ML20138E541
| ML20138E541 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/18/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20138E547 | List: |
| References | |
| NUDOCS 8510250049 | |
| Download: ML20138E541 (10) | |
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UNITED STATES e
NUCLEAR REGULATORY COMMISSION h
WASHINGTON, D. C. 20555
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GPU NUCLEAR CORPORATION AND JFRSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PPOVISIONAL OPERATING LICENSE Amendment No. 90 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation and Jersey Central Power and Light Conpany (the licensees) dated s
February 11, 1985, complies with the standards and require-ments 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Comnissinn; i
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health end safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this emendment 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 amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
0510250049 851018 PDR ADOCK 05000219 P
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Accordingly, the license is amended by chances to the Technical Specifications as irdicated in the attachrent to this licerse i
amendment and Paragraph 2.C.(?) of Previsional Operating License No. DPR-16 is hereby amended tn read as follows:
i
(?) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 90, are hereby incorrereted j
in the license. GNI Fuclear Corporation shell operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
l FOR THE NUCLEAR REGULAT RY COMMISSION 4L
(-
- Johr,
. 7volinski, Chief I
Opera ing Reactors Branch #5 1
Division of Licensino I
Attachment:
Chanaes to the Technical Specifications t
j Date of Issuance: October 18, 1985 i
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ATTACHMENT TO LICENSE AMEf!Di'ENT N0.90 PPOVISIONAL OPEPATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Fevise Arpendix A Technical Specifications by renovino the pages identified below and inserting the enclosed pages. The revised pages are identified by the caotioned erendnent nunber and contain vertical lines indicating the aree of change.
PEMOVE INSERT 4.3-1 4.3-1 4.3-3 d.3-3 on.
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A.3 P.EACTOR COOLANT 4.3-1 Applicability:
Applies to the' surveillance requirements for the reactor ccolant system.
Obiective:
To detennine the condition of the reactor coolant system and the operation nf the safety devices related to it.
Specification:
A.
Neutron flux monitors shall be installed in the reactor vessel ediacent to the vessel wall at the core midplane level. The monitors shall be removed and tested at the first refueling outage to experimentally verify the calculated values of integrated neutron flux that are used to determine the NDTT from Figure 3.3.1.
B.
Inservice inspection of ASME Code Class 1. Class 2 and Class 3 systems and components shall be perfonned in accordance with Section XI of the ASME Boiler and i
l Pressure Vessel Code and applicable Addenda as required by 10 CFR, Section 50.55a(g), except where specific written relief has been granted by ).
the NRC pursuant to 10 CFR, Section 50.li5a(g)(6)(i C.
Inservice testing of ASME Code Class 1 Class 2 and Class 3 pumos and valves shall be performed in i
accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR, Section 50.55a(g), except where specific written relief has been granted by the NRC pursuant to 10 CFR, Section 50.55a(g)(6)(1).
D.
A visual examination for leaks shall be made with the reactor coolant system at pressure during each scheduled refueling outage or after major repairs have been made to the reactor coolant system in accordance with Article 5000,Section XI. The requirements of specification 3.3.A shall be met during the test.
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E.
Each replacement safety valve or valve that has been repaired shall be tested in accordance with subsection j]
IWV-3510 of Section XI of the ASME Botier and Pressure Vessel Code. Setpoints shall be as follows:
I I
Number of Valves Set Point (psio) 4 1212 1 12 4
1221 2 12 4
1230 e 12
- l 4
1239 2 12 i
Amendment No. 82,90 l :
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l d.3-3
_ Bases:
Nil-Ductility Transition Temperature (NDTT) in various metal has been demonstrated to be relatively insensitive to neutron The base irradiation (see ex IV-2-9 ard IV-2-10)pected NDT changes in FDSE Table IV-1-1, and Figures The most conservative data has been used in Specification 3.3.
The integrated flux at the vessel wall is calculated j
from core physics data and will be sneasured using flux monitors installed inside the vessel.
1 The measurements of the neutron flux at the vessel wall will be used to check and if necessary correct, the calculated data 1
to detemine an accurate flux.
l From this a conservative NDT temperature cag be determined.
nyt is reached, the confimation can be made lonc before 10'7 shift would occur.
The inspection orogram will reveal problem areas should they occur, b a leak develops.
ba rie.de on critical systems.In addition, extensive visual inspection for leaks will prior to the ~eristence of ASME Section XI. Oyster Creek was designed and con addressed as " requests for relief" in accordanc Section XI of the ASME Boiler and Pressure Vessel detect failures or deterioration.
Section I of the ASME Code at +1% of design pressure.The tolerance value the safety ifait of 1375 psig is not exceeded.been perfomed wh An analysis has Conductivity instruments continuously monitor the Experience 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is adequate to ensure accurate readings.
ry will also be used to detemine the chloride ion content in limits of 3.3.E are not exceeded.
rapidly over a period of several days; therefore, the sampling adequate.
Amendment No p2,90 l
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ma ase UNITED STATES E
NUCLEAR REGULATORY COMMISSION g
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'j WASHINGTON, D. C. 20555
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4 GPU NUCLEAR CORPORATION AND JFRSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PPOVISIONAL OPERATING LICENSE Amendment No. 90 License No. DPR-16 1.
The Nuclear P.egulatory Comiss' ion (the Comission) has found that:
A.
