh, North Carolina 27699-4326 Assistant Attorney General State of North Carolina Chairman of the North Carolina Post Office Box 629 Utilities Commission Raleigh, North Carolina 27602 Post Office Box 29510 Raleigh, North Carolina 27626-0510 Public Service Commission State of South Carolina Ms. Linda Coleman, Chairperson Post Office Drawer 11649 Board of County Commissioners Columbia, South Carolina 29211 of Wake County P. O. Box 550 Ms. Beverly Hall, Acting Director Raleigh, North Carolina 27602 Division of Radiation Protection N.C. Department of Environment Mr. Gary Phillips, Chairman and Natural Resources Board of County Commissioners 3825 Barrett Drive of Chatham County Raleigh, North Carolina 27609-7721 P. O. Box 87 Pittsboro, North Carolina 27312 Mr. Terry C. Morton Manager Mr. James W. Holt, Manager Performance Evaluation and Support Services Regulatory Affairs CPB 7 Carolina Power & Light Company Carolina Power & Light Company Shearon Harris Nuclear Power Plant Post Office Box 1551 P. O. Box 165, Mail Zone 1 Raleigh, North Carolina 27602-1551 New Hill, North Carolina 27562-0165 Mr. Benjamin C. Waldrep Mr. John R. Caves, Supervisor Plant General Manager - Harris Plant Licensing/Regulatory Programs Carolina Power & Light Company Carolina Power & Light Company Shearon Harris Nuclear Power Plant Shearon Harris Nuclear Power Plant P. O. Box 165, Mail Zone 3 P. O. Box 165, Mail Zone 1 New Hill, North Carolina 27562-0165 New Hill, NC 27562-0165 Mr. John H. ONeill, Jr.

Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.

Washington, DC 20037-1128