ML080320434

Tech Spec Pages for Amendment 271 Re Refueling Operations - Decay Time

ML080320434
Person / Time
Site:	Salem
Issue date:	03/05/2008
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
Ennis R, NRR/DORL, 415-1420
Shared Package
ml08032041	List: ML080320434
References
TAC MD7027
Download: ML080320434 (2)

Text

- 4 (2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 271, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Special Low Power Test Program PSE&G shall complete the training portion of the Special Low Power Test Program in accordance with PSE&G's letter dated September 5, 1980 and in accordance with the Commission's Safety Evaluation Report "Special Low Power Test Program",

dated August 22, 1980 (See Amendment No. 2 to DPR-75 for the Salem Nuclear Generating Station, Unit No. 2) prior to operating the facility at a power level above five percent.

Within 31 days following completion Of the power ascension testing program outlined in Chapter 13 of the Final Safety Analysis Report, PSE&G shall perform a boron mixing and cooldown test using decay heat and Natural Circulation. PSE&G shall submit the test procedure to the NRC for review and approval prior to performance of the test. The results of this test shall be submitted to the NRC prior to starting up following the first refueling outage.

(4) Initial Test Program PSE&G shall conduct the post-fuel-loading initial test program (set forth in Chapter 13 of the Final Safety Analysis Report, as amended) without making any major modifications of this program unless modifications have been identified and have received prior NRC approval. Major modifications are defined as:

(a) Elimination of any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (b) Modification of test objectives, methods or acceptance criteria for any test identified in Chapter 13 of the Final Safety Analysis Report, as amended, as essential; (c) Performance of any test at a power level different by more than five percent of rated power from there described; and Amendment No. 271

REFUELING OPERATIONS DECAY TIME LIMITING CONDITION FOR OPERATION 3.9.3 The reactor shall be subcritical for at least:

a. 100 hours4.167 days <br />0.595 weeks <br />0.137 months <br />* - Applicable through year 2010

b. 168 hours7 days <br />1 weeks <br />0.23 months <br /> APPLICABILITY: Specification 3.9.3.a- From October 1 5 th through May 1 5 th, during movement of irradiated fuel in- the reactor pressure vessel.

Specification 3.9.3.b - From May 1 6 th through October 1 4 th, during movement of irradiated fuel in the reactor pressure vessel.

• For Salem Unit 2 refueling outage 2R16 only, the required subcritical time is 86 hours3.583 days <br />0.512 weeks <br />0.118 months <br /> ACTION:

With the reactor subcritical for less* than the required time, suspend all operations involving movement of irradiated fuel in the reactor pressure vessel. The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.3 The reactor shall be determined to have been subcritical as required by verification of the date and time of subcriticality prior to movement of irradiated fuel in the reactor pressure vessel.

SALEM - UNIT 2 3/4 9-3 Amendment No. 271