ML19260A063

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Tech Specs Change Request 22,Amend 1,to Amend DPR-50,App a Re Containment Isolation Valves.Certificate of Svc Encl
ML19260A063
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 04/15/1976
From: Arnold R
METROPOLITAN EDISON CO.
To:
Shared Package
ML19260A058 List:
References
NUDOCS 7910290689
Download: ML19260A063 (5)


Text

METROPOLITAN EDISON COMPANY JERSEY CE:iTRAL POWER & LIGHT COMPANY AND PEICISYLVANIA ELTCTRIC COMPANY THREE MILE ISLAND UUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Snecification Chance Reauest No. 22 Amendment No. 1 This Technical Specification Change Request is submitted in support of Licensee's request to change Appenc'ix A to Operating License No. DPR-50 for Cnree Mile Island Nuclear Station Unit 1. As a part of this request, proposed replacement pages for Appendix A are also included.

METROFOLITAN EDISON COMPANY 0 '

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Sworn and subscribed to me this day of dem/ , 1976.

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Metropolitan Edison Co. (Met-Ed)

Three Mile Island Nuclear Station Unit 1 (TMI-1)

Operating Licence No. DPR-50 Docket No. 50-289 TECHUICAL SPECIFICATION CHANGE REQUEST NO. 22 AMDIDMENT NO.1 The licensee requests that the attached changed pages replace page 4-33 of our original request dated October 29, 1975 REASON FOR CHANGE Appendix J to 10 CFR 50 requires type "C" tests to be conducted for certain contain=ent isolation valves. The leakages of valves served by a pressurized seal system, such as our Fluid Block System, may be excluded from the Acceptance Criterion of 0.60 La provided that the fluid inventory of the Fluid I' 'ck System is shown to be sufficient to assure sealing for at least 30 days at 1.10 Pa. Our present Technical Specifications and previously proposed Appendix J related Technical Specification Change Request (October 29, 1975) would permit testing in only the above manner. Appendix J however, would allow testing of each valve served by the Fluid Block System using nitrogen provided that the leakages of these valves are included when meeting the Acceptance Criterion of 0.60 La-Since only extremely small water leakages are tolerable given the small capacity of the Fluid Block Tanks, we have been unable to demonstrate that there is a 30 day supply of seal water at 1.10 Pa. We are able to reduce the from-containment air leakage of these valves to near zero and yet have sufficient seal water loss to prevent meeting the seal water acceptance criterion.

Efforts to date have not succeeded in assuring a 30 day supply of seal water.

This change to Technical Specifications is necessary to permit taking advantage of all of the options allowed by Appendix J.

CAFETY ANALYSIS JUSTIFYING CHAUGE Justification for all changes, except these marked by double marginal bars on the attached changed pages, was provided by our original request as supplemented by our letter of September 17, 1975 Those changes requested by this snendment to our previous request are completely in agreement with the requirements of 10 CFR 50 Appendix J and do not represent an unreviewed safety quection.

1479 184

9 Drain Valves (WDJ-V3, WDL-V303 and WDL-V53h)

c. The following isolation valves vill be te-ted by either testing the Fluid Block System or by measuring the local leak rate for all of those valves using a type "C" test as defined by 10 CFR 50, Appendix J.
1. Nuclear Service Closed Cooling Water (NS-VL -~'. US-V15)
2. Intermediate Cooling Water (IC-V3, Vh and V6) 3 Spent Fuel Cooling (SF-V23)
4. Make-up and Purification (MU-V3 and MU-V26) 5 Reclaimed Water (CA-V189)
6. Sample Valves (CA-V5A&B and CA-V2) ,

T. Drain Valves (WDL-V304, WDG-V4 and WDL-V535)

d. The following isolation valves or blank flanges will be tested by testing the Penetration Pressurization System.
1. Instrument Air (IA-V6 and IA-V20)
2. Service Air (SA-V2 and SA-V3) 3 Leak rate system (LR-v1, 2, 3, 4, 5, 6,10, and h9)

Blank flanges on Penetrations blk, 415, bl6

h. Incore Inst. Transfer Tube - Blank Flange on Penetration 2h1 h-33 1479 185

4.h.1.2.2 Conduct of Tests

a. Local leak rate testa shall be performed pneumatically at a pressure of not less than Pa, with the following exception: The access hatch door seal test shall normally be performed at 10 psig and the test every six months specified in h.h.l.2.5.b shall be performed at a pressure not less than P a-
b. Acceptable methods of testing are halogen gas detection, pressure decay, pneu=atic flow measurement or equivalent.
c. The pressure for a valve test shall be applied in the same direction as that when the valve would be required to perform its safety function unless it can be determined that the direction vill provide equivalent or more conservative results.
d. Valves to be tested shall be closed by normal operation and without any preliminary exercising or adjustments.

h.h.l.2.3 Acceptance Criteria The combined leakage from all items listed in h.h.1.2.1, except leakage from those valves or devices sealed by the Fluid Block System

  • or Penetration '

Pressurization System, shall not exceed .6 La (the maximum allowable leakage rate at P a)-

  • When credit is taken for the une of type "C" testing for the values served by the Fluid Block System, their air / nitrogen leakage shall be included.

4-33a 1479 186

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DOCKET NO. 50-289 LICENSE NO. DPR-50 bETROPOLITAN EDISON COMPANY This is to certify that a copy of Technical Specification Change Request No. 22, Anendment No. 1 to Appendix A of the Cperating License for Three Mile Island Nuclear Station Unit 1, dated April 15, 1976 and filed with the U. S. Nuclear Regulatory Conmission on April 15, 1976. has this 15th day of April been served on the chief executives of Londor derry Township, Dauphin County, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:

Mr. Weldon B. Arehart , Vice-Chairman Mr. Harry 3. Reese, Jr.

Board of Supervisors of Board of County Cornissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METROPOLITAN EDISON CC5'PANY By J A ,/- EM#/

_T Vice ErssTdent-GeneraTfoh d 1479 187