ML062230167

Tech Spec Pages for Amendment 222 Deletion of Requirement Related to NRC Approval of Engineering Evaluation for Elevated Relief Valve Discharge Pipe Temperature

ML062230167
Person / Time
Site:	Pilgrim
Issue date:	08/04/2006
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
References
TAC MC7053
Download: ML062230167 (3)

Text

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 222 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. Records ENO shall keep facility operating records in accordance with the requirements of the Technical Specifications.

D. Equalizer Valve Restriction - DELETED E. Recirculation Loop Inoperable - DELETED F. Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated December 21, 1978 as supplemented subject to the following provision:

ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Pilgrim Nuclear Power Station Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision 0" submitted by letter dated October 13, 2004.

Amendment 244, 24-6, 246, 24-7, 2-14,

LIMING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6 PRIMARY SYSTEM BOUNDARY (Cont) 4.6 PRIMARY SYSTEM BOUNDARY (Cont)

c. With no required leakage D. Safety and Relief Valves detection systems Operable, be in Cold Shutdown within 1. Testing of safety and relief/safety 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. valves shall be in accordance with 3.13.

D. Safety and Relief Valves

2. At least one of the relief/safety valves

1. During reactor power operating shall be disassembled and inspected conditions and prior to reactor startup each refueling outage.

from a Cold Condition, or whenever reactor coolant pressure is greater 3. Whenever the safety relief valves are than 104 psig and temperature required to be operable, the greater than 3400F, both safety discharge pipe temperature of each valves and the safety modes of all safety relief valve shall be logged relief valves shall be operable. The daily.

nominal setpoint for the relief/safety valves shall be selected between 4. Instrumentation shall be calibrated 1095 and 1115 psig. All relief/safety and checked as indicated in Table valves shall be set at this nominal 4.2.F.

setpoint +/- 11 psi. The safety valves shall be set at 1240 psig +/- 13 psi.

2. If Specification 3.6.D.1 is not met, an orderly shutdown shall be initiated and the reactor coolant pressure shall be below 104 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

NOTE Technical Specifications 3.6.D.3 -

3.6.D.5 apply to the two Stage Target Rock relief valves.

3. If the temperature of any safety relief discharge pipe exceeds 212°F during normal reactor power operation for a period of greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, an engineering evaluation shall be performed justifying continued operation for the corresponding temperature increases.

Amendment No. 2, 66,88, 133, 139,*1, 9 222 3/4.6-6

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.6 PRIMARY SYSTEM BOUNDARY (Cont) 4.6 PRIMARY SYSTEM BOUNDARY (Cont)

D. Safety Relief Valves (Con't)

4. Any safety relief valve whose discharge pipe temperature exceeds 212OF for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more shall be removed at the next cold shutdown of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more, tested in the as-found condition, and recalibrated as necessary prior to reinstallation.

5. The limiting conditions of operation for the instrumentation that monitors tail pipe temperature are given in Table 3.2-F.

E. Jet Pumps

1. Whenever the reactor is in the Startup or Run Modes, all jet pumps shall be Operable. If it is determined that a jet pump is inoperable, the reactor shall be in Hot Shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. E. Jet Pumps NOTES

1. Not required to be performed until 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the associated recirculation loop is in operation.

2. Not required to be performed until 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after >25% Rated Thermal Power.

Whenever there is recirculation flow with the reactor in the Startup or Run Modes, jet pump operability shall be checked daily by verifying at least one of the following criteria (1, 2, or 3) is satisfied for each operating recirculation loop:

1. Recirculation pump flow to speed ratio differs by < 5% from established patterns, and jet pump loop flow to recirculation pump speed ratio differs by < 5% from established patterns.

2. Each jet pump diffuser to lower plenum differential pressure differs by < 20% from established patterns.

3. Each jet pump flow differs by < 10% from established patterns.

Amendment No. 46,66, 71, 93, 13, 205,21*, 222 314.6-7