ML20092A305
| ML20092A305 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/01/1995 |
| From: | Matthews D NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20092A311 | List: |
| References | |
| NUDOCS 9509080333 | |
| Download: ML20092A305 (10) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0(C1
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-?aQ
- 5. WRY POWER STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 204 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 July 14, 1995, 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.
l 9509080333 950901 PDR ADOCK 05000280 P
. 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, ar.d paragraph 3.8 of Facility Operating Licerise No. DPR-32 is hereby amended to read as follows:
(B)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 204, 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 k0 EW PL David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 1, 1995
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NUCLEAR REGULATORY COMMISSION f
WASHINGTON, D.C. 20555-0001
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SVRRY POWER STATION. UNIT N0. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 204 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated July 14, 1995, complies with the standards and requirements. of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter c!;
B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 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 i
conducted in compliance with the Comission'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 Comission's regulations and all applicable requirements have been satisfied.
i
, 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 Specificationg The Technical Specifications contained in Appendix A, as revised through Amendment No. 204, 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 4
Q"Y-LN David B. Matthews, Director Project Directorate 11-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 1,1995 l
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
204 TO FACILITY OPERATING LICENSE NO. DPR-32 AMENDMENT NO.
204 TO FACILITY OPERATING LICENSE N0. OPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Paoes Insert Paoes 3.1-2 3.1 2 3.1-23 3.1-23 3.1-23a 3.1-23a 3.1-24 3.1-24 3.1-25 3.1-25
TS 3.12 b.
If an unscheduled loss of one or more reactor coolant pumps occurs while operating below 10% RATED POWER (P-7) and I results in less than two pumps in service, the affected plant shall be shutdown and the reactor made subcritical by inserting all control banks into the core. The shutdown rods may remain withdrawn.
When the average reactor coolant loop temperature is greater c.
than 350 F, the following conditions shall be met:
1.
At least two reactor coolant loops shall be OPERABLE.
l 2.
At least one reactor coolant loop shall be in operation.
d.
When the average reactor coolant loop temperature is less than or equal to 350 F, the following conditions shall be met:
1.
A minimum of two non-isolated loops, consisting of any combination of reactor coolant loops or residual heat removal loops, shall be OPERABLE, except as specified below:
(a)
One RHR loop may be inoperable 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 surveillance testing provided the other RHR loop is OPERABLE and in operation.
(b)
During REFUELING OPERATIONS the residual heat removal loop may be removed from operation as specified in TS 3.10.A.6.
2.
At least one reactor coolant loop or one residual heat removal loop shall be in operation, except as specified in Specification 3.10.A.6.
Amendment Nos. 204 and 204
TS 3.1-23 1
G.
Reactor Coolant System Overoressure Mitigation Soecification 1.
The Reactor Coolant System (RCS) overpressure mitigating system shall be OPERABLE as described below:
a.
Whenever the RCS average temperature is greater than 350 F, a bubble shall exist in the pressurizer with the necessary sprays and heaters OPERABLE.
b.
Prior to decreasing RCS average temperature below 350 F, verify a maximum of one charging pump is capable of injecting into the RCS and that each accumuistor is isolated. Thereafter, once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s:
(1)
~ Verify that a maximum of one charging pump is capable of injecting into the RCS.
(2)
Verify that each accumulator is isolated, if isolation is required.
c.
Whenever the RCS average temperature is less than or equal to l 350 F and the reactor vessel head is bolted:
(1) A maximum of one charging pump shall be OPERABLE and capable of injecting into the RCS. Two charging pumps may be in operation momentarily during transfer of operation from one charging pump to another.
and (2)
The accumulators shall be isolated (accumulator discharge valves closed and their respective breakers locked, sealed or otherwise secured in the open position). Isolation is not required if the accumulator pressure is less than the pressurizer PORV setpoint specified in TS 3.1.G.1.c.(4).
and Amendment Nos. 204 and 204
~..
