ML20126D198

Forwards marked-up Tech Specs,Clarifying Containment Integrated Leakage Rate Test Program.Util 850523 Description of Program Acceptable.Amend to Fsar,Reflecting Clarification,Requested

ML20126D198
Person / Time
Site:	Perry
Issue date:	06/10/1985
From:	Youngblood B Office of Nuclear Reactor Regulation
To:	Edelman M CLEVELAND ELECTRIC ILLUMINATING CO.
References
NUDOCS 8506140674
Download: ML20126D198 (3)

Text

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10 W Docket No. 50-440 Mr. Murray R. Edelman, Vice President Nuclear Operations Group The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101

Subject:

Performance of the Preoperational Containment Integrated Leakage Rate Test - Perry Nuclear Power Plant, Unit 1 Your letter dated May 23, 1985 (PY-CEI-0232L) informed the NRC staff how the Perry Unit 1 preoperational Containment Integrated Leakage Rate Test (CILRT) would be performed and the test result evaluated and analyzed for conformance with applicable requirements. Your staff subsequently requested that we formally document our concurrence.

Accordingly, the NRC staff finds acceptable CEI's description of the perfor-mance of the CILRT portion of the Initial Test Program for Perry Unit I stated in your May 23, 1985 letter with the following clarification:

"The primary containment leakage rates shall be demonstrated at the test schedule to be stipulated in the plant Technical Specifications 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; test results shall also be reported based on the Mass Point Methodology described in ANSI /ANS 56.8-1981" (underlined is point of clarification).

This clarification is being included in the Technical Specifications as shown in the enclosed draft page from the " Proof and Review" issue of the Perry i

Unit 1 Technical Specifications currently being finalized. The Perry FSAR should also be amended to reflect this clarification prior to Unit I licensing.

Sincerely, ORIGINAL SIGNED BY:

B. J. Youngblood, Chief Licensing Branch No. 1 Division of Licensing

Enclosure:

As stated

, DISTRIBUTION:

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Mr. Murray R. Edelman Perry Nuclear Power Plant The Cleveland Electric Units 1 and 2 Illuminating Company cc:

Jay Silberg, Esq.

Mr. Larry O. Beck Shaw, Pittman, & f,owbridge The Cleveland Electric 1800 M Street, N. W.

Illuminating Company j-Washington, D. C.

20006 P. O. Box 97 E-210 Donald H. Hauser, Esq.

The Cleveland Electric Illuminating Company P. O. Box 5000 Cleveland, Ohio 44101 Resident Inspector's Office U. S. Nuclear Regulatory Commission Parmly at Center Road Perry, Ohio,44081 Regional Administrator, Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Donald T. Ezzone, Esq.

-Assistant Prosecuting Attorney 105 Main Street Lake County Administration Center Painesville, Ohio 44077 Ms. Sue Hiatt OCRE Interim Representative 8275 Munson Mentor, Ohio 44060 Terry J. Lodge, Esq.

618 N. Michigan Street Suite 105 Toledo, Ohio 43624 John G. Cardinal. Esq.

Prosecuting Attorney Ashtabula County Courthouse Jefferson, Ohio 44047

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ENCLOSURE

.l -,,.,

g' CONTAINMENT SYSTEMS

' i.. L d. !.... ;.1. ].'. / f LINITING CONDITION FOR OPERATION Sontinued)

(

ACTION (Continued) r -

restore:

The overall integrated leakage rate (s) to less than or equal to a.

0.75 L,, and.

b.

The combined leakage rate for ali penetrations and all val l

s L except for main steam line isolation va es Tn..

l valves which are hydrostaticallylleak tested per Table 3.

4-1, subject to Type B and C tests to less than or equal to 0.

nd The leakage rate to less than 25 scf per hour for any one main c.

steam line through the isolatiori valves, and d.

The combined leakage rate for all penetrations shown in Table 3.6.4-1 as secondary containment bypass leakage paths to less than or equal to 'O.00' L,, and o.oss4 The combined leakage rate for all ::::

..J.". :: containment isolation e.

valves in hydrostatically tested line which penetrate the primary containment to less than or equal to 1 pm times the total number of such valves, g g g f,y /

prior to increasing reactor coolant system temperature above 200*F.

SURVEILLANCE REQUIREMENTS

[4.6.1.2 The primary containment leakage rates shall (demonstrated at the s....

f following test schedule and shall be determined in confo'reance with~the criteria j i

specified in Appendix J of 10 CFR Part 50 lusingW methods and provisions of ANSI 45.4-1972 and 8N-TOP-1 'and verifying'the result by,.the' Mass Point

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h Meinooology neiTribed in ANSI N56.8-1981:

4N Three Type A Overall Integrated Containment Leakage Rate tests shall a.

' g g al be conducted at 40 + 10 month intervals during shutdown at P,

g tED.

11.31 psig during each 10 year service period.

Thethirdteltof q

Mgg 6.on each set shall be conducted during the shutdown for the 10 year plant inservice inspection.

. g ki44 S N @b.l If any periodic Type A test fails to meet 0.75 L, the test schedule

'7 p a for subsequent Type A tests shall be reviewed an8 approved by the i

Commission.

If two consecutive Type A tests fail to meet 0.75 L Type A test shall be performed at least every 18 months until tw8, a

consecutive Type A tests meet 0.75 L,, at which time the above test schedule may be resumed.

The accuracy of each Type A test shall be verified by a supplemental

c.

• test which:

S e =

...a m = = =.

• a o a as PERRY - UNIT 1 3/4 6-4

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