ML20137D606
| ML20137D606 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/21/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20137D613 | List: |
| References | |
| NUDOCS 8511270107 | |
| Download: ML20137D606 (5) | |
Text
UNITED STATES f
.g NUCLEAR REGULATORY COMMISSION a
WASHINGTON, D. C. 20555
\\...../
GPU NUCLEAR CORPORATION AND JERSEY CENTRAL POWER & LIGHT COMPANY 0YSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 93 i
License No. DPR-16 1.
The Nuclear Reguletory Corm.'ssion (the Commission) has found that:
A.
The application for amendient by GPU Nuclear Corporation and Jersey Central Power and Light Company (the licensees) dated September 18, 1984, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act),
1 and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in confonnity 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
,i by this amendment crn be conducted without endangering the health and safety of the public, and (ii) that such activities will be
,[
conducted in compliance with the Connission's regulstions; D.
The issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance "ith 10 CFR Part 51 of the Conrission's regulations and all applicable requirements i
have been satisfied.
8511270107 851121 I
PDR ADOCK 05000219 P
PDR i
L_ _
. 2.
Accordingly, the license is ar: ended by changes to the Technical Specifications as indicated in the attechment to this license amendment and Paragraph 2.C.(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 93, are hereby 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 the date of its issuance.
FOR THE NUCLEAR REGULATORY C0fEISSION MAh
( John A. Zwolinski, Chief N Operating Reactors Branch #5 Division of Licensing
Attachment:
Chances to the Technical Specifications Date of Issuance:
November 21, 1985 i
I r
o
ATTACHMENT TO LICENSE AMENDMENT NO. 93 PROVISIONAL OPERATING LICENSE N0. DPR-16 DOCKET NO. 50-219 Revise Appendix A Technical Specifications by removing the pages identified below and ir.serting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicatirg the area of change.
REMOVE INSERT 3.3-2 3.3-2 3.3-6 3.3-6 5
i s
1 CP
" ' ' " - ^ ' ~ ' ' ~ *
- 3.3-2.
D.' Reactor Coolant System Leakage-Reactor coolant leakage into the primary containment from unidentified sources shall not exceed 5 gpm.
In addition, the total leakage in the containment, identified and unidentified, shall not exc'ed 25 gpm.
If e
these conditions cannot be met, the reactor _will be pla'ced in.the cold shutdown condition.
3 E.
Reactor Coolant Quality 1.
The reactor coolant quality during power operation with steaming rates to the turbine-condenser of less than 100,000 pounds per hour shall be i
limited to:
conductivity 2 US/cm (S = mhos at 25 C(77 F))
chloride ion 0.1 ppm 2.
When the conductivity and chloride concentration ilmits given in-3.3.E.1 are exceeded, an orderly shutdown shall be initiated immediately, and the reactor coolant temperature shall be reduced to less than 212*F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
J.-
3.
The reactor coolant quality during power operation with steaming. rates to the turbine-condenser of greater than or equal to 100,000 pounds 1
per hour shall be limited to:
j conductivity 10 uS/cm (S=mho' sat 25C(77F))
chloride ion 0.5 ppm 1
- 4. 'When the maximum onductivity or chloride concentration limits given in 3.3.E.3 are exceeded, an orderly shutdown shall be initiated innediately, and the reagtor coolant temperature shall be reduced to less than 212 F within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
5.
During power operation with steaming rates to the turbine-condenser of greater than or equal to 100.000 pounds per hour, the. time limit above
' S uS/cm at 25'C (77'F) and 0.2 ppm chloride shall not exceed 72 f
f.surs for any single incident.
6.
Whe., the time limits for 3.3.E.5 are exceeded, an orderly shutdown l
shall be initiated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
F.
Recirculation Loop Operability 1.
The reactor shall not be operated with one or more recirculation loops out of service except as specified in Specification 3.3.F.2.
I 2.
Reactor Operation with one idle recirculation loop is permitted l
provided that the idle loop is not isolated from the* reactor vessel.
3.
If Specifications 3.3.F.1 and 3.3.F.2 are not met, the reactor sh311 be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Amendment 16. 4, 93 1-t v,
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3.3-6 Chlorides are known to (1) promote intergranular stress corrosion cracking of sensitized stainless ste'els, (2) induce transgranular cracking of non-sensitized stainless steels, (3) promote pitting and (4) promote crevice attack in most RCS materials (BWR Water Chemistry Guidelines, EPRI, April 1, 1984). The higher the concentration, the faster the attack.
E Therefore, the level of chloride in the reactor water should be kept as low as is practically achievable. The limits are therefore set to be consistent with Regulatory Guide 1.56 (Rev. 1.)
In the case of BWR's where no additives are used in the primary coolant, and where neutral pH is maintained, conductivity provides a very good measure of the quality of the reactor water. When the conductivity is within'its proper normal range, pH, chloride, and other impurities affecting conductivity and water quality must also be within their normal ranges. Significant changes in conductivity provide the operator with a warning mechanism so that he can investigate and remedy the conditions causing the change.
Measurements of pH, chloride, and other chemical parameters are made to determine the cause of the unusual conductivity and instigate proper corrective action. These can be dcne before limiting conditions, with respect to variables affecting the boundaries of the reactor coolant, are exceeded. Several techniques are available to correct off-standard reactor water quality conditions including removal of impurities from reactor water by the cleanup system, reducing input of impurities causing off-standard conditions by reduc,ing power and reducing the reactor coolant temperature to less than 212*F. The major benefit of reducing the reactor coolant temperature to less than 212*F is to a
reduce the temperature dependent corrosion rates and thereby provide time for the cleanup system to re-establish proper water quality.
References (1) FDSAR, Volun.a I, Section IV-2 (2)(Deleted)
(3)(Deleted)
(4) Licens~ing Application Amendment 16 Design Requirements Section (5)(Deleted)
(6) FDSAR, Volume I, Section IV-2.3.3 and Volume II, Appendix H (7) FDSAR, Volume I, Table IV-2-1 (8) Licensing Application Amendment 34, Question 14 (9) Licensing Application Amendment 28, Item III-B-2 (10) Licensing Application Amendment 32, Questio'n 15 (11) (Deleted) l (12) Licensing Application Amendment 68 Supplement No. 6 Addendum 3 (13)LicensingApplicationAmendement16.Page1 Amendment No, M,93
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