ML20035H126
| ML20035H126 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/22/1993 |
| From: | Berkow H Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20035H127 | List: |
| References | |
| NUDOCS 9305030179 | |
| Download: ML20035H126 (10) | |
Text
8'.,a ucg'o, UNITED STATES a
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'j NUCLEAR REGULATORY COMMISSION
.C W ASHINGTON, D. C. 20555
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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. 177 License No. DPR-32 l.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated December 11, 1992, 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 1
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.
H 9305030179 930422 PDR ADOCK 05000200 P
. 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-32 is hereby amended to read as follows:
(B)
Technical Snecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.177, 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 its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
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Herbert N. Berkow Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 22,1993
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og'o, UNITED sT ATEs
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-y W ASHWGTON, D. C. 20555 9
4.....P VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-201 SURRY POWFR STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENS1 Amendment No.176 License No. DPR-37 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 11, 1992, 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.
m i
I 1
a
. 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 hereby amended to read as follows:
(B)
Technical Soecifications The Technical Specifications contained in Appendix A, as revised through Amendment No.176, are hereby incorporated in the i
license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
'l j
Her ert N. Berkow, Director Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 22, 1993 i
I i
ATTACHMENT TO LICENSE AMENDMENT i
AMENDMENT NO. 177 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO. 176 TO FACILITY OPERATING LICENSE NO. DPR-37 I
DOCKET NOS. 50-280 AND 50-281 Rev'tse Appendix A as follows:
Remove Paces Insert Paces i
3.1/-1 3.17-1 3.17-2 3.17-2 3.17-3 3.17-3 i
3.17-4 i
3.17-5 l
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3 i
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TS 3.17-1 j
3.17 LOOP STOP VALVE OPERATION l
l Anoticability i
Applies to the operation of the loop stop valves.
l Obiective t
To specify those limiting conditions for operation of the loop stop valves whichl
}
must be met to ensure safe reactor operation.
3 l
Soecifinntions j
1.
The loop stop valves shall be maintained open unless the reactor is in l
COLD SHUTDOWN or REFUELING SHUTDOWN.
f I
2.
A hot or cold leg stop valve in a reactor coolant loop may be closed in i
COLD SHUTDOWN or REFUELING SHUTDOWN for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for valve maintenance or testing. If the stop valve is not opened within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, the loop shall be isolated.
f 3.
Whenever a reactor coolant loop is isolated, the stop valves of the
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isolated loop shall have their AC power removed and their breakers locked open.'
(
4.
Whenever an isolated and filled reactor coolant loop is returned to j
service, the following conditions shall be met:
A source range nuclear instrumentation channel shall be operable a.
and continuously monitored with audible indication in the control room during opening of the hot leg loop stop valve, during relief f
line flow, and when opening the cold leg stop valve in the isolated l
loop. Should the count rate increase by more than a factor of two over the initial count rate, the hot and cold leg stop valves shall be l
re-closed and no attempt made to open the stop valves until the j
reason for the count rate increase has been determined.
l Power may be restored to a hot or cold leg loop stop valve in an isolated and i
filled loop provided the requirements of Specifications 4.b or 4.c are met, j
respectively. Power may be restored to a loop stop valve in an isolated and l
drained loop provided the requirements of Specifications 5.a and b are met.
l Amendment Nos.177 and 176 l
TS 3.17-2 b.
Before opening the hot leg loop stop valve.
1)
The boron concentration of the isolated loop shall be greater than or equal to the boron concentration in the active loops.
Verification of this condition shall be completed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to opening the hot leg stop valve in the isolated loop.
c.
Before opening the cold leg loop stop valve.
1)
The hot leg loop stop valve shall be open with relief line flow established for at least 90 minutes at greater than or equal to 125 gpm.
2)
The cold leg temperature of the isolated loop shall be at least 70 F and within 20 F of the highest cold leg temperature of the active loops.
Verification of this condition shall be completed within 30 minutes prior to opening the cold leg stop valve in the isolated loop.
3)
The boron concentration of the isolated loop shall be greater than or equal to the boron concentration in the active loops.
Verification of this condition shall be completed after relief line flow for at least 90 minutes at greater than or equal to 125 gpm and within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to opening the cold leg stop vatve in the isolated loop.
5.
Whenever an isolated and drained reactor coolant loop is filled from the active volume of the RCS, the following conditions shall be met:
a.
The isolated loop shall be drained. Verification of this condition shall be completed within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> prior to partially opening the hot or cold leg stop valve in the isolated loop.
i b.
