ML070860339

Technical Specifications, Modify the TSs to Extend the Use of the Current Pressure-Temperature Limits as Specified in TS Figures 3.6.1, 3.6.2, and 3.6.3 Through the End of Operating Cycle 18

ML070860339
Person / Time
Site:	Pilgrim
Issue date:	02/22/2007
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
References
TAC MD4093
Download: ML070860339 (4)

Text

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.227 , are hereby incorporated in the license. The licensee shall operate the facility in accordalnc-withithe Techhli-i l Specifiatiin-s.

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-f ully-implement-and-maintain-in-effect-all-provisions-of-tihe 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 227

PILGRIM REACTOR VESSEL PREmSSURE-TEMPERATURE LIMITS HYDROSTATIC AND LEAK TESTS III - . - - p- U- U- U- U- *- U- U- * - U- U- U - - U- U- - - U -

1,200 Ii

• BOTTOM HEAD ii A,i *,..

1,100 1,000 I I I I I 900 I I 800 700 C,)

U) 600 I I I j w

0. 500 400 I I -

FIGURE 3.6.1 300 Pilgrim Reactor Pressure Vessel Pressure-Temperature Limits for Hydrostatic Leak Tests 200 The curve applies through Operating Cycle 18 100 I I IL I. I I I 0

50 60 70 80 90 100 110 120 130 140 150 160 170 1.80 190 200 210 220 230 240 250 260 270 TEMPERATURE ('F)

Amendment No. 28,82, 94, 140,197, 227 3/4.6-9

PILGRIM REACTOR VESSEL PRESSURE-TEMPERATURE LIMITS SUBCRITICAL HEATUP AND COOLDOWN 1,2 b0 'I 1 i . .. !

1,1,00 IBOTTOM I ~HEAD I I 1,0100 9100 I I

I 800 t 700 U,

6'00 LU 500 400 FIGURE 3.6.2 300 q I I Pilgrim Reactor Pressure Vessel Pressure-Temperature I 1 Limits for Subcritical Heatup and Cooldown 200 The curve applies through Operating Cycle 18 100 I A 0 .. . . .  : , ,

• F, 50 60 70 80 90 100 110 120 130 140 150 160 170 180 190 200 210 220 230 240 250 260 270 TEMPERATURE (OF)

Amendment No. 287-882-, 94,440,4Q7, 227 3/4.6-10

PILGRIM REACTOR VESSEL PRE SSURE-TEMPERATURE LIMITS PILGRIM REACTOR VESSEL PRE SSURE-TEMPERATURE LIMITS CRITICAL CORE" OPERATION 1,200 1,100 1,000 900 800

0. 700 (I, 600 (n) wj cc 500 (L

400 300 200 FIGURE 3.6.3 Pilgrim Reactor Pressure Vessel Piressure-Temperature 100 Limits for Critical Core Operation The curve applies through Operating Cycle 18 0 * ,,! 'I __________________-J 50 60 70 80 90 100 110 120 130 140 150 1150 170 180 190 200 210 220 230 240 250 260 270 TEMPERATURE (°F) 97 Amendment No. ! 4 0 , 4 , 227 3/4.6-11