ML20217H279

Proposed Tech Specs 3.6.A.1 & 4.6.A.1,pertaining to Primary Sys Boundary,Thermal & Pressurizations Limitations & Surveillance Requirements & Basis 3/4.6.A

ML20217H279
Person / Time
Site:	Pilgrim
Issue date:	03/25/1998
From:	BOSTON EDISON CO.
To:
Shared Package
ML20217H272	List: ML20217H268 ML20217H279 ML20217H329
References
NUDOCS 9804030253
Download: ML20217H279 (5)

Text

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.6 PRIMARY SYSTEM BOUNDARY 4.6 PRIMARY SYSTEM BOUNDARY Applicability: Applicability:

Applies to the operating status of the reactor Applies to the periodic examination and coolant system. testing requirements for the reactor cooling system.

Objective: Objective:

To assure the integrity and safe operation of To determine the condition of the reactor the reactor coolant system. coolant system and the operation of the safety devices related to it.

Specification: Specification:

A. Thermal and Pressurization Limitations A. Thermal and Pressurization Limitations

1. The average rate of reactor coolant 1. During heatups and cooldowns, with the temperature change during normal heatup reactor vessel temperature less than or or cooldown shall not exceed 100 F/hr equal to 450 F, the-temperatures-at4he when averaged over a one-hour period followinglocations-shall-be-permanently except when the vessel temperatures are logged-at4 east every464ninutes-until4he above 450 F. The4eactor-vessel 41ange4o difference 4>etween-any4wo4eadings-at adjacent 4eactor-ve s sel-shell temperature . individual 40 cations 4aken-over-a-46-minute differential-shallmot-exceed 446 F- ' period-is4ess4han-62F+

a. Reactor-vessel-shell-adjacent 4ofeactor vessel 41ange t>--Reactor-vessel 4 hell 4lange c--Recirculation 4 oops-A-ande r 3 verify the RCS heatup and cooldown rates are within limits every 15 minutes.

L J

2. The reactor vessel shall not be 2. Reactor vessel shell temperatures, including pressurized for hydrostatic and/or leakage reactor vessel bottom head, and reactor tests, and subcritical or critical core coolant pressure shall be permanently operation shall not be conducted unless logged at least every 15 minutes whenever the reactor vessel temperatures are above the shell temperature is below 220c F and those defined by the appropriate curves the reactor vesselis not vented.

on Figures 3.6-1, 3.6-2, and 3.6-3. (Linear interpolation between curves is permitted).

At stated pressure, the reactor vessel j bottom head may be maintained at j temperatures below those temperatures j corresponding to the adjacent reactor vessel shell as shown in Figures 3.6-1 and 3.6-2.

9804030253 980325 PDR ADOCK 05000293 P PDR Revision 177 Amendment No. 28 7 82A40;463 3/4.6-1 j l

U

SASIS:

3/4.6 PRIMARY SYSTEM BOUNDARY A. Thermal and Pressurization I imitations The allowable rate of heatup and cooldown for the reactor vessel contained fluid is 100 F per hour averaged over a period of one hour. This rate has been chosen based on past experience with operating power plants. The associated time periods for heatup and cooldown cycles when the 100 F per hour rate is limiting provides for efficient, but safe, plant operation.

Specific analyses were made based on a heating and cooling rate of 100 F/ hour applied continuously over a temperature range of 100 F to 546 F. Calculated stresses were within ASME Boiler and Pressure Vessel Code Section III stress intensity and fatigue limits even at the flange area where maximum stress occurs.

The manufacturer performed detailed stress analysis as shown in Amendment 17 of the FSAR. This analysis includes more severe thermal conditions than those which would be encountered during normal heating and cooling operations.

The-permissible-Gange-to-adjacent-shell-temperature-differential-of 145 F is4he-maximum calculatedfor-100 F/ hour-heating-and-cooling-rate-applied-continuously-over a 100 F to 6502F-range--The-differential-is-due4o4he sluggish 4emperature-response-of-the flange metal-and4tswakie-deereases-for-eny-k>wer4 eating-rate +r-the+ame-rate-applied over a narrower-range-The coolant in the bottom of the vessel is at a lower temperature than that in the upper regions of the vessel when there is no recirculation flow. This colder water is forced up when recirculation pumps are started. This will not result is stresses which exceed ASME Boiler and Pressure Vessel Code, Section Ill limits when the temperature differential is not greater than 145 F.