The application for arendment by GPU Nuclear Corporation and J
Jersey Central Power and Licht Conpany (the licensees) dated February 11, 1985, complies with the standerds and require-ments of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR I
Chapter I; i
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the i
Comissinn; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health end safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; i
D.
The issuance of this emendment 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 anendrent is in accordance with 10 CFR Part 51 of the Comission's reguletiens and all applicable requirements have been satisfied.
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i 2.
Accordingly, the license is amended by changes tn the Technical Specifications as irdicated in the attachront to this license amendment and Paragraph 2.C.(P) of Previsional Operating License No. DPR-16 is hereby amended tn read es follows:
I (P) Technical Specifications I,
The Technical Specifications contained in Appendices A and B, 4
as revised through Amendnent No. 90, are hereby incorrereted in the license. CPli Fuclear Corporation shall operate the facility in accordance with the Technical Specifications.
i j
3.
This license amendment is effective as nf the date of its issuance.
l FOR THE NUCLEAR REGULAT RY COMMISSI0f!
j M L N-John
. 7velinski, Chief l
Opera ing Reactors Branch #5 l
Division of Licensing Attachrent:
Chances to the Technical Specifications I
Date of Issuance: October 18, 1985 l
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ATTACHMENT TO LICENSE AMEf:DI:ENT N0.90 PPOVISI0flAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Pevise Arpendix A Technical Specifications by reroving the pages identified below and insertira the enclosed pages. The revised pages are identified by the caotioned erendnent number and contain vertical lines indicating the area of change.
REMOVE INSERT 4.3-1 4.3-1 4.3-3 4.3-3 t
i
4,3 P.EACTOR COOLANT 4.3-1
.)
Applicability:
Applies to the' surveillance requirements for the reactor i !
coolant system.
Ob.fective:
To determine the condition of the reactor coolant 2
system and the operation nf the safety devices related to it.
i Specification:
A.
Neutron flux monitors shall be installed in the reactor vessel ed,iacent to the vessel wall at the lt core midplane level. The monitors shall be removed
- 1 and tested at the first refueling outage to experimentally verify the eniculated values nf integrated neutron flux that are used to determine the NDTT from Figure 3.3.1.
B.
Inservice inspection of A9tE Code Class 1, Class 2 and Class 3 systems and components shall be performed 4
j in acenrdance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR, Section 50.55a(g), except where specific written relief has been granted by(1).
the NRC pursuant to 10 CFR, Section 50.15a(g)(6) p C.
-Inservice testing of ASME Code Class 1, Class 2 and Class 3 pumos and valves shall be performed in P
accordance with Section XI of the ASME Boiler and j
Pressure Vessel Code and applicable Addenda as requiredby10CFR,Section50.55a(g),exceptwhere specific written relief has been granted by the NRC l
t pursuant to 10 CFR. Section 50.55a(g)(6)(1).
i D.
A visual examination for leaks shall be made with the i
reactor coolant system at pressure during each scheduled refueling outage or after major repairs have been made to the reactor coolant system in accordance with Article 5000.Section XI. The requirements of specification 3.3.A shall be met during the test.
E.
Each replacement safety valve or valve that has been repaired shall be tested in accordance with subsection IWV-3510 of Section XI of the ASME Boiler and Pressure Vessel Code. Setpoints shall be as follows:
i q
t Number of Valves set Point (psis) 4 1212 1 12 4
1221 1 12 4
1230 2 12 h
l 4
12l, #
12 b
ll Amendment No. 82,90 l
l
l d.3-3 I
Bases:
i i
Numerous data are avai,lable relating integrated flux and the change in liil-Ductility Transition Temperature (NDTT) in various steels. The base ineral has been demonstra'.ed to be relatively insensitive to r,eutron
~
i irradiation (see ex IV-2-9 and IV-2-10)pected NDT changes in FDS4F. Table IV-1-1, and Figures The most conservative data has been used in i
Specification 3.3.
The integrated flux at the vessel wall is calculated j
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 i
to detemine an accurate flux.
From this a conservative NDT temperature ca be determined. Since no shift will occur until an integrated flux of 10 7 nyt is reached, the confirmation can be made long before en NDTT shift would occur.
The inspection crogram will reveal problem areas should they occur, before a leak develops.
In addition, extensive visual inspection for leaks will be m de on critical systems. Oyster Creek was designed anc' constructed prior to the'eristence of ASME Section XI.
For this reason, the degree of access required by ASME Section XI is not generally available and will be addressed as " requests for relief" in accordance with 10 CFR 50.55a(g).
)
Experience in safety valve operation shows testing in accordance with Section XI of the ASME Boiler and Pressure Vessel Code is adequate to 1
detect failures or deterioration. The tolerance value is specified in Section I of the ASME Code at +1% of design pressure. An analysis has been perfomed which shows thaT with all safety valves set 12 psig higher the safety limit of 1375 psig is not exceeded.
lns atkona ca at a e f the c i
es t e er j
ours is adequate to ensure accurate readings. The reactor water sariple (m a sn be used to detemine the chloride ion content to assure that the 3
ts of 3.3.E are not exceeded. The chloride ion content will ret chan i r2 ver a period of several days; therefore, the sampling frequency f rp I
i 4
l Amendment No. 52, 90 I
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