ML20080T286

Proposed Tech Specs Re Pressurizer Level Band

ML20080T286
Person / Time
Site:	Millstone
Issue date:	10/31/1983
From:	NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20080T270	List: B10913, Application for Amend to License DPR-65,revising Tech Specs Re Pressurizer Level Band ML20080T286
References
TAC-52504, NUDOCS 8310200233
Download: ML20080T286 (3)

Text

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Docket No. 50-336 I

Attachment 1 Millstone Nuclear Power Station, Unit No. 2 l Proposed Revisions to Technical Specifications J

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October,1983

' 8310200233 831012 PDR ADOCK 05000336

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REACTOR COOLANT SYSTEM PRESSURIZER LIMITING CONDITION FOR OPERATION '

3.4.4.1 The pressurizer shall be OPERABLE wl'th:

a.

A water volume greater than or equal to 525 but less than or equal to 1020 cubic feet (70%) cubicandfeet 65 %)

b. At least two groups of pressurizer heaters each having a capacity of at least 130 kW.

APPLICABILITY: MODES 1 2 and 3.

ACTION:

a.

With only one group of pressurizer heaters OPERABLE, restore at least two grouos to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the fo11owing 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

With the pressurizer otherwise inoperable, be in at least HOT STANDBY with the reactor trip breakers open within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. .

SURVEILLANCE RE0'JIREMENTS 4.4.4 The pressurizer water volume shall be determined to be within I

its limits at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

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REACTOR CODLANT SYSTEM BASES During cperation, all press rizer code safety valves must be OPE).ABLE to prevent the RCS from being pressurized cbove its safety limit of 2750 psia.

The combined relief capacity of these valves is sufficient tc limit the Reactor Coolant System pressure to within its Safety Limit of 2750 psia I following a complete loss of turbine generator load while operating at RATED THERMAL POWER snd assuming no reactor trip until the first Reactor Protective System trip setpoint (Pressurizer Pressure-High) is reached (i.e., no credit is taken for a direct reactor trip on the loss of turbine) and also assuming no operation of the pressuri.zer power operated relief valve or steam dump valves.

3/4.4.3 RELIEF VALVES - -

The power operated relief valves (PORVs) operate to relieve RCS pressure below the setting of the pressurizer code safety valves. These relief valves have rer.otely operated block valves to provide a positive shutoff capability should a relief valve become inoperable. The electrical power for both the relief valves and the block valves is capable of being supplied from an emer-gency power sourcq.to ensure the ability to seal this possible RCS leakage path.

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, 3/4.4.2 pRESSUR12ER l An OPERABLE pressurizer provides pressure control for the reactor coolant system 1, during operations with both. forced reactor coolant flow and with natural circulation flow. The minimum water level in the pressurizer assures the pressurizer heaters, which are required to achieite and maintain pressure control, remain covered with water to prevent failure, which occurs if the heaters are energized uncovered.

The maximum water level in the pressurizer ensures that this parameter is maintained within the envelope of operation assumed in the safety analysis. The maximum water level also ensures that the RCS is not a hydraulically solid system and that a steam bubble will be provided to accommodate pressure surges during operation.

i, The steam bubble also protects the pressurizer code safety valves and power operated

relief valve against water relief. The requirement that a minimum number of i pressurizer heaters be OPERABLE enhances the capability of the plant to control

. Reactor Coolant System pressure and establish and maintain natural circulation.

The requirement tha,t 130 kw of pressurizer heaters and their associated controls be capable of being supplied electrical power from an emergency bus provides assurance that these heaters can be energized. during a loss of off-site power condition to maintain natural circulation at HOT STANDBY.

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3/4.4.5 STEAM GENERATORS ~ ,-

The Surveillance Requirements for inspection of the steam generator tubes ensure that the structural integrity of this portion of the RCS will be main-l tained. The program for inservice inspection of steam generator tubes is '

based on a modification of Regulatory Guide 1.83 Revision 1. Inservice

inspection of steam generator tubing is essential in order to maintain surveillance of the conditions of the tubes in the event that there is MILLSTONE - UNIT 2 8 3/4 4-2 ,

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