ML082340996

Technical Specifications, Issuance of Amendment No. 273 Refueling Operations - Decay Time

ML082340996
Person / Time
Site:	Salem
Issue date:	09/24/2008
From:	Plant Licensing Branch 1
To:
Ennis R, NRR/DORL, 415-1420
Shared Package
ml082340910	List: ML082340922 ML082340975 ML082340996
References
TAC MD8259, TAC MD8260
Download: ML082340996 (2)

Text

- 4 (2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 273, 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

- - - - - C C C

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

a. 80 hours9.259259e-4 days <br />0.0222 hours <br />1.322751e-4 weeks <br />3.044e-5 months <br />

b. 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> APPLICABILITY: Specification 3.9.3.a - From October 15th 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.

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 ....~ SALEM Lrnrr,./- lIMITen N-273