The Reactor Coolant System level shall be at least 18 ft. during opening of the loop stop valves and during the filling of the isolated loop. If Reactor Coolant System levelis not maintained at 18 ft. or above, the loop stop valves shall be closed.
Amendment Nos. 177 and 176
a TS 3.17-3 c.
The hot and cold leg stop valves shall be fully opened within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the isolated loop is filled.
d.
A source range nuclear instrumentation channel shall be operable and continuously monitored with audible indication in the control room during the backfill evolution. Should the count rate increase by more than a factor of two over the initial count rate, the hot and cold leg stop valves shall be re-closed and no attempt made to open the stop valves until the reason for the count rate increase has been determined.
Basis The Reactor Coolant System may be operated with isolated loops in COLD SHUTDOWN or REFUELING SHUTDOWN in order to perform maintenance. A loop stop valve in any loop can be closed for up to two hours without restriction for testing or maintenance in these operating conditions. While operating with a loop isolated, AC power is removed from the loop stop valves and their breakers locked opened to prevent inadvertent opening. When the isolated loop is retumed to service, the coolant in the isolated loop mixes with the coolant in the active loops. This situation has the potential of causing a positive reactivity addition with a corresponding reduction of shutdown margin if:
- a. The temperature in the isolated loop is lower than the temperature in the active loops (cold water accident), or
- b. The boron concentration in the isolated loop is insufficient to maintain the required shutdown margin (boron dilution accident).
The ret;rn to service of an isolated and filled loop is done in a controlled manner that virtually eliminates any sudden positive reactivity addition from cold water or boron dilution. A flow path to mix the isolated loop with the active loops is established through the relief line by opening the hot leg stop valve in the isolated loop and starting the reactor coolant pump. The relief line flow is low enough to limit the rate of any reactivity addition due to differences in temperature and boron concentration between the isolated loop and the active loops. In addition, a source range instrument channei is required to be operable and continuously monitored to detect any change in core reactivity.
Amendment Nos.177 and 176
TS 3.17-4 The limiting conditions for returning an isolated and filled loop to service are as follows:
- a. A hot leg loop stop valve may not be opened unless the boron concentration in the isolated loop is greater than or equal to the boron concentration in the active portion of the Reactor Coolant System.
- b. A cold leg loop stop valve can not be opened unless the hot leg loop stop valve is open with relief line flow established for at least 90 minutes at greater than or equal to 125 gpm. In addition, the cold leg temperature of the isolated loop must be at least 70 F and within 20*F of the highest cold leg temperature of the active loops. The boron concentration in the isolated loop must be verified to be greater than or equal to the boron concentration in the active portion of the Reactor Coolant System.
- c. A source range nuclear instrument channel is required to be monitored to detect any unexpected positive reactivity addition during hot or cold leg stop valve opening and during relief line flow.
If an isolated loop is initially drained, the above requirements are not applicable. An initially isolated and drained loop may be returned to service by partially opening the loop stop valves and filling the loop in a controlled manner from the Reactor Coolant System. Prior to partially opening the loop stop valves, the following measures are required to ensure that no sudden positive reactivity addition or loss of Reactor Coolant System inventory cccurs:
- a. The isolated loop is verified to be drained, thus preventing dilution of Reactor Coolant System boron concentration by liquid present in the loop.
T
- b. Reactor Coolant System levelis verified to be 218' elevation to ensure Reactor Coolant System inventory is maintained for decay heat removal. Reactor Coolant System inventory is required to be maintained at 218' elevation during the backfill evolution. In addition, the filling evolution is limXed to one isolated loop at a time.
i
- c. A source range nuclear instrument channel is required to be monitored to detect any unexpected positive reactivity addition.
Amendment Nos.177 and 176
TS 3.17-5 After an initially drained loop is filled from the Reactor Coolant System by partially opening the loop stop valves, the loop is no longer considered to be isolated. Thus, the requirements for returning an isolated and filled loop to service are not applicable and the loop stop valves may be fully opened without restriction within two hours of j
completing the loop fill evolution.
The initial Reactor Coolant System level requirement has been established such that, even if the three cold leg stop valves are suddenly opened and no makeup is available, the Reactor Coolant System water level will not drop below mid-nczzle level. This ensures continued adequate suction conditions for the residual heat I
removal pumps.
'l The safety analyses assume a minimum shutdown margin as an init!al condition.
Violation of these limiting conditions could result in the shutdown margin being reduced to less than that assumed in the safety analyses, in addition, violation of i
i these limiting conditions could also cause a loss of shutdown decay heat removal.
j i
Reference
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(1)
UFSAR Section 4.2 (2)
UFSAR Section 14.2.5 Amendment Nos.177 and 176
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