Text

Proposed Tech Specs,Requiring Valves to Be Tested at Pressure Greater than or Equal to Calculated Peak Containment Internal Pressure Re Design Basis LOCA
	ML20063C994
Person / Time
Site:	Monticello
Issue date:	01/26/1994
From:	; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20063C961	List: ML20063C956; ML20063C982; ML20063C994;
References
	NUDOCS 9402070276
	Download: ML20063C994 (7)
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d OO 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS OM nM 70> b. When Primary Containment Integrity is required, b. The primary containment leakage rates o4 leakage rates shall be limited to: shall be demonstrated at the following UUh test schedule and shall be determined -

80 1. An overall integrated leakage rase f less in conformance with the criteria, methods, !?

Tho u than or equal to La, 1.2 percent by weight and provisions of 10 CFR Part 50:

jy> of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at Pa, ?' .

u 42 psig.

1. Three Type A overall integrated

2. A combined leakage rate of less than or equal containment leakage rate tests shall to 0.6La for all penetrations and valves, be conducted at 40110 month intervals

except for main steam isolation valves, during shutdown at >Pa during each subject to Type B and C tests when ressurized 10-year service period. The third to Pa. test of each set shall be conducted 25b3 s during the shutdown for the 10-year

3. Less than or equal t abb-9 scf per hour for plant inservice inspection.

an sin steam i o a on valve when tested j at m5 pai. 2. If any periodic Type A test fails to p>s R. 4_7 PS 3 meet 0.75La, the test schedule for With the measured overa ntegraved primary subsequent Type A tests shall be containment leakage r.ste exceeding 0.75La, or the reviewed and approved by the Commission.

measured combined leakage rate for all penetrations If two consecutive Type A tests fail to and valves, except main steam isolation valves, meet 0.75La, a Type A test shall be subject to Type B and C testing e ing 0.6La, or performed at least every 18 months until the measured leak rate exceeding 44-4h cf per hour two consecutive Type A tests meet 0.75La, I for any one main steam isolatio a ve, restore at which time the above test schedule leakage rates to less than or ual to these values may be resumed.

prior to increasing reactor olant system temper- +

ature above 212*F or, alter tively, restore 3. All Type A test leakage rates shall be measured leakage rates to ithin these limits within calculated using observed data converted one hour or be in at lea Hot Shutdown within the to absolute values. Error analyses next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Co d Shutdown within the shall be performed to select a balanced following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . integrated leakage measurement system.

The second test of the second 10-year

-- 25T.?5 service period may be conducted during the 1989 refueling outage.

3.7/4.7 159 ntm 199 11/7/R9

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V 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILIANCE REQUIREMENTS

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

a. Confirms the accuracy of the test by verifying that the difference between the supplemental data and the Type A test data is within 0.25La, and

b. lias duration sufficient to establish accurately the change in leakage rate between the Type A test and the supple-mental test, and

c. Requires the rate of gas injected into the containment or bled from the containment during the supplemental test to be limited between 75 to 125% '

of La.

5. Type B and C tests shall be conducted h with gas at > Pa at each refueling shutdown (maximum interval of 24 months),

except for tests involving the main steam line isolation valves. Hain steam isolation val hall be conducted with gas at __ +- ach 18 months. A combined le e of < 0.6La shall be demonstr d for all penetrations and valves, e ept for main steam line isola-tion val s, subject to' Type dC tests. A leakage rate of < L1-r5- cf per hour all be demonstrated for each main ste m line isolation valve.

25. *b 3.//4.7 160

--R EV li G 2/15/59 -

q .

V .

f Bases Continued:

While the design of the Monticello plant predates 10 CFR Part 50, Appendix J, " Primary Reactor C)

Containment Leakage Testing for Vater-Cooled Power Reactors," testing substantially conforms to the (

requirements of Appendix J. The design of the plant was thoroughly reviewed to determine where

)

compliance with Appendix J was impossible or impractical. In each case where a departure from the (

requirements of Appendix J was identified, a request for exemption from the requirements of Appendix >

J or a plant modification was proposed and submitted for NRC Staff review. Exemptions were proposed )

in those cases where compliance with Appendix J would have provided no meaningful improvement in (

plant safety. >

(

In their review of Appendix J compliance (1) , the NRC Staff approved a number of exemption requests, >

denied others, and provided necessary interpretation and clarification of the requirements of Appendix J. The Technical Specification surveillance requirements reflect the results of this

(

review. .

Exemption from the requirements of. Appendix J was provided in the following areas: ,

(

a. 1esting of valves sealed by water

b. Lev pressure tc bleg of = in st == line inclatica valves-b Af. Low pressure testing of the primary containment airlock <

C /.IReduced airlock testing frequency when the airlock is in frequent use >

(s The Monticello airlock is tested by pressurizing the space between the inner and outer doors.

Individual door seal leakage tests cannot be performed. Since the inner door is designed to seat ('

with containment pressure forcing the door closed, special bracing must be installed for each ~(,

leakage test. The outer door must be opened to install and remove this bracing. Because of the ( ;

complexity of this operation, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 'may be necessary to perform a leakage test. )

~(

)

(

)

(1) Letter from.D C Eisenhut, Director, Division of Licensing, USNRC, dated June 3,1984, " Safety (

)

Evaluation by the Office of NRR, Appendix J Review".

