ML20071E836
| ML20071E836 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/01/1983 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071E839 | List: |
| References | |
| NUDOCS 8303100401 | |
| Download: ML20071E836 (11) | |
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UNITED STATES 8
i NUCLEAR REGULATORY COMMISSION 3
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION, UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 83 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated December 31, 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 t
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.
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i 2-2.
Accordingly, the license is amended hy changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-32 is herehy amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 83, 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 f.
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Attachment:
Changes to the Technical Specifications Date of Issuance:
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO.50-28T SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 84 License No. OPR-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Canpany (the licensee) dated December 31, 1 981, 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 Canmission; C.
There is reasonable assurance (i) that the activities auth6rized 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.
O
P 2-2.
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-37 is herehy amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 84, are herehy 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 05) i
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/ deven A Varga, Ctf Operating Reactors B anch #1 DivisionofLicensih
Attachment:
Changes to the Technical Specifications Date of Issuance: March 1,1983 O
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ATTACHMENT TO LICENSE AMENDMENTS AMENDMENT NO. 83 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 84 TO FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 3.8-1 3.8-1 3.8-2 3.8-2 4.1 -l a 4.1 -l a 4.1-2 4.1-2 4.1-3 4,1-3 4.1 -9d 4.1 -9d O
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TS 3.8-1 3.8 CONTAINMENT Applicability Applies to the integrity and operating pressure of the reactor containment.
Objective To define the limiting operating status of the reactor containment for unit operatien.
Specification A.
Containment Integritv and Operating Pressure 1.
The containment integrity, as defined in TS Section 1.0, shall not be violated unless the reactor is in the cold shutdown condition.
2.
The reactor containment shall not be purged whenever the Reactor Coolant System temperature is above 200*F.
3.
The inside and outside isolation valves in the steam jet air ejector suction line shall be locked, sealed or otherwise secured closed whenever the Reactor Coolant System temperature is above 200*F.
4.
The Reactor Coolant System temperature and pressure must not exceed 350*F and 450 psig, respectively, unless the air partial pressure in the containment is at a value equal to, or below, that specified in TS Fig. 3.8-1.
5.
The containment integrity shall not be violated when the reactor vessel head is unbolted unless a shutdown margin greater than 10 percent k/k is maintained.'
P Amendments 83 & 84 w.-
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TS 3.8-2 6.
Positive recctivity changes shall not be made by rod drive motion or l
boron dilution unless the containment integrity is intact.
7.
The containment isolation valves shall be listed in Tables 3.8-1 and 3.8-2.
B.
Internal Pressure 1.
If the internal air partial pressure rises to a point 0.25 psi above the allowable value of the air partial pressure (TS Fig. 3.8-1),
the reactor shall be brought to the hot shutdown condition.
2.
If the leakage condition cannot be corrected without violating the containment integrity or if the internal partial pressure continues to rise, the reactor shall be brought to the cold shutdown condition utilizing normal operating procedures.
3.
If the internal pressure falls below 8.25 psia the reactor shall be placed in t.he cold shutdown condition.
4.
If the air partial pressure cannot be maintained' greater than or equal to 9.0 psia, the reactor shall be brought to the hot shutdown condition.
Basis The Reactor Coolant System temperature and pressure being below 350*F and 450 psig, respectively, ensures that no significant amount of flashing steam will be formed and hence that there would 'oe ne significant pressure build-t up in the containment if there is a loss-of-coolant accident.
i Amendments 83 & 84 l
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TS 4.1-1s 2.
Each Pressurizer PORV block valve shall be demonstrated operable at least once per 92 days by operating the valve through one complete cycle of full travel.
3.
Tne pressurizer water volume shall be determined to be within its limit as defined in Specification 2.3.A.3.a at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the reactor is not subcritical by at least 1% ok/k.
C.
Sampling tests shall be conducted as detailed in Table 4.1-2B.
D.
Whenever containment integrity is not required, only the asterisked items in Table 4.1-1 and 4.1-2A and 4.1-2B are applicable, s
E.
