ML20091D262
| ML20091D262 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/18/1984 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Metropolitan Edison Co, Jersey Central Power & Light Co, Pennsylvania Electric Co, GPU Nuclear Corp |
| Shared Package | |
| ML20091D263 | List: |
| References | |
| DPR-50-A-093 NUDOCS 8405310099 | |
| Download: ML20091D262 (6) | |
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.pA R E G I
b UNITED s TATES E lt
. c 'T k NUCLEAR PEGULATC RY COMMISSION
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wA ;HINGTON, D. C. 20535
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METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY i
PENNSYLVANIA ELECTRIC COMPANY GPU NUCLEAR CORPORATION DOCKET NO. 50-289 THREE MILE ISLAND NUCLEAR STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.~93 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendrent by GPU Nuclear Corporation, et al (the licensees) dated April 21, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conforn.ity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurai.ce (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; j
and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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. 2.
Accordingly, the license is amended by changes to the Technical Sytcifications as indicated in the enclosure to this license amendment, and paragraph 2.c.(2) of Facility Operating License No. OPR-50 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 93, are hereby
,A incorporated in the license.
GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Joh F. Stolz, Chief I
0 rating Reactors Branch No. 4 Division of Licensing
Enclosure:
Changes to the Technical Specifications Date of Issuance:
May 18,1984
ATTACHMENT TO LICENSE AMENDMENT NO. 93 FACILITY OPERATING LICENSE NO. OPR-50 l
DOCKET NO. 50-289 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendme.it number and contain vertical lines indicating the areas of change.
I Remove Insert 4-32 4-32 4-33 4-33 4-34b 4-34b i
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1 detection tests.
Sufficient data and analysis shall be included to shov that a stabilized leak rate was attained and to identify all significant required correction factors such as those associated with humidity and barometric pressure, and all significant errors such as those associated with instrumentation sensitivities and data scattet. This report shall be titled Reactor Containment Building Integrated Leak Rate Test and shall be submitted to the-NRC within 3 months of the test.
4.4.1.2 Local Leakage Rate Tests 4.4.1.2.1 Scope of Testing The local leak race shall be measured for the following components a.
using a type "B" test as defined in 10 CFR 50, Appendix J.
1.
1-ersonnel air lock door gaskets and other seals 2.
Emergency air lock door gaskets and other seals 3.
The resilient seals on the equipment hatch and fuel transfer tube blind flanges 4.
Blind flanges on penetration'No. 414 (L.R. Pressure Sensing) 5.
Reactor Building Purge valves (AH-VIA, B, C and D) 6.
Blind flanges on both ends of pipe through the following penetrations:
6.1 No. 104 (S/G drains) 6.6 No. 24'. (Incore inst. Transfer Tube) 6.2 No. 105 (S/G cleaning) 6.7 No. 415 (L.R. Test Bleed Line) 6.3 No.106 (S/G cleaning) 6.8 No. 416 (L.R. Test Bleed Line) 6.4 No. 210 (S/G annulus drains) 6.5 No. 211 (S/G annulus drains) b.
The local leak rate shall be measured for the following isolation valves using a type "C" test as defined in 10 CFR 50, Appendix J.
t 1.
CA-V1. 2, 3, 11 (Primary Samplina)
CA-V189,192 (Reclaimed Water)
CA-V4A, 4B, SA, 53 (Secondary Sampling)
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2.
CF-V2A,.2B, 12A, 12B, 19A, 19P, 20A, 20B (Core Flood) l 3.
Of-V1, 2, 3, 4 (Contain==nt Monitoring) i 4.
DH-V64, 69-(Decay Heat) l S.
HP-V1, 6 (Hydrogen Purge) l 6.
HR-2A, 2B, 4A, 43, 22A, 223, 23A, 23B (Hydrogen Recombiner) 7.
IA-V6, 20 (Instrument Air)
S.
IC-V2, 3, 4, 6, 16, le (Intermediate Ccoling)
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4-32 Amendment No. H,93
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LR-V1, 4, 5, 6,,
10,'49 (Leak Rate Test) 10.
MU-V2A, 2B, 1, 18, 20, 25, 26, 116 (Make up and Purification) 11.
