ML20149E760

Proposed Tech Specs Re Increase Allowable Rate for MSIVs & Deletion of MSIV LCS

ML20149E760
Person / Time
Site:	Limerick
Issue date:	08/01/1994
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20149E758	List: ML20149E753 ML20149E760
References
NUDOCS 9408050193
Download: ML20149E760 (6)

Text

.. . . .

l APPENDIX 2  :

1 LIMERICK GENERATING STATION UNIT 1 AND UNIT 2 i D :ket Nos.

50-352 50-353 License Nos.

NPF-39 NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST NO. 93-18-0 REVISED AFFECTED PAGE UNIT 1 VNIT2 3/46-3 3/46-3 i

P*2R!!8m,,

PDR

^ ~ ' ~

'CONTAlhMENTSYSTEMS LIMilitiGCONDITIONFOROPERATION(Continued)

ACTION: (Continued)

b. The combined leakage rate for all penetrations and all valves listed i in Table 3.6.3-1, except for sain steam line isolation valves

• and l valves which are hydrostat! .1y tested per Table 3.6.3-1, subject to Type B and C tests t' lest then or equal to 0.60 La, and l

c. The leakage rate to $11.5 scf pe. hour for any main steam isolation valve  !

that exceeds 100 scf per hour, ud restore the combined maximum pathway  !

leakage to $200 scf per hour, and I j

4

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, i prior to increasing the reactor coolant system temperature above 200'F.

1URVElllANCEREQUIREMENTS 4.6.1.2 The primary containment leakage rates shall be demonstrated at the i

following test schedule and shall be determined in conformance with the criteria  ;

specified in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI 45.4-1972 and BN-TOP-1 and verifying the result by the Mass Point -

Methodology described in ANSI N56.8-1981:

a. Three Type A Overall Integrated Containment Leakage Rate tests shall  ;

be conducted at 40 +/- 10 month intervals during shutdown at Pa, 44.0 psig, during each 10-year service period. The third test of each set shall be i conducted during the shutdown for the 10-year plant inservice inspection.**  !

b. If any periodic Type A test fails to meet 0.75 La, the test schedule  !

for subsequent Type A tests shall be reviewed and approved by the  !

Commission. If two consecutive Type A tests fail to meet 0.75 La. i a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 La, at which time the above test schedule may be resumed. [

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

1. Confirms the accuracy of the test by verifying that the difference i' between the supplemental data and the Type A test data is within O.25La. The formula to be used is: [L Lam - 0.25 Lal 5 L  !

ssuperimposed

[Lo + Lam + leakage; Lam = measured Type A leak; m  !

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 La and 1.25 La- 4

• Exemption to Appendix "J" to 10 CFR Part 50.

• • The interval between the second and third Overall Integrated Leakage Rate tests of the i first 10-year service period will be extended to the sixth Unit I refueling outace.

As a result, the duration of the first 10-year service period will be extended to the end of the sixth Unit I refueling outage. .

LIMERICK - UNIT 1 3/4 6-3 r

.' " CONTAINMENT SYSTEMS LIMTTING 'ONDITION C FOR OPERATION (Continuedi ACTION: (Continued)

b. The combined leakage rate for all penetrations and all valves listed in Table 3.6.3-1, except for main steam line isolation valves

• and valves which are hydrostatically tested per Table 3.6.3-1, subject  !

to Type B and C tests to less than or equal to 0.60 La, and

c. The leakage rate to $11.5 scf per hour for any main steam isolation valve that exceeds 100 scf per hour, and restore the combined maximum pathway leakage to $200 scf per hour, 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, I l

prior to increasing the reactor coolant system temperature above 200*F. l SURVEILLANCE RE0VIREMENTS j 4.6.1.2 The primary containment leakage rates shall be demonstrated at the  !

following test schedule and shall be determined in conformance with the criteria I specified in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI 45.4-1972 and BN-TOP-1 and verifying the result by the Mass Point Methodology described in ANSI N56.8-1981:

a. Three Type A Overall Integrated Containment Leakage Rate tests shall be conducted at 40 10 month intervals during shutdown at Pa, 44.0 psig, ,

during each 10-year service period. The third test of each set shall be l conducted during the shutdown for thc 10-year plant inservice inspection.  !

l

b. If any periodic Type A test fails to meet 0.75 La, the test schedula for subsequent Type A tests shall be reviewed and approved by the Commission. If two consecutive Type A tests fail to meet 0.75 Las a Type A test shall be performed at least every 18 months until two consecutive Type A tests meet 0.75 La, at which time the above test schedule may be resumed.