{

4.7 BASES NEXT PAGE IS PAGE 188 184 REV 100 11/25/07--

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i Exhibit C Monticello Nuclear Generating Plant License Amendment Recuest Dated January 26, 1994 f i

Revised 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 y --

I 4

159 l 160 i 184 ;

4 i

P

'l

'l .

1'

.s 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

b. When Primary Containment Integrity is b. The primary containment-leakage rates -i required, leakage rates shall be limited to: shall be demonstrated at the following test schedule and shall be determined in

1. An overall integrated leakage rate of less conformance with the criteria, methods, than or equal to L.,1.2 percent by weight and provisions of 10 CFR Part 50:

of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P.,

42 psig. 1. Three Type A overall integrated ;

containment leakage rate tests shall j i

2. A combined leakage rate of less than or be conducted at 40110 month' equal to 0.6L, for all penetrations and intervals

during shutdown at 2P.

valves, except for main steam isolation during each 10-year service period.

valves, subject to Type B and C tests when The third test of each set shall be pressurized to P . conducted during the shutdown for the '

10-year plant inservice inspection.

3. Less than one or equal to 25.3 scf per hour -;

for any one main steam isolation valve when 2. If any periodic Type A test fails to tested at P., 42 psig, meet 0.75I,, the test schedule for subsequent Type A tests shall be With the measured overall integrated primary reviewed and approved by the containment leakage rate exceeding 0.751, or Commission. If two consecutive Type the measured combined leakage rate for all a tests fail to meet 0.75Lg, a Type A penetrations and valves, except main steam test shall be perfcrmed at least-isolation valves, subject to Type B and C every 18 months until two consecutive testing exceeding 0.61,, or the measured leak Type A tests meet 0.75Ls, at which rate exceeding 25.3 sef per hour for any one time the above test schedule may be l main steam isolation valve, restore leakage _

resumed.

rates to less than or equal to these values j '

prior to increasing reactor coolant system 3. All Type A test leakage rates shall temperature above 212*F or, alternatively, be calculated using observed data restore measure leakage rates to within these converted to absolute values. Error limits within one hour or be in at least Hot analyses shall be performed to select Shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 'and in Cold a balanced integrated leakage Shutdown within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . - measurement system.

"The second test of the second 10-year service period may be conducted during the 1989 refueling outage.

3.7/4.7 159

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L 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 * -i SURVEILLANCE REQUIREMENTS

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

a. Confirms the accuracy of the test by

verifying that the difference between the supplemental data and the Type A test data is within 0.25L , and

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

c. Requires the rate of gas injected into the containment or bled from the containment during the supplemental ,

t test to be limited between 75 to 125%

of L,.

5. Type B and C tests shall be conducted with gas at 2 P, at each refueling shutdown (maximum interval of 24 months) except for tests involving the main steam isolation valves. Main steam isolation valve tests shall be conducted with gas- l at 2 P, each 18 months. A combined [

1eakage rate of $ 0.6L, shall be demonstrated for all penetrations and valves, except for main steam line isolation valves, subject to Type B and C

. tests. A leakage rate of 5 25.3 scf per l hour shall be demonstrated for each main steam line isolation valve.

3.7/4.7 160 i

. _ _ _ _ _ _ _ _ _ _ _ - . . - , _ . _ . . . _ _ . _ ._......__._m. .-.. _ ..... _ _ __ ..- . - - . ~ . . _ _ _ . . , . ~ . -..., ~ -._. ,- -._ _ _ _ . _ .-__._ ____._._ _ _

E 4

Bases Continued:

While the design of the Monticello plant predates 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled, Power Reactors," testing substantially conforms to the -

requirements of Appendix J. The design of the plant was thoroughly reviewed to determine where compliance with Appendix J was impossible or impractical. In each case where a departure from the requirements of Appendix J was identified, a request for exemption from the requirements of Appendix J or a plant modification was proposed and submitted for NRC Staff review. Exemptions were proposed ,

in those cases where compliance with Appendix J would have provided no meaningful improvement in plant safety.

In their review of Appendix J compliance 0D , the NRC Staff approved a number of exemption requests, denied others, and provided necessary interpretation and clarification of the requirements of Appendix J. The Technical Specification surveillance requirements reflect the results of this review.

Exemption from the requirements of Appendix J was provided in the following areas:

a. Testing of valves sealed by water

b. Low pressure testing of the primary containment airlock ,

c. Reduced airlock testing frequency when the airlock is in frequent use The Monticello airlock is tested by pressurizing the space between the inner and outer doors.

Individual door seal leakage tests cannot be performed. Since the inner door is designed to seat with containment pressure forcing the door closed, special bracing must be installed for each leakage test. The outer door must be opened to install and remove this bracing. Because of the complexity of this operation, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months may be necessary to perform a leakage test.

(1) Letter from D G Eisenbut. Director, Division of Licensing, USNRC, dated June 3,1984, " Safety Evaluation by the Office of NRR, Appendix J Review".

t 4.7 BASES NEXT PAGE IS PAGE 188 184 1

u___.________.--_____ _ . . _ _ _ _ _ _ _ . ..______._..._.._:___.._... n...-..,__-_.,;.- _. _ .. - . _ _. - . - _, __..__._n.__u._ _ . .;_..

ML20063C994

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