ML20090E242

Marked-up Proposed Tech Specs,Clarifying Leak Rate Testing of Seal Sys Fluid Pressurized Valves

ML20090E242
Person / Time
Site:	Callaway
Issue date:	07/17/1984
From:	UNION ELECTRIC CO.
To:
Shared Package
ML20090E240	List: ML20090E237 ML20090E242
References
NUDOCS 8407190363
Download: ML20090E242 (7)

Text

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'h ENCLOSURE C

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MARKED TECHNICAL SPECIFICATIONS AND BASES J

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REVisl0N 8 i 4'iVERPRESSURE l9ROTECTI0ft SYSTEMS =N 4 ($\ g ' '

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LM11TitlG C0t1DITI0ti FOR C! ERAT 10t4

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3.4.9.3 At least one of the S f,ollavi,ogfverpressure Protection Systems small be OPERABLE:

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a. Two residual heat removai (RHR) suction relief valves each with a Setpoint of 450 psig, C, or 1

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. b. Two power-operated relief valves (PORVs) with Setpoints which do not exceed the limit established. in Figura 3.4-4, or t

c. The Reactor Coolant Sys'em (R53) depressurized with an RCS vent of greater than or equal to 2'3quaie inches.

APPLICABILITY: MODE 3 when the temperature of any RCS cold leg is less than or equal to 368 F, MODES 4 and S, and MODE 6 with the reactor vessel head on.

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a. .!ith one PCRV wt one RHR suction reliof valve iny 21, either rutore two PORVs or two RHR suction ' relief valves to OPERABLE status within 7 days or <1epressurize and vent the RCS through at least a 2 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

b. With both PORVs and bott' RHR suction relief valves inoperable, depressurize and- not the RCS through at least a 2 square inch vent within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

c. In the event t"a 20RVs, or the PHR suction relief 9alves, or the RCS vent (s) are'used to mitigate an PCS pressure f.ransient, a Special Repor( shall be prepared and s'ibmit.ted to the Commission pursuant to Specification 6.9.2. within 30 days. The report shall describe the~ circumstances initiating the transient, the effect of the PORVs,'or the RHR< suction relief valves, or RC5 vent (s) on the transient, and ary corrective action necessary to prevent recurrence.

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d. The p.' avis 40ns c( SM cification 3.0.4 are not applicable.

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ULNRC-875 7/17/84 i

CONfAlflMEf1T SYSTEMS SjlRVE!LLANCE REGUIREMENTS (Centinued)

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

1) Confirms the accuracy of the test by veri fying that the supple-mental test result, L , minus the sum of the Type A and the superimposed leak, 9L , is equal to or less than 0.25 L ,

2) Has a duration sufficient to ettablish accurately tne change in leakage rate between the Type A test and the supplemental test.

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3) Requires that the rate at which gas is injected intn the contain-ment or bled f rom the containment during the supplemental test is between 0.75 La and 1.25 La '

d. Type B and C tests shall be conducted with gas at a pressure not less than P , 48 psig, at intervals no greater than 24 months except for tests involving:

1) Air locks, and

2) Purge supply and exhaust isolation valves with resil.ient material seals.

INSE RT A

e. Air locks shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.3;

f. Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE by the requirements of Specifications 4.6.1.7.2 and 4.6.1.7.4, as applicable; and

g. The provisions of Specification 4.0.2 are not applicable.

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3/4.6.1 J RIMARY LONTAINMENT

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Primary CONTAINMENT INTEGRITY engdes that the release of radioactive materials from the containment atmosphere wil1 be restricted to those leakage paths and ' ass'oiiated leak rate's iss'umed in the: safety arealyses. This

- restriction,,in conjunction with die leakage . rate limitation, will limit the i t' L . SITE 80VNDART N radiation doses,to within the dose (uideline values of 10 CFR Part 100 during accident conditions.

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, 3/4.6.1.2 CONTA?NMENTLEdKAGE f -

d The limitatiors on contsinment leakage rates ensure that the total contai.nment leakage' volume will not exceed the value assumed in the accident agalyses, at the peak accident pressure, P,. As an added conservatism, the

' measured'ove#rall' integrate 0 leakage rate is further limited to less than or L equal to'O.75 L, or 0.75 Lt, as applicable, during performance of ^he periodic 4 , test to account for possible degradation of the containment leakage barriers betwe n leakage testi./

f The' surveillance testing for measuring leakage rates are consistent with the requiremdnts of Appendix J of 10 CFR Part 50.

- .INSE RT C, 3/4.6.1.3 'C'ONTAINMENT AIR 1.0CKS The' limitations'on closure and leak rate. for the containment air locks are required to meet the restrictions on CONTAINMENT INTEGRITY and containment leak rate. Surveillance testing of the air lock seals provides assurance that the overale air lock leakage will not become excessive due to seal damage during the intervals between air lock leakage tests.

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CALLAWAY - UNIT 1 8 3/4 6-1

,E ULNRC-875 7/17/84 INSERT A ENCLOSURE C

3) Valves pressurized with fluid from a seal system.

INSERT B ENCLOSURE C

h. Leakage from isolation valves that are sealed with fluid from a seal system may be excluded, subject to the provisions of Appendix J,Section III.C.3e when determining the combined leakage rate provided the seal system and valves are pressurized to at least 1.10 Pa (53 psig) and the seal system capacity is adequate to maintain system pressure for at least 30 days.

INSERT C ENCLOSURE C The Essential Service Water Penetrations are tested as valves which have seal water applied. The system acts as a passive source of seal water and is consistent with the requiremen*s of Appendix J of 10 CFR Part 50, Paragraph III.C.3. This supply is a 30 day supply for leak rates < 7500 cc/hr.

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SNUPPS ENCLOSURE D ULNRC-875 7/17/84 atmosphere into the secondary side of the steam generators. This requirement will be included in the Emergency Operating Instructions.

The test equipment to be usad during the Type C tests will con-sist of a_ connection to an air supply source, a holding vessel, a pressure regulator, an absolute pressure gage, a flow indicator, and associated valving.

Iw)lation valves will be positioned to their post-accident position by the normal method with no accompanying adjustments.

Fluid systems are properly drained and vented with the valves aligned to provide a test volume and atmospheric air back pres-sure on the isolation. valve (s) being tested.

INSERT The test volume and holding vessel are pressurized to the test pressure Pa, as specified in Chapter 16.0. The pressure regulator (s) maintain the test volume at a minimum of Pa. The air flow rate into the test volume is recorded, as is the pressure reading, at the intervals specified on the data form. These records are utilized to determine the leakage rate in cubic centimeters per minute.

For larger test volumes, a pressure decay method may be utilized

- to determine the leakage rate.

The total leakage rate for Type B and C tests must be less than 0.6 L

• a The criteria for determining the direction in which the test pressure is applied to the isolation valves are as follows:

Gate Valves Parallel disc a. Test in the DBA direction.

b. Testing can be performeo between the discs if a test connection or drain is provided in the valve design.

Flexible wedge a. Test in the DBA direction.

b. Testing can be performed between the wedge sections if a test connection or drain is provided in the valve design.

Solid wedge a. Test in the DBA direction.

Globe Valves If the DBA flow direction is over'the disc (flow to close),

the valve may be tested in the 6.2.6-6 L

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ULNRC -875 7/17/84 INSERT TO ENCLOSURE D The essential service water penetrations are tested as valves which have seal water applied. The system acts as a passive source of seal water and is consistent with the requirements of Appendix J of 10 CFR Part 50, Paragraph III.C.3.

This supply is a 30 day supply for leak rates less than or equal to 7500 cc/hr.

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