ML20036A730

Errata to Amends 102 & 104 to License NPF-29,consisting of Typo & Format Errors in TS Pages 3/4 4-9,3/4 4-10 & 3/4 6-3

ML20036A730
Person / Time
Site:	Grand Gulf
Issue date:	05/05/1993
From:	Oconnor P Office of Nuclear Reactor Regulation
To:
Shared Package
ML20036A731	List: ML20036A730
References
NUDOCS 9305140079
Download: ML20036A730 (3)

Text

.

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING COND! TION FOR OPERATION 3.4.3.2 Reactor coolant system leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE.

b.

5 gpm UNIDENTIFIED LEAKAGE.

c.

30 gpm total leakage.

d.

I gpm leakage at a reactor coolant system pressure of 1050 10 psig from any reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1.

e.

2 gpm increase in UNIDENTIFIED LEAKAGE within any 24-hour period or less (applicable in OPERATIONAL CONDITION 1 only).

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

J a.

With any PRESSURE B0UNDARY LEAKAGE, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With any reactor coolant system leakage greater than the limits in b and/or c, above, reduce the leakage rate to within the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

With any reactor coolant system pressure isolation valve leakage greater than the above limit, isolate the high pressur~e portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following ?.4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

d.

With one or more high/ low pressure interface valve pressure monitors and/or interlocks inoperable, restore the inoperable monitor (s) and/or interlock (s) to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

e.

With any reactor coolant system UNIDENTIFIED LEAKAGE increase greater than 2 gpm within any 24-hour period or less, identify the source of l

leakage increase as not. service sensitive Type 304 or 316 austenitic stainless steel within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

GPAND GULF-UNIT 1 3/4 4-9 Amendment No. 104 9305140079 930505 PDR ADOCK 05000416 P

PDR

• q-

~

REACTOR COOLANT SYSTEM l

SURVEILLANCE REQUIREMENTS 4.4.3.2.1 The reactor coolant system leakage shall be demonstrated to be i

within each of the above limits by:

i i

a.

Monitoring the drywell atmospheric particulate and gaseous l

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

l b.

Monitoring the drywell floor and equipment drain sump level and flow l

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

c.

Monitoring the drywell air coolers condensate flow rate at least once l

per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and j

i d.

Monitoring the reactor vessel head flange leak detection system at i

least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l 4.4.3.2.2 Each reactor coolant system pressure isolation valve specified in Table 3.4.3.2-1 shall be demonstrated OPERABLE by leak testing pursuant to Specification 4.0.5 and verifying the leakage of each valve to be within the specified limit:

l a.

At least once per 18 months, and b.

Prior to returning the valve to service following maintenance, repair or replacement work on the valve which could affect its leakage rate.

i The provisions of Specification 4.0.4 are not applicable for entry into j

OPERATIONAL CONDITION 3.

4.4.3.2.3 The high/ low pressure interface valves leakage pressure monitors shall be demonstrated OPERABLE with alarm and interlock setpoints per Table 3.4.3.2-2 and Table 3.4.3.2-3 by performance of a:

a.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and l

b.

CHANNEL CALIBRATION at least once per 18 months.

I GRAND GULF-UNIT 1 3/4 4-10 Amendment No. 2Gr104 z-

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION (Continued) b.

The combined leakage rate for all penetrations and all valves #

subject to Type B and C tests to less than or equal to 0.60 L, and c.

The leakage rate to less than 100 scf per hour for all four main steam lines through the isolation valves, and d.

The combined leakage rate for all containment isolation valves in hydrostatically tested lines which penetrate the primary containment to less than or equal to 1 gpm times the total number of such valves, prior to increasing reactor coolant system temperature above 200*F.

SURVEILLANCE RE0VIREMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4

- 1972:

a.

Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 i 10 month intervals

• during shutdown at P,,11.5 psig, during each 10-year service period.

b.

If any periodic Type A test fails to meet 0.75 L the test schedule for subsequent Type A tests shall be reviewed an,, approved by the d

Commission.

If two consecutive Type A tests fail to meet 0.75 L,,

a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 L,, at which time the above test schedule may be resumed.

The accuracy of each Type A test shall be verified by a supplemental c.

test which-1.

Confirms the accuracy of the test by verifying-that the containment leakage rate, L', calculated in accordance with

)

ANSI N-45.4-1972, Appendix C,, is within 25 percent of the contain:nent leakage rate, L,, measured prior to the introduc-tion of the superimposed leak.

2.

Has duration sufficient to establish accurately the change in leakage rate between the Type A test and the supplemental test.

3.

Requires the quantity of gas injected into the containment or bled from the containment during the supplemental test to be between 0.75 L, and 1.25 L,.

1. xcept for those that are hydrostatically leak tested.

E i

• The third Type A test within the first 10-year service period shall be con-ducted prior to startup following the sixth refueling outage. This is an exemption from 10 CFR Part 50, Appendix J Requiremente.

GRAND GULF-UNIT 1 3/4 6-3 Amendment No. 89,102