NI-V27 (Nitrogen) t 12.
NS-V4,11,15, 35 (Nuclear Services Closed Cooling) 13.
RB-V2A, 7 (R.B. Industrial Cooling System) 14.
SA-V2, 3 (Service Air) 15.
SF-V23 (Spent Fuel Cooling)
I 16.
WDG-V3, 4 (Waste Gas Header) 17.
WDL-V303, 304 (Waste Disposal Liquid) 18.
WDL-V534, 535 (R.B. Sump Gravity Drains)
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L' 4.4.1.2.2 Conduct of Tests h
Local leak rate tests shall be performed pneu=atically at a pressure a.
of not less than P, with :he following exception:
The access hatch I
doorsealtestsha$1normallybeperfornedat 10 psig and the test every six conths specified in 4.4.1.2.5.b shall be performed at a pressure not less than P.3 b.
Acceptable methods of testing are halogen gas detection, pressure decay, y
pneumatic flow measurement or equivalen:.
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The pressure for a valve test shall be applied in the same direce. ion c.
E as that when the valve would be required to perfor= 1:s safety function 5
unless it can be deter =ined that the direction will provide equizalen or more conserva,tive results.
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d.
Valves to be tested shall be closed by taormal operation and without g
any preliminary exercising or adjustments.
e 4.4.1.2.3 Acceptance Criteria The combined leakage from all items listed in 4.4.1.2.1 shall not exceed.6 L
=
(the maximum allowable leakage rate at P )-
a P
c t
7 4-33 r
Amendment Nos. JS, $7, 93
- Tha mini =um t:st pr:ssura of' 27.5 psig fcr the periodic. integrated 1catagi rate test is sufficisntly high to provide an accurnta mensurement of the leaka'ge rate and it duplicates the pre-operations.1 leakage rate test at the reduced pressure. The specification provides e. relationship for relating the measured leakage of air at the reduced pressure to the potential leakage of 53 psis.
"'he minimum of 2h hours was rpecified fcr the integrated leakage rate test to help stabilite conditione and thus i=preve accuracy and to better evaluate data scatter. The frequency of the periodic inte5 rated leakage rate test is keyed to the rePaeling schedule for the reactor, because t.hese tests can best be perfcrmed during refueling' shutdowns.
The specified frequency of periodic integrated leakage rate tests is based on three major considerations. First is the low probability of leaks in the liner, because of conformance of the complete containment to a 0.10 percent leakage rate at 55 psig during pre-operational testing and the absence of any significant stresses in the liner during reactor operation.
Second is the more' frequent testing, at design pressure, of those portions cf the containment envelope that are most likely to develop leaks during reactor operation, and the low value (0.06 percent) of leakage that is specified as acceptable from penetrations and isolation valves. Third is the tendon stress surveillance program which provides assurance that an important part of the structural integrity of the containment is maintcined.
More frequent testing of various penetrations is specified as these locations are more susceptible to leakage than the reactor building liner due to the mechanical closure involved. The basis for specifying a total leakage rate of 0.06 percent from those penetrations and isolation valves is that more than one-half of the allowable integrated leakage rate vill be from these sources.
Valve operability tests a e specified te assure pr per :lesure er cpe",g of the rea:.cr building isola.ict va.1ves te provide fer isele. tion er functioning Of Engineered St.fety yee. u es sys,rtzs. Ve.1ves vill be stroked te.he peritic:
required sc *u"' -heir sefety function unless it is established
.he.. such
.esting is net pre.ctice.1 during enere.icn. Ve.1ves that cannot be full-s.roke
.e sted vill be part-stroke.ested du-ing Opere.:ien e.nd full-stroke tested during er.ch nernel rePaeling shutdev..
Periciic su:-ceillance of the e.irlech interlock syster: is specified c ass e centinued operability and precinde ins.ances where :ne er both decrs a. e in-e.dver,ently left Open. knen e.:. e.irlock is inoperable e.ni cente.in=ent in e--ity is required, local supe-vir.icn cf e.irlock eteratic: is specified.
peterence (1) FSAS, Section 5
. Anendment Nc. #, 93 L-31b
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