ML20217C131: Difference between revisions

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==1.0    INTRODUCTION==
==1.0    INTRODUCTION==


By letter dated March 17,1999, the Yankee Atomic Electric Company (YAEC or licensee) proposed to amend the facility Possession Only License No. DPR-3 for the Yankee Nuclear Power Station (YNPS or plant) by deleting Technical Specifications (TS) Section 6.2.2.f, which contains limits on the working hours of plant staff who perform safety-related functions. YAEC has committed in its March 17 letter to provide appropriate working hour restrictions in its Administrative Procedures. This license amendment will not be implemented until the pertinent    -
By {{letter dated|date=March 17, 1999|text=letter dated March 17,1999}}, the Yankee Atomic Electric Company (YAEC or licensee) proposed to amend the facility Possession Only License No. DPR-3 for the Yankee Nuclear Power Station (YNPS or plant) by deleting Technical Specifications (TS) Section 6.2.2.f, which contains limits on the working hours of plant staff who perform safety-related functions. YAEC has committed in its March 17 letter to provide appropriate working hour restrictions in its Administrative Procedures. This license amendment will not be implemented until the pertinent    -
Administrative Procedures have been made effective.                                                !
Administrative Procedures have been made effective.                                                !
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==2.0      BACKGROUND==
==2.0      BACKGROUND==
The reactor was first made critical in 1960, began commercial operation in 1961, and operated until permanent shutdown on October 1,1991. The nuclear steam supply system was a four-loop pressurized-water reactor designed by the Westinghouse Electric Corporation. A Possession Only License was issued on August 5,1992. On December 20,1993, YAEC submitted a Decommissioning Plan (Plan) and requested NRC approval of the Plan. In an NRC Order dated February 14,1995, and subsequently by letter dated October 28,1996, the Plan was approved. The Plan permitted YAEC to decontaminate and dismantle the structures and components at the site. Decommissioning activities have been proceeding under the approved Plan. As of summer 1999, about 80 percent of the systems not required to support the storage of spent fuel have been dismantled and removed. The spent fuel pool and other support systems associated with fuel storage have been electrically and mechanically isolated from all other remaining plant systems so that spent fuel will not be adversely impacted by future site activities.
The reactor was first made critical in 1960, began commercial operation in 1961, and operated until permanent shutdown on October 1,1991. The nuclear steam supply system was a four-loop pressurized-water reactor designed by the Westinghouse Electric Corporation. A Possession Only License was issued on August 5,1992. On December 20,1993, YAEC submitted a Decommissioning Plan (Plan) and requested NRC approval of the Plan. In an NRC Order dated February 14,1995, and subsequently by {{letter dated|date=October 28, 1996|text=letter dated October 28,1996}}, the Plan was approved. The Plan permitted YAEC to decontaminate and dismantle the structures and components at the site. Decommissioning activities have been proceeding under the approved Plan. As of summer 1999, about 80 percent of the systems not required to support the storage of spent fuel have been dismantled and removed. The spent fuel pool and other support systems associated with fuel storage have been electrically and mechanically isolated from all other remaining plant systems so that spent fuel will not be adversely impacted by future site activities.
3.0      EVALUATION There are no accidents or other events in the Final Safety Analysis Report that would result in an immediate threat to the public or the plant staff, or result in offsite doses in excess of the Environmental Protection Agency Protective Action Guides. Therefore, the staff concludes that the deletion of Section 6.2.2.f from the YNPS TS is acceptable if concurrent with the inclusion of appropriate restraints on excessive overtime in the YNPS Administrative Procedures.
3.0      EVALUATION There are no accidents or other events in the Final Safety Analysis Report that would result in an immediate threat to the public or the plant staff, or result in offsite doses in excess of the Environmental Protection Agency Protective Action Guides. Therefore, the staff concludes that the deletion of Section 6.2.2.f from the YNPS TS is acceptable if concurrent with the inclusion of appropriate restraints on excessive overtime in the YNPS Administrative Procedures.
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9910130174 991008 9 DR ADOCK 0

Latest revision as of 04:01, 21 March 2021

Safety Evaluation Supporting Amend 153 to License DPR-3
ML20217C131
Person / Time
Site: Yankee Rowe
Issue date: 10/08/1999
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20217C110 List:
References
NUDOCS 9910130174
Download: ML20217C131 (2)
v • d • e


Text

.

e teru 4 t UNITED STATES g g NUCLEAR REGULATORY COMMISSION

          • l l l

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION 1 RELATED TO AMENDMENT NO.153 TO POSSESSION ONLY LICENSE NO. DPR-3 YANKEE ATOMIC ELECTRIC COMPANY YANKEE NUCLEAR POWER STATION  !

ROCKET NO. 50-29

1.0 INTRODUCTION

By letter dated March 17,1999, the Yankee Atomic Electric Company (YAEC or licensee) proposed to amend the facility Possession Only License No. DPR-3 for the Yankee Nuclear Power Station (YNPS or plant) by deleting Technical Specifications (TS) Section 6.2.2.f, which contains limits on the working hours of plant staff who perform safety-related functions. YAEC has committed in its March 17 letter to provide appropriate working hour restrictions in its Administrative Procedures. This license amendment will not be implemented until the pertinent -

Administrative Procedures have been made effective.  !

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2.0 BACKGROUND

The reactor was first made critical in 1960, began commercial operation in 1961, and operated until permanent shutdown on October 1,1991. The nuclear steam supply system was a four-loop pressurized-water reactor designed by the Westinghouse Electric Corporation. A Possession Only License was issued on August 5,1992. On December 20,1993, YAEC submitted a Decommissioning Plan (Plan) and requested NRC approval of the Plan. In an NRC Order dated February 14,1995, and subsequently by letter dated October 28,1996, the Plan was approved. The Plan permitted YAEC to decontaminate and dismantle the structures and components at the site. Decommissioning activities have been proceeding under the approved Plan. As of summer 1999, about 80 percent of the systems not required to support the storage of spent fuel have been dismantled and removed. The spent fuel pool and other support systems associated with fuel storage have been electrically and mechanically isolated from all other remaining plant systems so that spent fuel will not be adversely impacted by future site activities.

3.0 EVALUATION There are no accidents or other events in the Final Safety Analysis Report that would result in an immediate threat to the public or the plant staff, or result in offsite doses in excess of the Environmental Protection Agency Protective Action Guides. Therefore, the staff concludes that the deletion of Section 6.2.2.f from the YNPS TS is acceptable if concurrent with the inclusion of appropriate restraints on excessive overtime in the YNPS Administrative Procedures.

9910130174 991008 9 DR ADOCK 0

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  • j Furthermore, there are no structures, systems, or components important to safety that during normal or off normal operations require immediate operator actions to protect public hc alth and safety.

4.0 STATE CONSULTATION

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' In accordance with the Commission's regulations, the Commonwealth of Massachusetts State  !

official was notified of the proposed issuance of the amendment. The Massachusetts State official had no comments.

]

5.0 ENVIRONMENTAL CONSIDERATION

Pursuant to 10 CFR 51.21. 51.32 and 51.36, an environmental assessment and finding of no significant impact was published in the Federal Register on October 7,1999 (64 FR 54653). j Accordingly, based upon the environmental assessment, the Commission has determined that issuance of this amendment will not have a significant effect on the quality of the human environment.

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.

I Principal Contributor: Morton Fairtile

~

Date: October 8,1999 ,

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