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

1. Confirms the accuracy of the test by verifying that the difference between the supplemertal data and the Type A test data is within 0.25 La. The formula to be used is: [Lo + Lam -0.25 La3 6 Lc s [Lo + Lam + 0.25 La] where Lc = supplemental test result; lo -

superimposed leakage; Lam = measured Type A leakage.

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 La and 1.25 La-

• Exemption to Appendix "J" to 10 CFR Part 50.

LIMERICK - UNIT 2 3/4 6-3

, . . . . l l

l l

l APPENDIX 3 l 1

I LIMERICK GENERATING STATION l l

UNIT 1 AND UNIT 2 l

Docket Nos.

50-352 50-353 License Nos.

NPF-39 NPF-85 TECHNICAL SPECIFICATIONS CHANGE REQUEST i NO. 93-18-0

" increase the Allowable Leak Rate for the Main Steam isolation Valves and Delete the MSIV Leakage Control System" General Electric Company Letter to PECO Energy Company Dated May 27,1994 - 2 PAGES t

1 . n s GE Nuclear Energy GeneralBectroc Cornpany 175 Curtner Avenue, San Jcse. CA 95125 1

OG94-423-09 May 27,1994 Andy Winter PECO Energy 965-55 Chesterbrook Boulevard Wayne, PA 19087-5961

SUBJECT:

LIMERICK GENERATING STATION MSIV LEAKAGE RADIOLOGICAL DOSE CALCULATION CORRECTION DUE TO REVISED DRAIN LINE VALVE FLOW AREA

Reference:

Ixtter, Domas Green from A. A. Winter, " Limerick Generating Station Data Input for BWROG MSIV Leakage Closure Committee Radiological Dose Calculation Correction", dated May 19,1994

Attachment:

Backup Calculation Sheet We have evaluated the effect on the subject radiological dose assessment of a small change in the effective altemate t sin line pathway minimum flow area (see Attachment). A change in the drain line valve effective diameter from 1.687 inches to 1.552 inches will increase the fractional flow to the high pressure turbine from 1.3% to 1.5%. However, since the dose contribution from the high pressure turbine is so small (0.16% of total thyroid dose) the effect en the total dose is insignificant (resulting increase less than 0.01 rem for both control room and low population zone).

If you have any questions regarding this verified information or want to discuss any aspects of the MSIV Leakage Closure Committee, please contact the undersigned.

Very truly yours, M

T. A. Green Senior Technical Project Manager BWR Owners' Group Project Tel: (408) 925-1308 Fax: (408) 925-2476 Mail Code 482 TAG /jz Attachment cc: SJ Stark, GE

r

. ., . I BACKUP CALCULATIONSHEET l

Reference. MSIV Leakage Radiological Dose Calculations for Limedek 1,2; OG93-964-09 dated October 22,1993 and the Associated Design Record File (DRF A00-04146 Section M) l Drain Line Valve Flow Area (Original Basis = 1.687 inch diameter) 1 A = (x) (1.687)2/4 = 2.235 in2 Drain Line Valve Flow Area (Revised Basis = 1.552 inch diameter)

A = (x) (1.552)2/4 = j.892 in2 IIP Turbine Valve EtTective Leakage Area = 0.0288 in 2 Flow Split (original basis) = 0.0288 = 0.0127 (1.3%)

2.235 + 0.0288 Flow Split (revised basis) = 0.0288 _ = 0.0150 (1.5%)

1.892 + 0.0288 ,

I Basis: Limerick 1 Thyroid Results (HP Turbine pathway had no i

contribution to whole body calculations)

.I CONTROL ROOM LOH'POPULA TION ZONE i

1. Total Dose (Odginal) 6.27 Rem 36.37 Rem

2. Contribution from HP Turbine 0.01 Rem 0.06 Rem (Original)

3. % Contribution of HP Turbine 0.16 % 0.16 %

l (Original)

4. Estimated Contribution from 0.012 0.069 HP Turbine (Revised)

5. Total Dose (Revised) 6.27 36 3S I

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