The reactor coolant system is a primary barrier against the release of fission products to the environs. In order to provide assurance that this barrier is maintained at a high degree ofintegrity, restrictions have been placed on the operating conditions to which it can be subjected.

Appendix G to 10CFR50 defmes the temperature-pressurization restrictions for hydrostatic and leak tests, pressurization, and critical operation. These limits have been calculated for Pilgrim and are contained in Figures 3.6-1,3.6-2, and 3.6-3.

Revision 177 Amendment No. 45,56,71,93,133 B3/4.6-1

ATTACHMENT C i

Amended Technical Specification Paaes 3/4.6-1 and B 3/4.6-1 i

I LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.6 PRIMARY SYSTEM BOUNDARY 4.6 PRIMARY SYSTEM BOUNDARY Apf

_ licability: Applicability:

Applies to the operating status of the reactor Applies to the periodic examination and coolant system. testing requirements for the reactor cooling j system.

Objective: Obiective:

To assure the integrity and ssfe operation of To determine the condition of the reactor the reactor coolant system. coolant system and the operation of the safety devices related to it.

Specification: Specification:

A. Thermal and Pressurization Limitations A. Thermal and Pressurization Limitations

1. The average rate of reactor coolant 1. During heatups and cooldowns, temperature change during normal heatup with the reactor vessel temperature or cooldown shall not exceed 100 F/hr less than or equal to 450 F, verify when averaged over a one-hour period the RCS heatup and cocidown except when the vessel temperatures are rates are within limits every 15 above 450 F. minutes.

2. The reactor vessel shall not be 2. Reactor vessel shell temperatures, including pressurized for hydrostatic and/or leakage reactor vessel bottom head, and reactor tests, and subcritical or critical core coolant pressure shall be permanently operation shall not be conducted unless logged at least every 15 minutes whenever the reactor vessel temperatures are above the shell temperature is below 220*F and those defined by the appropriate curves the reactor vesselis not vented.

on Figures 3.6-1, 3.6-2, and 3.6-3. (Linear interpolation between curves is permitted).

At stated pressure, the reactor vessel j bottom head may be maintained at temperatures below those temperatures corresponding to the adjacent reactor vessel shell as shown in Figures 3.6-1 and 3.6-2.

Revision Amendment No. 287 82 7 440r463 3/4.6-1

DAllE:

3/4.6 PRIMARY SYSTEM BOUNDARY A. Thermal and Pressurization Limitations The allowable rate of heatup and cooldown for the reactor vessel contained fluid is 100 F per hour averaged over a period of one hour. This rate has been chosen based on past ~ ,

experience with operating power plants. The associated time periods for heatup and cooldown cycles when the 100 F per hour rate is limiting provides for efficient, but safe, q plant operation. j Specific analyses were made based on a heating and cooling rate of 100 F/ hour applied continuously over a temperature range of 100 F to 546 F. Calculated stresses were within ASME Boiler and Pressure Vessel Code Section III stress intensity and fatigue limits even at the flange area where maximum stress occurs.

The manufacturer performed detailed stress analysis as shown in Amendment 17 of the FS AR. This analysis includes more severe thermal conditions than those which would be encountered during normal heating and cooling operations.

The coolant in the bottom of the vessel is at a lower temperature than that in the upper l regions of the vessel when there is no recirculation flow. This colder water is forced up 4 when recirculation pumps are started. This will not result is stresses which exceed ASME Boiler and Pressure Vessel Code,Section III limits when the temperature differential is not greater than 145"F.

p The reactor coolant system is a primary barrier against the release of fission products to the environs. In order to provide assurance that this barrier is maintained at a high degree ofintegrity, restrictions have been placed on the operating conditions to which it can be subjected.

Appendix G to 10CFR50 defines the temperature-pressurization restrictions for hydrostatic and leak tests, pressurization, and critical operation. These limits have been calculated for Pilgrim and are contained in Figures 3.6-1,3.6-2, and 3.6-3.

Revision Amendment No.' 45, M, 71, ??,133 .

83/4.6-1.

k, ' ': , ' , , , .

l ATTACHMENT D CALC. NO. M-778. REV. 0 EVALUATION OR RPV FLANGE TO ADJACENT SHELL 145 DEG. F DIFFERENTIAL TEMPERATURE LIMIT 1

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