ML20236N228
| ML20236N228 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/06/1987 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20236N232 | List: |
| References | |
| DPR-16-A-118 NUDOCS 8711160073 | |
| Download: ML20236N228 (4) | |
Text
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o UNITE D STATES g
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NUCLEAR REGULATORY COMMISSION o
5 Lj WASHINGTON, D C. 20555
...../
GPU NUCLEAR CORPORATION I
AN,p JERSEY CENTRAL _P0WER,&_LIGH,1 COMPANY.
j DOCKET NO._ __50-219 OYSTER CREEK NUC.L.E.A.R..G.E.N.E.R.A. TING STAT.IO.N -
AMENDMENT TO PROVISIONAL OPERATING LICENSE-1 Amendment No.ll8 License No..DPR-16 1.
The Nuclear Regulatory Commission (the Comnfission) has found thatt i
A.
The aplication' for amendment by GPU Nuclear Corporation, et al'.
1 (the licensee) dated June 19, 1987, as supplemented July 14, 1987, complies with the standards and requirements of the Atomic Energy Act cf 1954, as amended (the Act), and the Comission's rules and I
regulations set forth in 10 CFR Chapter I; l
B.
The facility will operate in conformity with the application, i
l the provisions of the Act, and.the rules and regulations of the l
Commission; C.
There is reasonable assurance (1) 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 Comission's regulation ;
s D.
The issuance of this amendnent will nct be inimical to the common defense and security or to the health and safety.of the public; and i
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have
.I been satisfied, l
2.
Accordingly, the license is amended by changes to the Technical l
l Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(P) of Facility Operating License No. DPR-16 is hereby.
anended to read as follows:
1 8711160073 871106 l
PDR ADOCK 05000219 P
.b
l (2) Technica_1 Specifications The. Technical Specifications contained in Appendices A and B, as revised through Anendment No.118. are hereby incorporated in the licer.se.
GPlf Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.-
3.
This amendnent is effective on issuance, to be implemented no later than 30 days after issuance.
i F0 HE NUCLEAR REGUL TORY COMMISSION-l
/@
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JphnF.Stolz, Director Profect Directorate I Division of Reactor Projects I/II
Attachment:
1 Changes to the Technical 1
Specifications Date of Issuance: tov enbr 6,1987 1
ATTACHMENT TO LICENSE AMENDMENT NO.118 PROVISIONAL OPERATING LICENSE N0. DPR-16 0
00CKET N0,, 5,0,-?)9 Replace the following page of Appendix A Technical Specifications with the I
enclosed page. The revised page is identified by amendment number and contains vertical lines indicating the areas of change.
l Remove Insert l
l Page 4.3-2 Page 4.3-2 1
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- G.
Primary Coolant System Pressure Isolation Valves i
5 specification:
j 1.
Feriodic leakage testing (a) on each valve listed in table 4.3.1 shall be accomplished prior to exceeding 600 psig reactor pressure every time the plant is placed in i
tne 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 ' preceeding 9 months, whenever the valve is moved whether 6y manual actuation or due to flow conditions, and after returning the valve to service af ter maintenance, repair or l
replacement work is perf ormed.
H.
Reactor Coolant System Leakage 1.
Unidentified leakage rate shall be calculated at least i
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 i
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 4
flow integrator and the primary containment eouipment drain tank flow integrator shall be conducted at least i
once per 18 months.
j Bases:
l8 Numerous data are available relating integrated flux and the change in Nil-Ductility Transition Temperature (NDTT) in various steels.
The base i
metal has been demonstrated to be relatively insensitive to neutron irradiation (see expected NDT changes in FOSAR Table IV-1-1, and Figures l
IV-2-0 and IV-2-10).
The most conservative data has been used in i
Specification 3.3.
The integrated flux at the veseel wall is calculated from core physics data and will be measured using flux monitors installed inside the vessel. The measurements of the neutron flux at the vessel Wall will be used to check and if necessary correct, the calculated data to I
determine an accurate flux.
From this a conservative NDT temperature gan be l
determined. Since no shift will occur until an integrated flux of 10 '
nyt is reached, the confirmation can be made long before an NDTT shift would occur.
l The inspection program will reveal problem areas should they occur, before a l
l leak develops.
In addition, extensive visual inspection for leaks will be made on critical systems.
Oyster Creek was designed and constructed prior to l
tal To satisf y ALARA requirements, leakage may be measured indirectly (as I
f rom th'e perf ormance of pressure indicators) if accomplished in accordance with approved procedures and supported by computations showing that the i
method is capable of demonstrating valve compliance with the leakage l
criteria.
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- NRC Order dated April 20, 1981 t
Corrected:
1/28/86 I
l pf, P, i18 OYSTER CREEK 4.3-2 Amendment:
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