ML20045G609

Proposed TS 4.0.d Re Recording Unidentified & Identified Leakage Rates & 3/6/4.6 Re Analyzing Grad Samples of Primary Containment Atmosphere Once Per 12 H

ML20045G609
Person / Time
Site:	Monticello
Issue date:	07/07/1993
From:	NORTHERN STATES POWER CO.
To:
Shared Package
ML20045G604	List: ML20045G603 ML20045G606 ML20045G609
References
NUDOCS 9307140193
Download: ML20045G609 (6)

Text

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Exhibit B Monticello Nuclear Generating Plant License Amendment Reauest Dated July 7. 1993 '

Technical Specification Pages Marked Up with Proposed Wording Changes. ,

Exhibit B consists of the existing Technical Specification pages marked up with the proposed changes. Pages affected by this change are listed below:

Revised Page 126 Added Page 126a a

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3.0 LIMITING CONDITICNS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS D. Coolant Leakage D. Coolant Leakage

1. Any time irradiated fuel is in the react 1. An time irrad ated fuel is in the reactor vessel and oolant tem ure i ab ve 2 F, 1 nd ant tem era is above ase on e

,be carrie inc s rvei ance program reactor goo ant sys em re~

sump monitoring, th 11 e . clite to: s ou't :

. 3m IJnidentified Le a. nidenti d ans;l Identified Leakpge ure rateso _shall

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t e s ur e of nerease rs or 1 i te an order s ut own o e a. Pri ary containment at here' rticulate reactor an less than 12 F r with[n uce r f4 oc' hours.ater c- temperature to mon torin systems-per ance ho asbnsor a c annel heck.at eaot once er s, ncti na st at as mont an a

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS

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Exhibit C  ;

Monticello Nuclear Generating Plant 1,1 cense Amendment Reauest Dated July 7. 1993 I

I vised Monticello Technical Specification Pages i

Exhibit C consists of revised Technical Specification pages that incorporate ,

the proposed changes. The pages included in this exhibit are Revised Par.e i

126 Added Pace.

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l- 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS i D. Coolant Leakage D. Coolant Leakage }

1. Any time irradiated fuel is in the reactor 1. Any time irradiated fuel is in the reactor i vessel and coolant temperature is above 212 F, vessel and coolant temperature is above reactor coolant system leakage, based on sump 212 F, the following surveillance program monitoring, shall be limited to: shall be carried out:

a. 5 gpm Unidentified Leakage a. Unidentified and Identified Leakage

b. 2 gpm increase in Unidentified rates shall be recorded once per shift Leakage within any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period not to exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> using primary

c. 20 gpm Identified Leakage containment floor and equipment drain

d. no pressure boundary leakage sump monitoring equipment.

2. With reactor coolant system leakage greater than 2. The reactor coolant system leakage ,

3.6.D.l.a or 3.6.D.l.c above, reduce the leakage detection systems shall be demonstrated rate to within acceptable limits within four OPERABLE by: ,

hours or initiate an orderly shutdown of the reactor and reduce reactor water temperature to a. Primary containment atmosphere less than 212 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. particulate monitoring systems- t performance of a sensor check at least

3. With an increase in Unidentified Leakage in once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, a channel t excess of the rate specified in 3.6.D.l.b, functional test at least monthly and a t identify the source of increased leakage within channel calibration at least once per four hours or initiate an orderly shutdown of cycle.

the reactor and reduce reactor water temperature .

to less than 212 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. b. Primary containment sump leakage j q measurement system-performance of a l' l 4. If any Pressure Boundary Leakage is detected sensor check at least once per shift when the corrective actions outlined in 3.6.D.2 not to exceed 12. hours and a channel j and 3.6.D.3 above are taken, initiate an orderly calibration test at least once per shutdown of the reactor and reduce reactor water cycle.  ;

temperature to less than 212 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

1 i

3.6/4.6 126 i

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 5.

.Any time irradiated fuel is in the reactor

• vessel and reactor water temperature is above

, 212'F at least one of the leakage measurement

. instruments associated with each sump shall be i operable. If-no leak rate measurement instru-ments' associated with a sump are' operable, then:

a. Perform manual leak rate measurements once

.per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and restore a measurement instrument to operable status within 30 days.

b. Otherwise, initiate an orderly shutdown of the reactor and reduce reactor water temperature to less than' 212 F. within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

6. Any time irradiated fuel is in the reactor I vessel'and reactor water temperature is above ,

212 F the drywell- particulate radioactivity

• monitoring system shall be operable. If the drywell particulate radioactivity monitoring system is not operable, then:  ;

a. Analyze grab samples of the primary. I containment atmosphere once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

4

b. Otherwise, initiate an orderly shutdown of the reactor and reduce reactor water '

temperature toi less than 212 F within 24 i

hours.

3.6/4.6 126a

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