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Proposed Tech Specs,Revising Max Individual MSIV Leak Rate Acceptance Criteria of 11.5 Scfh to Overall Criteria That Encompasses Four Main Steam Lines Into One Limit of 46 Scfh
	ML20087J425
Person / Time
Site:	Monticello
Issue date:	08/15/1995
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20087J418	List: ML20087J416; ML20087J421; ML20087J425;
References
	NUDOCS 9508210146
	Download: ML20087J425 (11)
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i a .I Exhibit B --

' Monticello Nuclear Generating Plant ,

. License Amendment Reauest Dated Au' aust 15.1995 ;

p, - Technical Specification Pages Marked Up 1

p. ' with Proposed Wording Changes .-

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Exhibit B consists of the ex' sting TechnicC 3pecification pages marked up with the proposed changes. Existing pages a'fected by this change are listed below: . -

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3.0 LIMITING CONDITION FOR. OPERATION -

4.0 SURVEILLANCE REQUIREMENTS C. Containment' Spray / Cooling System C. Containment _ Spray / Cooling System '

[: 1. . ' Except as ' specified in 3.5.C.2, 3 and 4 ' below, 1. Demonstrate the RHR Service Water pumps both Containment Spray / Cooling Subsystems ~. F

'shall be operable whenever irradiated fuel is develop 3,500 gym flow rate:against a 500 ~J ft head when tested pursuant to-

'in the reactor vessel and reactor water 2-. .

Specification 4.15.B.

l temperature is greater than 212*F. A - ~-(

} containment / spray cooling subsystem consists. 2. Test the valves in accordance with- )'

of the following equipment powered from one fy

-Sgecification 4.15.82

_(-

division: -

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)_ 3. Demenstrate th operability of..the'drywell 2 RilR Service Water Pumps i Heat Exchanger spray hea aa nozzles.with an. air test '( ); J1 2 RIIR Pumps" during e h y ye r period.

Valves and piping necessary for:

ci Torus Cooling Drywell Spray 2.

One-RilR Service Water Pump may be inoperable for 30 days.

3. One RilR Service: Water Pump.in:each subsystem l may be inoperable for 7 days.

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4. One Containment' Spray / Cooling Subsystem may be inoperable . for . 7 days.

5. If the_ requirements of 3.5.C.1, 2, 3 and 4 cannot be met, an orderly shutdown of the reactor will be initiated and'the reactor- :

/ water. temperature shall be reduced to less

- than 212'F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . #

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For allowed' out of: service times for the RllR pumps see Section 3.5.A. '

3.5/4.5: .

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS

2. Primary Containment Integrity 2. ' Primary Containment Integrity ~ -

a. Primary Containment Integrity, as defined in a. Primary Containment Integrity shall Section 1, shall be_ maintained at all times be demonstrated after each closing when the reactor is critical or when the reactor of each penetration subject to Type B water temperature is above 212*F and fuel is in testing, if opened following a Type A the reactor vessel, except when performing low power physics tests at atmospheric pressure or Type B test, by leak rate testing g

'the seal with gas at > Pa, 42 psig, during or after refueling at power levels not *'

and verifying that when the measured 4 to exceed 5 MW(t). Without Primary Contain:,ent leakage rate for these seals is added Integrity, restore Primary Containment Integrity to the leakage rates determined pursuan within one hour or be in at least ilot Shutdown to Surveillance Requirement 4.7.A.2. .

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within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Cold. Shutdown for all other Type B and C penetration ,

within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . the combined leakage rate is less than or equal to 0.6La.

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3.0 LIMITINC CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

b. When Primary Containment Integrity is required, b. The primary containment leakage rates leakage rates shall be limited to: shall be demonstrated : th; felle ir.g in au.cA.us idab de +est- schedule 2nd rh:11 5: f: :--in; e f

1. An overall integrated leakage rate of less ir m.f: = :r : ci" the criteria, methods (

than or equal to La, 1.2 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at Pa, and provisions of 10 CFR Part 503 rQpma ! d os.s mochfrial by groweA sf emyTbc [.

42 psig. s O&rel

1. % ee Type A overall integrate

2. A combined leakage rate of less than or equal cont ent leakage rate t shall to 0.6La for all penetrations and valves, be condu at 40110 h intervals *

-- rpt f-- --i eter- i r r ! - *- i r - --! rr, during shutdo a _ a during each subject to Type B and C tests when pressurized 10-year servi od. The third-test of e set shal conducted to Pa 42 9513 3 4L duri e shutdown for t2 0-year

3. Less than or equal to 11.5 scf per hour or nPi nt inservice inspection.

m y ene main steam isolation valveSwhen tested Deltrel at25psg. 2. any periodic Type A test fails meet 75La, the test schedul or With the measured overall integrated primary subseque pe A tests sh be containment leakage rate exceeding 0.75La, or the reviewed an roved the Commission.

