ML14175A678
| ML14175A678 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 05/14/1981 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML14175A679 | List: |
| References | |
| DPR-23-A-056 NUDOCS 8105260263 | |
| Download: ML14175A678 (6) | |
Text
0 UNITED STATES 0
NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 CAROLINA POWER AND LIGHT COMPANY DOCKET NO.
50-261 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 56 License No. DPR-23
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Carolina Power and Light Company (the licensee) dated May 5,1981, 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 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 Commission's regulations and all applicable requirements have been satisfied.
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- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-23 is hereby amended to read as follows:
2, Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.
56, 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.
F R THE NUCLEAR R GULATORY COMMISSION Steven A. arga, Chie Operating Reactors r nch 1 Division of Licensin
Attachment:
Changes to the Technical Specifications Date of Issuance: May 14, 1981
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 56 TO FACILITY OPERATING.LICENSE NO. DPR-23 DOCKET NO. 50-261 Revise Appendix A as follows:
Remove Pages Insert Pages 3.1-16 3.1-16 3.1-19a 3.1-19a 4.1-10 4.1-10
3.1.5 Leakage 3.1.5.l If the nrimary system leakage exceeds 1 9pm and the source of leakage is not identified within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the reactor shall be placed in the hot shutdown condition utilizing normal operating procedures. If the source of leakage exceeds 1 gpm and is not identified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in the cold shutdown condition utilizing normal operating procedures.
3.1.5.2 If the sources of leakage have been identified and it is evaluated that continued operation is safe, operation of the reactor with a total leakage rate not exceeding 10 npm shall be permitted. If leakage exceeds 10 gpm, the reactor shall be placed in the hot shutdown condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> utilizing normal operating procedures. If the leakage exceeds 10 gpm for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the reactor shall be placed in the cold shutdown condition utilizing normal operating procedures.
3.1.5.3 If the leakage is determined to be primary to secondary steam generator leakage in excess of 0.35 gpm in any steam generator, or in excess of 1 gpm total for all three steam generators, the reactor shall be shutdown and the plant placed in the cold shutdown condition utilizing normal procedures within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> after detection.
3.1.5.4
- a. During reactor operation and hot shutdown conditions all pressure isolation valves listed in Table 3.1-1 shalt be functional as a pressure isolation device, except as specified in 3.1.5.4.b. Valve leakage shall not exceed the amounts indicated,
- b. In the event that integrity of any pressure isolation valve specified in Table 3.1-1 cannot be demonstrated, reactor operation may continue, provided that at least two valves in each high pressure line having a non-functional valve are in,and remain in,the mode corresponding to the isolated condition. (Manual valves shall be locked in the closed position; motor operated valves shall be placed in the closed position and power supplies deenergized ).
- c. If Specifications 3.1.5.4a or b cannot be met, an orderly shutdown shall be initiated and the reactor shall be in hot shutdown within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in the cold shutdown condition within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Amendment No. 56 3.1-16
1ABLE 3.1-1 PRIMARY COOLANT SYSTEM PrrE$SURE ISOLATIO! VALVES Maximum (a)
System Valve No.
Allowable Leakagc Low-Pressure Safety 5.0 GPM for each(
Injection/Residual valve Heat Removal Loop 1, cnid leg F75A 876A Loop 2, cold leg E75; 876B Loop 3, cold leg 875C 876C High-Pressure Injection Loop 2, hot leg 8740 Loop 3, hot leg 874A (a)1.
Leakage rates less than or equal to 1.0 gpm are considered acceptable.
- 2. Leakage rates greater than 1.0 gpm but less than or equal to 6.0 gpm are considered acceptable if the latest measured rate has not exceeded the rate determined by the previous test by an amount that reduces the margin between measured leakage rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
3, Leakage rates greater than 1,0 gpm but less than or equal to 5.0 gpm are considered unacceptable if the latest measured rate exceeded the rate determined by the previous test by an amount that reduces the maroin between measured leakace rate and the maximum permissible rate of 5.0 gpm by 50% or greater.
- 4. Leakage rates greater than 5.0 gpm are considered unacceptable.
(b)More than one valve may be tested in parallel.
The combined leakage shall not exceed 5.0 gpm.
Redundant valves in each line shall not be tested in series.
Amendment No.
56 3.119a
TABLE 4.1-3 (Continued) iaximr.um T7 Check Frequency Between Tes
- 13. Turb ne InspeCtiol Vilual, Magnaflux Every five y 6 y'ears and Die Penetrant
- 14. Fans and Associated Fans functioning, Once per operating cycle NA Charcoal and ALso-Laboratory tests on lute Filters for charcoal must show Control P.oom and
> 99% iodine removal.
Residual Hct In-place test must Pemoval Compart-show 99f removal of
.ments (HVE-19, pclydispersed OP HVE-Fa and 5b particles by the IEPA respectively) filters and Freon by the charcoal filters.
- 15. Isolation Seal Functioning Each refueling shutdown NA Water System 1 l. Overpressure Functioning,,
Each refueling shutdown NA Protection System
- 17. Primary Coolant Functioning
- 1. Periodic leakage testing(a)(b)
System check on each-lcvalve listed vaves cin Table 3.1-1 shall valves.
be accomplished prior to entering reactor operation condition (1) after every time the plant is placed in the cold shutdown condition for refueling, (2) after 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 D ceding 9 months, (3) after maintenance, repair or replacement work is performed.
(a)To satisfy ALARA requirements, leakage may be measured indirectly (as from.the performance of pressure indicators) if accomplishA in accordance with approved procedures and supoorted by computdtions showing ttat the method is capable of demonstrating valve compliance with 'he Teakage criteria.
'Minimum test differential pressure shalI not be les. than 150 paid.
(c)More than one valve may be tested in parallel.
The combined leakage shall not exceed 5.0 gpm.
Redundant valves in each line shall not be tested in series.
Amendment No.
56 4.1-10