ML19290A333
| ML19290A333 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/12/1976 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19290A331 | List: |
| References | |
| NUDOCS 7911060574 | |
| Download: ML19290A333 (5) | |
Text
.
UNITED STATES c
4 O-t NUCLEAR REGULATORY COMMISSION
[ j WASHINGTON. D. C. 20555 j
a g-
%...../
METROPOLITAN EDISON COMPANY JERSEY CENTRAL POkT.R AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY DOCKET NO. 50-289 THREE MILE ISLAND NL' CLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 16 License No. DPR-50 1.
The Nuclear Regulatory Commission (the Coc=ission) has found that:
A.
The application for amendment by Metropolitan Edison Company, Jersey Central Power and Light Company, and Pennsylvania Electric Company (the licensees) dated April 15, 1976, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Cocmission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulatiens of the Commission; C.
There is reasonable assurance (1) that the activities authori::ed by this acendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Cocmission's regulations; D.
The issuance of this amend =ent will not be inimical to the coc=on defense and security or to the health and safety of the public; and E.
After weighing the environ = ental aspects involved, the issuance of this acend=ent 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 a: ended by a change to the Technical Specifications as indicated in the attachment to this license acend=ent.
3.
This license anend:ent is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY C010!ISSION tc,-
Robert W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors Attach =ent:
Changes to the Technical Specifications Dated: AMY I 21976 1555 269
ATTACIL12NT TO LICENSE AMEND 32NT NO.16 FACILITY OPERATING LICENSE NO. DPR-50 DOCl2T No. 50-289 Remove pages 4-33 and 4-34 from the Appendi:c A Technical Specifications and insert the attached replacement pages. The changed areas on the revised page are shown by marginal lines. Page 4-34 is unchanged and is included for convenience only.
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The following isolation valves vill be tested by either testing the c.
Fluid Block Syste= or by ceasuring the local leak rate for all of these valves using a type "C" test as defined by 10 CFR 50, Appendix J.
1.
Nuclear Service Clos ed Cooling Water ( :3-74 and 55-715) 2.
Inte=ediate Ccoling Water (IC-V3, V4 and V6) 3 Spent Fuel Cooling (SF-V23) h.
Make-up and Purification (MU-V3 and !CJ-V26) 5 Reclair-ad ' Water (CA-V189) 6.
Sa=ple Valves (CA-VSA&3 and CA-V2) 7 Drain Valves (WDL-V30h, kTS-Vh and WDL-V535 )
d.
Tae folleving isolation valves or blank flanges vill be tested by testing the Penetration Pressurization Systen:
1.
Instr =ent Air (IA-V6 and IA-V20) 2.
Service Air (SA-V2 and SA-V3) 3 Leak rate testing (LR-V1, 2, 3, h, 5, 6 end 10)
Blank flanges on Penetrations klk, 415, kl6 h.
Incore Inst. Transfer Tube - Blank flan,e on Penetration 221 e
h.h.l.2.2 Conduct of Tests a.
Local leak rate tests shall be perfomed pne=atically at a pressure of not less than Pa.
b.
Acceptable cethods of testing are halogen 6as detection, press'ure decay, pneu=atic flev reasure=ent or equivalent.
c.
Tne pressure for a valve test shall be applied in the sa=3 directic: as that when the valve veuld be required to perfors its safety fune:icn unless it can be dater =ined that ths :lirection vill provi:le equivalen or more conserrative results.
d.
Valves to be tested shall, be closed by nomal operatien and without any preli=inary exercising or adjust =ents,
h.4.1.2.3 Accepta.ce Criteria The co=bined leakage fro: all ite=3. Listed in h.h.1.2.1, except leakage frc= those valves or devices sealed by the Fluid ' lock Systedor Penetratien Pressurization f
Syste=, shall not exceed.6 La (the =eximu= allovable leakage rate at P ).
2
- When type "C" testing is used for the valves served by the Fluid Block System, their air / nitrogen leakage shall be included in the combined leakage.
Amendment No. 16 h-33
J YW L.I. 1.2.h Corree-ive 1.: tion and Eete:
If at any ti=e it is detemined that the criterien of h.h.l.2.3 a.
above is exceeded, repairs shall be initiated in=ediately.
b.'
If conformance to the criterien of h.h.1.2.3 is not demonstrated within hS he22 folleving detection of excessive leeal leakage, the reacter shall be shutdevn and depressurized until repairs are effected and the local leakage =eets the acceptance criterica as demonstrated by retest.
4.k.1.2 5 Test Frequency Icccl lech detection tests shall be perfomed at a frequency of at least each refueling period, except that :
The equip ent hatch end fuel transfer tube seals shall be tested n.
ever/ other refueling period but in no case at intertals greater than 3 years. If they are opened they will be tested after being closed.
b.
The resilient seal of the personnel and energency eIr locks' outer doors shall be tested at six nonth intertals, except when the air locks are opened during that interval.
In this case they shall be tested after each use but no more than once daily. During Cold S/D the mini =t:s test frequency is one per week.
c.
The reactor building purge isolation valves shall be tested yearly.
d.
Readings of the rote eters in each =anifold of the penetration pressurizatica systes shall be recorded at periodic intervals not to exceed three =enths.
h.h.1.3 Isolation valve Functional Tests Ever/ three =enths, re= tely operated reactor building isclatics valves shall be stroked to the position required to fulfill their safe ^y function unless such operation is not practical during plant operatien. The valves not streked ever/ three conths shall be strched curing each refueling period.
h.h.1.h Annual Insrection A visual exa:ination of the accessible interier and exterior surfaces of the contain=ent structure and its cc:penehts shall be performed annually and prior to any integrated leak test to na. cover any evidence of deterioration which =ay affect either the ecstain=ent's structural integrity or leak-tightness. The discover / of any significant deterioration shall be acec=panied by corrective actions in accord with acceptable procedures, nondestructive tests, and inspec-tions, and local testing where practical, prior tu the conduct.cf any integrated Icak test. Such repairs shall be reported as part of the test results.
1555 272 h-3h c.