ML020990743

Issuance of Amendments to Remove the low-scram Pilot

ML020990743
Person / Time
Site:	Browns Ferry
Issue date:	04/08/2002
From:	Jabbour K NRC/NRR/DLPM/LPD2
To:	Scalice J Tennessee Valley Authority
Jabbour K, NRR/DLPM, 415-1496
References
TAC MB2722, TAC MB2723
Download: ML020990743 (12)

Text

April 8, 2002 Mr. J. A. Scalice Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 2 AND 3 - ISSUANCE OF AMENDMENTS TO REMOVE THE LOW-SCRAM PILOT AIR HEADER PRESSURE SWITCHES (TAC NOS. MB2722 AND MB2723)

Dear Mr. Scalice:

The Commission has issued the enclosed Amendment Nos. 276 and 235 to Facility Operating Licenses Nos. DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Units 2 and 3, respectively. The amendments are in response to your application dated August 17, 2001 (TS-366). They would remove the low-scram pilot air header pressure switches at the Browns Ferry Plant, Units 2 and 3.

A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.

Sincerely,

/RA/

Kahtan N. Jabbour, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-260 and 50-296

Enclosures:

1. Amendment No. 276 to License No. DPR-52

2. Amendment No. 235 to License No. DPR-68

3. Safety Evaluation cc w/enclosures: See next page

April 8, 2002 Mr. J. A. Scalice Chief Nuclear Officer and Executive Vice President Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801

SUBJECT:

BROWNS FERRY NUCLEAR PLANT, UNITS 2 AND 3 - ISSUANCE OF AMENDMENTS TO REMOVE THE LOW-SCRAM PILOT AIR HEADER PRESSURE SWITCHES (MB2722 AND MB2723)

Dear Mr. Scalice:

The Commission has issued the enclosed Amendment Nos. 276 and 235 to Facility Operating Licenses Nos. DPR-52 and DPR-68 for the Browns Ferry Nuclear Plant, Units 2 and 3, respectively. The amendments are in response to your application dated August 17, 2001 (TS-400). They would remove the low-scram pilot air header pressure switches at the Browns Ferry Plant, Units 2 and 3.

A copy of the Safety Evaluation is also enclosed. Notice of Issuance will be included in the Commissions biweekly Federal Register notice.

Sincerely,

/RA/

Kahtan N. Jabbour, Senior Project Manager, Section 2 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-260 and 50-296

Enclosures:

1. Amendment No. 276 to License No. DPR-52

2. Amendment No. 235 to License No. DPR-68

3. Safety Evaluation cc w/enclosures: See next page Distribution:

PUBLIC KJabbour RLandry PDII-2 Reading ACRS PFredrickson, RII HBerkow GHill (4)

OGC RCorreia RDennig BClayton (hard copy)

ADAMS ACCESS.NO.ML020990743

• No major changes to the SE OFFICE PDII-2/PM PDII-2/LA SRXB/SC OGC PDII-2/SC NAME KJabbour BClayton SE dated*

AHodgdon(NLO)

RCorreia DATE 03 /18/02 03/18/02 03/07/02 03/17/02 04/01/02 OFFICIAL RECORD COPY

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-260 BROWNS FERRY NUCLEAR PLANT, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 276 License No. DPR-52

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 17, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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. DPR-52 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 276, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days following completion of the Unit 2 Cycle 12 refueling outage scheduled for the spring 2003.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Richard P. Correia, 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: April 8, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 276 FACILITY OPERATING LICENSE NO. DPR-52 DOCKET NO. 50-260 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment numbers and contain marginal lines indicating the areas of change.

REMOVE INSERT 3.3-9 3.3-9 B 3.3-2 B 3.3-2 B 3.3-28 B 3.3-28 B 3.3-29 B 3.3-29 B 3.3-41 B 3.3-41

TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-296 BROWNS FERRY NUCLEAR PLANT, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 235 License No. DPR-68

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

A.

The application for amendment by Tennessee Valley Authority (the licensee) dated August 17, 2001, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commissions 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 Commissions 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 Commissions 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. DPR-68 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 235, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 120 days following completion of the Unit 3 Cycle 10 refueling outage scheduled for the spring 2002.

FOR THE NUCLEAR REGULATORY COMMISSION

/RA/

Richard P. Correia, 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: April 8, 2002

ATTACHMENT TO LICENSE AMENDMENT NO. 235 FACILITY OPERATING LICENSE NO. DPR-68 DOCKET NO. 50-296 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment numbers and contain marginal lines indicating the areas of change.

