ML17251A111
| ML17251A111 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 05/31/1988 |
| From: | Wessman R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17251A112 | List: |
| References | |
| NUDOCS 8806090288 | |
| Download: ML17251A111 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION AME lt.
E.G~ R PLANT ENSE Amendment No. 27 License No.
DPR-18 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Rochester Gas and Electric Corporation (the licensee) dated September 23, 1987 complies with the standards and requirements 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 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E.
The issuance nf this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No.
DPR-18 is hereby amended to read as follows:
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(2)
Technical S ecifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 27
, are hereby incorporated in the license.
The licensee 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 COMMISSION Richard H. Wessman, Director Project Directorate I-3 Division of Reactor Projects I/II
Attachment:
Changes to the Technical Specifications H
Date of Issuance:
M>~ 3l'e'8
ATTACHMENT TO LICENSE AMENDMENT NO. 27 FACILITY OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.
The revised pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE
- 3. 1-21 3.1-22 6.9-6 6.,9-7 INSERT 3.1-21 3.1-22*
6.9-6 6.9-7
- No change - repositioned on page
3.1.4 Maximum Coolant Activit 3.1'.4.1 S ecifications Whenever the reactor is critical or the reactor coolant average temperature is greater than 500 F:
0 a.
The total specific activity of the reactor coolant shall not exceed 84/E pCi/gm, where E is the r
average beta and gamma energies per disintegration in Mev.
3.1.4.2 b.
The I-131 equivalent of the iodine activity in the reactor coolant shall not exceed 0.2 pCi/gm.
c.
The I-131 equivalent of the iodine activity on the secondary side of a steam generator shall not exceed 0.1 pCi/gm.
If the limit of 3.1.4.l.a is exceeded, then be subcritical with reactor coolant average temperature less than 500 F
within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.1.4.3 a.
If the I-131 equivalent activity in the reactor coolant exceeds'he limit of 3.1.4.1.b but is less than the allowable limit shown on Figure 3.1.4-1, operation may continue for up to 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />.
If the I-131 equivalent activity in the reactor coolant exceeds the limit of 3.1.4.l.b for more than 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> in any consecutive 6-month
- period, then prepare and submit a report to the Commission pursuant to Specification 6.9.2.
Amendment No.
27 3.1-21
The'eactor may be taken critical or reactor coolant average temperature may be increased above a 500 F with the I-131 equivalent activity greater than the limit of 3.1.4.1.b as long as the provisions of this paragraph are met.
- b. If the I-131 equivalent activity exceeds the limit of 3.1.4.1.b for more than 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> during one continuous time interval or exceeds the limit shown on Figure 3.1.4-1, be subcritical with reactor coolant average temperature less than 500 F within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
3.1.4.4 Basis:
- c. If the I-131 equivalent activity exceeds the limit of 3.1.4.1.b, then perform sampling and analysis as required by Table 4.1-4, item 4a, until the activity is reduced to less than the limit of 3.1.4.l.b.
If the limit of 3.1.4.1.c is exceeded, then be at hot shutdown within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and in cold shutdown within the following 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br />.
The total activity limit for the primary system corresponds to operation with the plant design basis of 1% fuel defects.
Radiation shielding and the radioactive waste disposal systems 3.1-22 Amendment Nq, 27
6.9.2 6.9.2.1 6.9.2.2 Uni e
Re ortin Re uirements Annually:
Results of required leak test performed on sources if the tests reveal the presence of 0.005 microcurie or more of removable contamination.
Annually:
A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man-rem exposure according to work and job functions, e.g.,
reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
(NOTE:
This tabulation supplements the requirements of Section 20.407 of 10CFR Part 20.)
6.9.2.3 Annually:
The results of specific activity analysis in which the primary coolant exceeded the limits of I'pecification 3.1.4.1.a and b.
The following information shall be included:
(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radioiodine performed prior to exceeding the limit, 6.9-6 Amendment Ho.
27
6.9.2.4 6.9.2.5
/
results of analyses while the limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than the limit.
Each result should include the date and time of sampling and the radio-iodine concentrations; (3) Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentra-tion and one other radioiodine isotope concentration as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radioiodine limit.
Reactor Overpressure Protection System Operation In the event either the PORVs or the RCS vent(s) are used to mitigate a
RCS pressure transient, a Special Report shall be prepared and submitted to the Commission within thirty days.
The report shall describe the circumstances initiating the transient, the effect of the PORVs or vent(s) on the transient and any other corrective action necessary to prevent recurrence.
Special reports shall be submitted to the Director of the NRC Regional Office listed in Appendix D',
10CFR Part 20, with a copy to the Director, Office of Inspection and Enforcement, U.S. Nuclear Regulatory Commission, Washington, D.C. 20555 within the time period specified for each report.
6.9-7 Amendment No.
27