ML20082U314
| ML20082U314 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/12/1991 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20082U316 | List: |
| References | |
| DPR-16-A-154, GL-88-001 NUDOCS 9109200109 | |
| Download: ML20082U314 (4) | |
Text
O
.f O Q*%
UNITED sTA*ES
!" s P[ %
NUCLE AR REGULATORY COMMISSION
$, ' "m r.. $
WASHINGTON, D. C. 205b5
}
\\
p
~
....+
GPU NUCLEAR CORPORAT10fl AND JERSEY CENTRAL POWER A LIGHT C0t'DANY PP.C.K.E,T, !19,,5p-219 O Y ST E P C R E E K tl UC L E,A R, G E tl E,P,A,T,l t: G,,$,T,A,T,lpy Af1E!Dt4ENT TO FACILITY OPERAT1tlG LICENSE Amendment t!o. 154 License No. DPR-16 1.
The fluclear Regulatory Commission (the Commission) has found that:
A.
The application for amendnent by GPU tiuclear Corporation, et al.,
(the licensee), dated June 11, 1991, complies with the standards and requirements of the Atomic Energy Act of 195t., as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The f acility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (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 Conciission's regulations; D.
The issuance of this amendnent will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this antendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable iequirements have been satisfied.
91092003o9 93o93p DR p
ApoCK 05000d19 PDR
i i
2 i
2.
Accordingly, the license is amended by changes to the Technical i
Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. DPR-16 is hereby 1
anended to read as follows:
(2) T e,c,h,n,1,c,a,1,,Sp e,c i f i c a t i o n s The Technical Specifications contained in Appendices A and B, as 4
revised through Arnendment No.154, are hereby ircorporated in the license.
GPU lluclear Corporation shall operate the facility in
[
accordance with the Technical Specifications.
l 3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
j FOR THE I40 CLEAR REGULATORY COPit1SSION r
i
/
l I
John 3T. Stoir, Director l
Project Directorate 1-4 ision of Reactor Pr ects - 1/11 i
Office of fluclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications j
September 12), 1991 Date of Issuance:
+
k f
t h
'b
ATTACWEliT T0 LICEt4SE AtiEtiDVEt4T 110. 154-fl.CJ LJ D. Pf.EF.A,TJ !1p, J.),C,Eji,$,E, !!p,., OfF;jj DOCKET tJO_. 50 219 l
1 Feplace the following pages of the Aprendix A Technical Specifications with the enclosed pages as indicated..The revised pages are identified by aniendrient nuniber and contain vertical lines indicating the areas of change.
Pemove Insert Page 4.3-2 Page 4.3 2 t
8 k
s i --
4 srgy
-a,e-:-m py--*-
y gyw-gw
=eea---su-gw ag-yy w w-pp twtg-T-ige wa v
F Sr
'T*CWr'
- Th7
- MNW"*'W N**PYM'T*W"We""'**""***"'N#"'-'*--"*"""-
^ ^ ^ - -- ^ ^ - -
,~.- ___.-
.~.
e G.
Primary coolant System Pressure isolation Valves Egeeificatient 1.
Periodic leakage testing (a) on 6ach valve listed in Table 4.3.1 shall be accomplished prior to exceeding 600 poig reactor pressure every time the plant is placed in the cold shutdown condition for refueling, each time the plant is placed in a cold shutdown condition for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if testing has not been accomplished in the preceding 9 months, whenever the valve is movod whether by manual actuation or due to flow conditions, and af*.or returning the valve to service after maintenance, repair or replacement work is performed.
H.
Peneter ceqlant system teakaoe 1.
Unidentified leakage rate shall be calculated at least once every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
2.
Total leakage rate (identified and unidentified) shall be calculated at least once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.
A channel calibration of the primary containment sump flow integrator and the primary containment equipment drain tank flow integrator shall be conducted at least once per 18 months.
1.
An inservice inepection program for piping identified in NRC Generic Letter 88-01 shall be performed in accordance with the NRC staff positions on schedule, methods, personnel, and sample expansion included in the generie letter or in accordance with alternate measures approved by the NRC staff.
EAR 118 Data is available relating neutron fluence (E>1.0MeV) and the change in the Reference Nil-Ductility Transition Temperature (RTNDT). The pressura-temperature (P-T) operating curves (h),(b) and (c) in Figure 3.3.1 were developed based on the results of testing and evaluation of specimens removed from the vessel after 8.38 EFPY of operation.
Similar testing and analysis will be performed throughout vessel life to monitor the effects of neutron irradiation on the reactor vessel shell materials.
The inspection program will reveal problem areas should they occur, before a leak develops.
In addition, extensive visual inspection for leaks will be made on critical systems. oyster creek was designed snd constructed prior to I") To satisfy ALARA requirements, leakage may be mateured j
indirectly (as from the performance of pressure indicators) if accomplished in accordance with approved procer' ares and supported l
by computations showing that the method is capable of demonstrata l
ing valve compliance with the leakage criteria.
- NRC Order dated April 20, 1981.
OYSTER CREEK 4.3-2 Amendment No.: 82,90,97,118,120, 15 A 154
-.-