REMOVE INSERT 3.3-9 3.3-9 B 3.3-2 B 3.3-2 B 3.3-28 B 3.3-28 B 3.3-29 B 3.3-29 B 3.3-41 B 3.3-41

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 276 TO FACILITY OPERATING LICENSE NO. DPR-52 AND AMENDMENT NO. 235 TO FACILITY OPERATING LICENSE NO. DPR-68 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 2, AND 3 DOCKET NOS. 50-260, AND 50-296

1.0 INTRODUCTION

By letter dated August 17, 2001(Reference 1), the Tennessee Valley Authority (TVA or the licensee) submitted a request for changes to the Browns Ferry Nuclear Plant, Units 2 and 3 (BFN Units 2 and 3), Technical Specifications (TS). The requested changes would remove the low scram pilot air header pressure switches and lower the allowable value for the scram discharge volume water level high float switches.

TVA implemented short-term and long-term fixes at BFN Units 2 and 3 which included the installation of the low scram pilot air header pressure switches in response to the U.S. Nuclear Regulatory Commission (NRC) IE Bulletin 80-17, Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR [Boiling Water Reactor], (Reference 2). The installation of the air pressure switches was a short-term fix to scram the reactor on sensing low-pressure in the control air system that serves the control rod drive system. The short-term fix was to be removed after completion of long-term modifications identified in the IE Bulletin. Due to additional issues raised by slow response time of the float switches, the low scram pilot air header pressure switches were left in place.

The connecting piping between the Scram Discharge Instrument Volume (SDIV) and the float switches will be replaced by larger pipe and the elevation of the float switches will be lowered during the current refueling outage for BFN Unit 3, and the next refueling outage for BFN Unit 2.

2.0 EVALUATION TVA responded to the modifications outlined in IE Bulletin No. 80-17 by use of scram pilot air header pressure switches that were compared with diverse instruments in the SDIVs for the SDIV high water level trip function. The redundant pairs of resistance-temperature detectors (RTDs) and float switches were found to result in a delayed scram actuation signal from the float switches by as much as 20 seconds. The scram pilot air pressure switches, though intended as a short-term fix, were retained while a remedy was determined for this scram signal delay. Analyses have indicated that the slow response time of the float switches was due to an undersized piping connection between the SDIVs and the float switch assemblies. During the current refueling outage for BFN Unit 3 and the next refueling outage for BFN Unit 2, the piping size between the float switches and the SDIVs will be increased and the float switch assemblies will be lowered. Thus, the scram pilot air pressure switches will no longer be needed.

Unit 2 has experienced two spurious reactor scram signals from the scram pilot air pressure switches, due to maintenance activities, which will be eliminated by the removal of the switches.

In response to the long-term modifications noted in the IE Bulletin, BFN has added separate SDIVs for each of the two rod banks, increased the piping connection size between the SDV and SDIVs to 6 inches, made improvements to the scram discharge volume (SDV) vent and drains, and added redundant and diverse high water level trip sensors in the SDIVs.

Redundant pairs of RTDs and Magnetrol float switches have been installed in each SDIV to provide diverse trip capability for a high water level condition in the SDIVs.

The scram pilot air pressure switches were added to the TS in License Amendment 125 for Unit 2 and License Amendment 197 for Unit 3. The pressure switches are included in TS Table 3.3.1.1-1, Reactor Protection Instrumentation, Function 13.

3.0

SUMMARY

TVA has provided an acceptable resolution of the modifications recommended as long-term fixes in IE Bulletin 80-17 and the close-out of the IE Bulletin (Reference 3). Based on its review, the staff finds that the proposed TS changes are acceptable. Furthermore, the staff finds that the removal of the scram pilot air header pressure switches and the lowering of the SDV from 50 gallons to 46 gallons are also acceptable.

4.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Alabama State 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 and changes surveillance requirements. 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 57126). 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 Commissions 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.

7.0 REFERENCES

1.

Letter from TVA to NRC dated August 17, 2001.

2.

IE Bulletin No. 80-17, Failure of 76 of 185 Control Rods to Fully Insert During A Scram at a BWR, July 3, 1980.

3.

NUREG/CR-5191, Close-out of IE Bulletin 80-17: Failure of 76 of 185 Control Rods to Fully Insert During a Scram at a BWR, December 1988.

Principal Contributor: Ralph Landry, NRR Date: April 8, 2002

Mr. J. A. Scalice BROWNS FERRY NUCLEAR PLANT Tennessee Valley Authority cc:

Mr. Karl W. Singer, Senior Vice President Nuclear Operations Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Jon R. Rupert, Vice President (Acting)

Engineering & Technical Services Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Ashok S. Bhatnagar, Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 General Counsel Tennessee Valley Authority ET 11A 400 West Summit Hill Drive Knoxville, TN 37902 Mr. Robert J. Adney, General Manager Nuclear Assurance Tennessee Valley Authority 6A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 Mr. Robert G. Jones, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Mr. Mark J. Burzynski, Manager Nuclear Licensing Tennessee Valley Authority 4X Blue Ridge 1101 Market Street Chattanooga, TN 37402-2801 Mr. Timothy E. Abney, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority P.O. Box 2000 Decatur, AL 35609 Senior Resident Inspector U.S. Nuclear Regulatory Commission Browns Ferry Nuclear Plant l0833 Shaw Road Athens, AL 35611 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611