measured combined leakage rate for all penetrations If two consecuti e A tests fail to and valves, except --la ste?- ircl2 tie- "cl-_ . ., meet 0.75La, a e t shall be W ype B and C' testing exceed [n.6La, or I N

performed a east every onths until the measgree leak rate exceeding 11.; Ttf per hour two con utive Type A tests m 0.75La, for en? e main steam isolation valvd restore at w c time the above test sche le leakage rates to less than or equal to these values be resuged.

prior to increasing reactor coolant system temper- e.\s-T e, d ature above 212*F or, alternatively, restore 3. e A test leakage rates s measured leakage rates to within these limits within calculat. observ

a converted one hour or be in at least Hot Shutdown within the to absolute va , analyses next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Cold Shutdown within the shall ormed to select -

ced following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . integrated leakage measuremen m.

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1 ie test of the seco car Coynbme,b YY\ab mtAm Dtd o service periot onducted during th te ueling. outage.

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3.7/4.7 159 i"? :1/ l

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3.0 LIMITING CONDITIONS FOR OPERATION '

4.0 SURVEI1 g CE REQUIREMENTS 05 elat cA

4. e accuracy of each Type A test shall b '

ve led by a supplemental test which:

a. Con s the accuracy of the at by verify that the differen between the supp ental data and a Type A

., test data within 0.2 , and n

b. Ilas duration su e nt to establish accurately the ch e in leakage rate between the Typ At and the suppla-mental test, d

c. Requires ne rate of gas in ted into t containment or bled a the cont nment during the supplemen to be limited between 75 to 1

5. Typ: 5 :nd C :::: :h 11 h nat.: .d li;.

s.. i i - t : 1. . fu: ling ch :te: -- (; xixx int:r;;l f 2'. ::nd ),

creept f:: t::t: ir::1 ring th: ::in

:: lin: 1::1 ti:n e:1ver. Main steam isolation valve tests shall be conducted with gas at > 25 psig 22:5 IS : nth:. A

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a. .u_ :.:,.:.:_:_:,, _:.n_,: _:: _ a.,r._ r_ _. :n y ; 7 texte. leakage rate of < 11.5 auf per

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hour sh be demonstrated for +aek main steam ne' isolation valves, 0 .11 CDYn Nsnek vvw d wav M Mota ycth

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3.//4.7 160

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3.0 1.IMITING CONDITIONS FOR OPERATION 4.0 SURVEli.IANCE REQUIREMENTS

c. When Primary Containment Integrity is required, c. The primary containment airlock shall be

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the primary containment airlock shall be operable demonstrated operable:

with:

1. At ;;;h refueling sh td;-n, ;nd et

1. Both doors closed except when the airlock is . 6 ~..;.h being used, then at least one airlock door ..du; ting let.r. 1; there.fter, n ;;;;;11 hy:g:

eirl:25 1:22 shall be closed, and s.

t;at et i_,_"; and 3;_;;;tr; ting th:t

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2. An overall airlock leakage rate of less than 5b$b5I .iS bEbb bt$NEl b;y 50-or equal to 0.05La at Pa or 0.007La at 10 psig. esi...d:d up t; th; ::t ::ft: ling cut g:. (up t; e .;21 _ int.r. 1 With the primary containment airlock inoperable, 5:t2 :r :::t: :t ?; cf 25 ::xthe) maintain at least one airlock door closed and if ther; hav b : n: cir 12:5 :;:n*ng>

restore the airlock to Operable status within 'n : th: 12:t :::::::ful t::: et ";.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least Hot Shutdown within beleM the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Cold Shutdown within 2. er each opening by conducting the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . over airlock leakage test

> 10 psig d verifyin eskage rate is < 0. h the airlock is being used iple openings, b 7 iecSormio 3 this tes not requi after each b ac.c.edwe. tdrb 3 Meca\\ Sc\ock The schdde. d leah e TbT ope , but shall be perfo ast once per 72 houra.

at C riTecton e4- 10 C.FR ParT So 1 %P,eJtt % 3. At six month intervals by verifying af, m e A*t y, d b y a p reo d 2 1.e m P Tso n s. that only one door can be opened at a time. If the airlock has not been used since.the last door interlock test, this test is not required.

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d. The interior surfaces of the dryvell shall )

be visually inspected each operating cycle ['

for evidence of deterioration. )

b s ~1. 7/4. 7 161 -

NEXT PAGE IS PACE 163 -Er? 110 2/23/oS L _ __ _- _ _--------_ _ _ -- - ---_-- - - - -

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Exhibit C

' Montice!!o Nuclear Generating Plant License Amendment Reauest Dated Auaust 15.1995 Revised Monticello Technical Specification Pages Exhibit C consists of revised Technical Specification pages that incorporate the proposed --

changes._ The pages included in this exhibit are as listed below. Note that due to removal of' specific material and the resulting reconciliation, page 161 is no longerincluded.

