ML070680300

Tech Spec Pages for Amendment 259 Maximum Allowable Power with Inoperable Main Steam Safety Valves

ML070680300
Person / Time
Site:	Salem
Issue date:	03/07/2007
From:	NRC/NRR/ADRO/DORL/LPLI-2
To:
Ennis R, NRR/DORL, 415-1420
Shared Package
ML070170301	List: ML070170268 ML070680300
References
TAC MD1190
Download: ML070680300 (2)

Text

(2) Technical Specifications and Environmental Plan The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 259 , 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.259

TABLE 3.7-1 MAXIMUM ALLOWABLE POWER WITH INOPERABLE STEAM LINE SAFETY VALVES Maximum Number of Inoperable Safety Maximum Allowable Power*

Valves on Any Operating Steam Generator (Percent of RATED THERMAL POWER) 1 87 2

3 58 I

39

• The values do not provide any allowance for calorimetric error.

SALEM - UNIT 2 3/4 7-2 Amendment No.259