ML20238E146: Difference between revisions

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f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO 10 CFR 50.62, ATWS RULE POWER AUTHORITY OF THE STATE OF NEW YORK                            l JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 INTRODUCTION By letter dated April 15, 1987 (JPN-87-020), the Power Authority of the State of New York (the licensee) submitted a description of its plans for implementing the requirements of 10 CFR 50.62 (the ATWS rule) at the James A. FitzPatrick Nuclear Power Plant. The Standby Liquid Control System (SLCS) is one of the items addressed by 10 CFR 50.62. The proposed SLCS design would su of enriched sodium pentaborate solution (26.7 aton percent of          to B-10)pply the      50 gpm reactor vessel in order to meet the requirements of the ATWS rule.
f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO 10 CFR 50.62, ATWS RULE POWER AUTHORITY OF THE STATE OF NEW YORK                            l JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 INTRODUCTION By {{letter dated|date=April 15, 1987|text=letter dated April 15, 1987}} (JPN-87-020), the Power Authority of the State of New York (the licensee) submitted a description of its plans for implementing the requirements of 10 CFR 50.62 (the ATWS rule) at the James A. FitzPatrick Nuclear Power Plant. The Standby Liquid Control System (SLCS) is one of the items addressed by 10 CFR 50.62. The proposed SLCS design would su of enriched sodium pentaborate solution (26.7 aton percent of          to B-10)pply the      50 gpm reactor vessel in order to meet the requirements of the ATWS rule.
b I                            EVALUATION I
b I                            EVALUATION I
The SLCS system description provided by the licensee has been reviewed against the requirements of the ATWS rule and Generic Letter 85-03, " Clarification of Equivalent Control Capacity for Standby Liquid Control Systems", dated January 28, 1985. The licensee has proposed to increase the boron enrichment to 26.7 atom percent of B-10, and to supply 50 gpm of 13 weight percent of sodium pentaborate solution to the reactor vessel.      Since the FitzPatrick reactor vessel is 218 inches in diameter, the aforementioned flow / enrichment combination satisfies the ATWS rule equivalency requirement which is based upon 86 gpm, 13 weight percent sodium pentaborate and 19.8 atom percent B-10, and a 251 inch diameter vessel.*
The SLCS system description provided by the licensee has been reviewed against the requirements of the ATWS rule and Generic Letter 85-03, " Clarification of Equivalent Control Capacity for Standby Liquid Control Systems", dated January 28, 1985. The licensee has proposed to increase the boron enrichment to 26.7 atom percent of B-10, and to supply 50 gpm of 13 weight percent of sodium pentaborate solution to the reactor vessel.      Since the FitzPatrick reactor vessel is 218 inches in diameter, the aforementioned flow / enrichment combination satisfies the ATWS rule equivalency requirement which is based upon 86 gpm, 13 weight percent sodium pentaborate and 19.8 atom percent B-10, and a 251 inch diameter vessel.*
The proposed design is therefore acceptable.
The proposed design is therefore acceptable.
The licensee has state 6 in the April 15, 1987 submittal that surveillance and positive verification will be performed periodically (once per month) to assure that the correct isotopic enrichment is maintained. When additional chemicals, e.g., boron or boric acid, are added to the storage tank, the isotopic enrichment of B-10 in the solution will also be verified. This, commitment as well as the conmitment to periodically verify the 50 gpm flow rate should be reflected in the Technical Specifications.
The licensee has state 6 in the April 15, 1987 submittal that surveillance and positive verification will be performed periodically (once per month) to assure that the correct isotopic enrichment is maintained. When additional chemicals, e.g., boron or boric acid, are added to the storage tank, the isotopic enrichment of B-10 in the solution will also be verified. This, commitment as well as the conmitment to periodically verify the 50 gpm flow rate should be reflected in the Technical Specifications.
* As discussed in NRC letter dated October 21, 1986, G. Lainas to Terry Pickens, Chairman, BWR Owners Group.
* As discussed in NRC {{letter dated|date=October 21, 1986|text=letter dated October 21, 1986}}, G. Lainas to Terry Pickens, Chairman, BWR Owners Group.
8709140172 870908 PDR    ADOCK 05000333 P                  PDR
8709140172 870908 PDR    ADOCK 05000333 P                  PDR


Latest revision as of 11:49, 9 March 2021

Safety Evaluation of Util 870415 Proposed Design for Standby Liquid Control Sys.Design Meets Requirements of 10CFR50.62 Re ATWS
ML20238E146
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 09/08/1987
From:
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20238E138 List:
References
NUDOCS 8709140172
Download: ML20238E146 (2)
v • d • e


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f SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATING TO 10 CFR 50.62, ATWS RULE POWER AUTHORITY OF THE STATE OF NEW YORK l JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 INTRODUCTION By letter dated April 15, 1987 (JPN-87-020), the Power Authority of the State of New York (the licensee) submitted a description of its plans for implementing the requirements of 10 CFR 50.62 (the ATWS rule) at the James A. FitzPatrick Nuclear Power Plant. The Standby Liquid Control System (SLCS) is one of the items addressed by 10 CFR 50.62. The proposed SLCS design would su of enriched sodium pentaborate solution (26.7 aton percent of to B-10)pply the 50 gpm reactor vessel in order to meet the requirements of the ATWS rule.

b I EVALUATION I

The SLCS system description provided by the licensee has been reviewed against the requirements of the ATWS rule and Generic Letter 85-03, " Clarification of Equivalent Control Capacity for Standby Liquid Control Systems", dated January 28, 1985. The licensee has proposed to increase the boron enrichment to 26.7 atom percent of B-10, and to supply 50 gpm of 13 weight percent of sodium pentaborate solution to the reactor vessel. Since the FitzPatrick reactor vessel is 218 inches in diameter, the aforementioned flow / enrichment combination satisfies the ATWS rule equivalency requirement which is based upon 86 gpm, 13 weight percent sodium pentaborate and 19.8 atom percent B-10, and a 251 inch diameter vessel.*

The proposed design is therefore acceptable.

The licensee has state 6 in the April 15, 1987 submittal that surveillance and positive verification will be performed periodically (once per month) to assure that the correct isotopic enrichment is maintained. When additional chemicals, e.g., boron or boric acid, are added to the storage tank, the isotopic enrichment of B-10 in the solution will also be verified. This, commitment as well as the conmitment to periodically verify the 50 gpm flow rate should be reflected in the Technical Specifications.

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LCONCLUSION

, We.heve reviewed the SLCS' design proposed by the-licensee and find that it is ~-

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