ML20203D041

Proposed Tech Spec 3.4.9.1.C Re RCS Pressure/Temp Limits

ML20203D041
Person / Time
Site:	North Anna
Issue date:	07/11/1986
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML20203D032	List: ML20203D027 ML20203D041
References
NUDOCS 8607210125
Download: ML20203D041 (3)

Text

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i Attachment 1 Proposed Technical Specifications Change Unit 1 1

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i 860721012S 860711 PDR ADOCK 0D000338 P PDR m

REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4-2 and 3.4-3 during heatup, cooldown, criticality, and inservice leak and hydrostatic testing with:

a. A maximum heatup of 60*F in any one hour period.

b. A maximum cooldown of 100*F in any one hour period.

c. A maximum temperature change of less than or equal to 10*F in any one hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.

APPLICABILITY: At all times.

ACTION:

With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System; determine that the Reactor Coolant System remains acceptable for continued operations 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 reduce the RCS T and pressure to less than 200*F and 500 psig, respectively, within the folfo"81ng 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown,and inservice leak and hydrostatic testing operations.

4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, at the intervals required by 10 CFR 50, Appendix H. The results of these examinations shall be used to update Figures 3.4-2 and 3.4-3.

NORTH ANNA - UNIT 1 3/4 4-26 Amendment No.

ATTACHMENT 2 Description of Amendm'ent Request:

The proposed amendment would reinstate Specification 3.4.9.1.c which was erroneously deleted via License Amendment No. 74. Specification 3.4.9.1.c specifies: "a maximum temperature change of less than or equal to 10*F in any one hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves." An identical requirement is contained in North Anna Unit 2 Technical Specifications, and Station Operating Procedures for both units contain the necessary restrictions on temperature changes during inservice hydrostatic and leak testing.

Basis for No Significant Hazards Determination:

The proposed change does not involve a significant hazards consideration

because operation of North Anna Unit 1 in accordance with this change would not

(1) involve a significant increase in the probability or consequences of an accident previously evaluated. The change merely reinstates a previously existing license requirement that was erroneously deleted via a previous amendment and that continues to be satisfied through Station Operating Procedures. Therefore, this change cannot increat e

the probability or consequences of an accident.

(2) create the possibility of a new or different kind of accident from any accident previously analyzed. The proposed change does not involve any changes to plant design or operations and therefore cannot create the possibility of a new or different kind of accident.

(3) involve a significant reduction in a margin of safety. The proposed change merely reinstates a previously existing license requirement which was erroneously deleted via a previous amendment and therefore cannot reduce the margin of safety.

Therefore, it has been concluded that the proposed change does not involve a significant hazards consideration. Further, and for the same reasons as stated above, it has been determined that the proposed change does not involve an unreviewed safety question as defined in 10 CFR 50.59.

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