Flushing of sensitized stainless steel pipe sections shall be conducted as detailed in TS Table 4.1-3A and 4.1-3B.
F.
The outside containment purge and vent isolation valves and the isolation valve in the steam jet air ejector suction line outside containment shall be determined locked, sealed, or otherwise secured in the closed position at least once per 31 days.
i G.
The inside contatament purge and vent isolation valves shall be determined i
j locked, sealed or otherwise secured in the closed position each 661d shutdown but not more often than once per 92 days.
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Amendments 83 & 84
TS 4.1-2 H.
During or immediately after the flushes required by Specification 4.1.E.
water flushed from the pipe section will be analyzed for chloride concem-tration and fluorld'e co'ncentration. If either the chloride or fluoride concentration exceeds 0.15 ppm, the flush will be continued or resumed until further samples indicate that the chloride concentration and the fluoride concentration in the sensitized pipe, have been reduced to less than 0.15 ppm.
Basis Check Failures such as blown instrument fuses, defective indicators, and faulted amplifiers which resultiin " upscale" or "downscale" indication can be easily recognized by simple observation of the functioning of an instrument or, system. Furthermore, such failures are, in many cases, revealed by alarm or annunciarbr action, and a periodic check supplements this type of built-in surveillance.
Based on 2xperience in operation of both conventional and nuclear unit systems, when the unit is in operation, the minimum checking frequencies set forth are deemed adequate for reactor and steam system instrumenta-tation.
Calibration Calibration shall be performed to ensure the presentation and acquisition of accurate information.
The nuclear flux (power level) channels shall be calibrated daily against a heat balance standard to account for errors induced by changing rod patterns and core physics parameters.
Amendments 83 & 84
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TS 4.1-3 s
Other channels are subject only to the " drift" arrors induced within the instrumentation itself and, consequently, can tolerate longer intervals between calibration. Process systems instrtssentation errors resulting from drif t within the individual instruments are normally negligible.
During the interval between periodic channel tests and daily check of each channel, a comparison between redundant channels will reveal any abnormal condition resulting from a calibration shift, due to instrument drift of a single channel.
1 During the periodic channel test, if it is deemed necessery, the channel may be tuned to. compensate for the calibration shif t. However, it is not expected that this will be required at any fixed or frequent interval.
Thus, minimum calibration frequencies of once-per-day for the nuclear flux (power level) channels, and once each refueling shutdown for the process system channels is considered acceptable.
Testing The =4n4-= testing frequency for those instrument channels connected to the safety system is based on an average unsafe failure race of 2/5 x 10-6 t
failure /hr per channel. This is based on operating experience at conventional and nuclear units. An unsafe failure is defined as one which negates channel operability and which, due to its nature, is revealed only when the channel is
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tested or when it attempts to respond to a proper signal.
Amendments 83 & 84
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TABLE 4.1-2A (CONTINUED)
MINIMUM FREQUENCY FOR EQUIPMENT TESTS FSAR SECTION DEECRIPTION TEST FREQUENCY
. REFERENCE
- 1. Periodic leakage testing (8 on each valve 18.
Primary Coolant System Functional listed in Specification 3.1.C.7a shall bc accomplished prior to entering power operation condition af ter every time the plant is placed in the cold shutdown condition for refueling, after each time the plant is placed in 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 accomp-lished in the preceeding 9 months, and prior to returning the valve to service after maintenance, repair or replace-ment work is performed.
19.
Containment Purge MOV Leakage Functional Semi-Annual (Unit at power or shutdown) if purge valves are operated during interval (c)
To satisfy ALARA requirements, leakage may be measured indirectly (as from the performance of pressure indicators) if accomplished in ac~cordance with approved procedures and supported by computctions showing that the method is capable of demonstrating valve compliance with the leakage criteria.
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Minimum differential test pressure shall not be below 150 psid.
i (c) Refer to Section 4.4 for acceptance criteria.
- See Specification 4.1.D.
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