Paoe 104 158 159 160

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, 3.0 LIMITING CONDITION FOR OPERATION .4 '. 0 . :SURVEILIANCE REQUIREMENTS -

.C. Containment Spray / Cooling System C. Containment Spray / Cooling' System . 'E

l. Except as specified in 3.5.C.2.13 and 4 below, 1. Demonstrate the RHR Service Water pumps- -v

-both Containment _ Spray / Cooling Subsystems develop 3.500.gpa flow rate.against;a-500~

shall be operable whenever irradiated fuel:is ft head when tested pursuant to-

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in the reactor vessel and reactor water Specification 4.15.B.. .

temperature is greater than .212*F. A containment / spray cooling subsystem consists 2. Test the valves in accordance with" of- the following equipment. powered from.one Specification 4.15.B.

division:

3. Demonstrate the operability of.the drywell~

2 RHR Service Water Pumps spray headers and nozzles with an air, test 4 1 Heat Exchanger during each 10 year period. l.

2 RHR Pumps

Valves-and piping necessary for:

" Torus Cooling Drywell Spray

2. One RHR Service Water Pump may be inoperable for 30 days.

3. One RHR Service Water Pump'in each subsystem '

may be inoperable for 7 days.

4. One Containment Spray / Cooling Subsystem may be inoperable.for 7 days.

5..If-the requirements of 3.5.c.1, 2,-3 and 4 cannot be: met,:an orderly-shutdown of the

reactor willLbe' initiated and the reactor water temperature shall be reduced to less' than 212*F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ForLallowed out of service times for the RHR pumps see Section 3.5.A.

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3.5/4.~5 s104

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3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

2. Primary Containment Integrity 2. Primary Containment Integrity

a. Primary Containment Integrity as defined a. Primary Containment Integrity shall .

in Section 1, shall be maintained at all be demonstrated after each closing times when the reactor is critical or of each penetration subject to Type 'B when the reactor water temperature is testing, if opened following a Type A above 212*F and fuel is in the reactor or Type B test, by leak rate testing vessel, except when performing low power the seal with gas at 2 Pa, 42 psig, physics test at atmospheric pressure and verifying that when the measured during or after refueling at power levels leakage rate for these seals is added not to exceed 5 MW(t). Without Primary to the leakage rates determined pursuant Containment Integrity, restore Primary to Surveillance Requirements 4.7.A.2.b l Containment Integrity within one hour or for all other Type B and C penetrations, be in at least Hot Shutdown within the the combined leakage rate is less than next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and Cold Shutdown within or equal to 0.6La.

the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.7/4.7 158

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3.0 LIMITING CONDITIONS FOR OPERATION- 4.0 SURVEILIANCE REQUIREMENTS

b. When Primary Containment Integrity is required, b. The primary containment leakage rates shall be '

leakage rates shall be limited to: demonstrated in accordance with the schedule, criteria, methods, and provisions of 10 CFR

1. An overall integrated leakage rate of less Part 50, Appendix J as modified by approved than or equal to IA,1.2 percent by weight exemptions:

of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at Pa, 42 psig. 1. Deleted

2. A combined leakage rate of less than or 2. Deleted equal to 0.6La for all penetrations and valves, subject to Type B and C tests when 3. Deleted pressurized to Pa, 42 psig.

4. Deleted

3. Less than one or equal to 46 scf per hour combined maximum flow path leakage for all 5. Main steam isolation valve tests shall be main steam isolation valves when tested at- conducted with gas at 2 25 psig. A 25 psig. combined maximum flow path leakage rate of

<; 46 scf per hour shall be demonstrated for With the measured overall integrated primary all main steam line isolation valves.

containment leakage rate exceeding 0.75La, or the measured combined leakage rate for all penetrations and valves, subject to Type B and C testing exceeding 0.6La, or the measured combined maximum flow path leak rate exceeding

.46 scf per hour for all main steam isolation valves, restore leakage rates to less than or equal.to these values prior to increasing reactor coolant system temperature above 212*F or, alternatively, restore measure leakage rates to within these limits within one hour or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Cold Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

159 3.7/4.7

s 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS

c. When Primary Containment Integrity is required, c. The primary containment airlock'shall be the primary containment airlock shall be demonstrated operable:

operable with:

1. By performing overall airlock leakage test

1. Both doors closed except when the airlock in accordance with the schedule and is being used, then at least one airlock criterion of 10 CFR Part 50, Appendix J, door shall be closed, and as modified by approved exemptions.

2. An overall airlock leakage rate of less 2. Deleted than or equal to 0.05La at Pa or 0.007La at 10 psig. 3. At six month intervals by verifying that only one door can be opened at With the primary containment airlock a time. If the airlock has not been inoperable, maintain at least one airlock door used since the last door interlock closed and restore the airlock'to Operable test, this test is not required.

status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Cold d. The interior surfaces of the drywell shall Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . be visually inspected each operating cycle for evidence of deterioration.

3.7/4.7 160 NEXT PAGE IS PAGE 163

ML20087J425

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