TS 3.1-23a (3)
During the initial 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, maintain a bubble in the pressurizer with a maximum narrow range level of 33%,
or (4)
Maintain two Power Operated Relief Valves (PORV)
OPERABLE with a lift setting of s; 385 psig and verify each PORV block valve is open at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or (5)
The RCS shall be vented through one open PORV or an equivalent size opening as specified below:
(a) with the RCS vented through an unlocked open vent i
path, verify the path is open at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or (b) with the RCS vented through a locked open vent path verify the path is open at least once per 31 days.
2.
The requirements of Specification 3.1.G.1.c.(4) may be modified as i follows:
a One PORV may be inoperable in INTERMEDIATE SHUTDOWN with the RCS average temperature > 200 F but < 350 F for a period not to exceed 7 days. If the inoperable PORV is not restored to OPERABLE status within 7 days, then completely depressurize the RCS and vent through one open PORV or an equivalent size opening within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
b One PORV may be inoperable in COLD SHUTDOWN or REFUELING SHUTDOWN with the reactor vessel head bolted for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If the inoperable PORV is not restored to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> then completely depressurize the RCS and vent through one open PORV or an equivalent size opening within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
Amendment Nos. 204 and 204
TS 3.1-24 c.
With both PORV's inoperab!e, depressurize the RCS within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> unless Specification 3.1.G.1.c.(3) is in effect. When the RCS l has been depressurized, vent the RCS through one open PORV or an equivalent sized opening, or establish the conditions listed below. Maintain the RCS depressurized until both PORV's have been restored to OPERABLE status.
(1)
A maximum pressurizer narrow range level of 33%.
(2)
The series RHR inlet valves open and their respective breakers locked open or an alternate letdown path OPERABLE.
(3)
A maximurn of one charging pump is capable of injecting into the RCS.
(4)
Safety injection accumulator discharge valves closed and their respective breakers locked, sealed, or otherwise secured in the open position.
d.
When the conditions noted in 3.1.G.2.c.(1) through 3.1.G 1.c.(4) above are required to be established, verify the required conditions are met at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
3.
In the event that the Reactor Coolant System Overpressure Mitigating System is used to mitigate a RCS pressure transient, a Special Report j
shall be prepared and submitted to the Commission pursuant to Specification 6.6 within 30 days.
The report shall describe the circumstances initiating the transient, the effect of the mitigating system or the administrative controls on the transient and any corrective actions necessary to prevent recurrence.
Basis The operability of two PORV's or the RCS vented through an opened PORV ensures that the Reactor Vessel will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when the Reactor Coolant System average temperature is s 350 F and the Reactor Vessel Head is bolted. When the Reactor Coolant System average temperature is > 350cF, overpressure protection is provided Amendment Nos. 204 and 204
TS 3.1-25 by a bubble in the pressurizer and/or pressurizer safety valves. A single PORV has adequate relieving capability to protect the Reactor Vessel from overpressurization when the transient is limited to either (1) the start of an idle Reactor Coolant Pump with the secondary water temperature of a steam generator s 50 F above the RCS cold leg temperature or (2) the start of a i
charging pump and its injection into a water solid RCS.
The limitation for a maximum of one charging pump allowed OPERABLE and the surveillance required to verify that two charging pumps are inoperable below 350 F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV, or equivalent. The Safety injection accumulators are not considered a credible mass input mechanism for RCS low temperature overpressurization concerns. There are administrative controls to ensure isolation, including de-energizing the Safety injection (SI) accumulator isolation valves, during plant shutdown conditions (RCS pressure less than 1000 psig) to prevent inadvertent Si accumulator discharge into the RCS for low temperature overpressurization concerns. An undesired pressurizer PORV lift due to inadvertent Si accumulator discharge is not possible when Si accumulator pressure is less than the low temperature PORV lift setpoint specified in TS 3.1.G. Therefore, Si accumulator isolation, and verification of such isolation is not necessary when Si accumulator pressure is less than the low temperature PORV setpoint.
A maximum pressurizer narrow range level 'of 33% has been selected to provide sufficient time, approximately 10 minutes, for operator response in case of a malfunction resulting in maximum charging flow from one charging pump (530 gpm). Operator action would be initiated by at least two alarms that would occur between the normal operating level and the maximum allowable level (33%). When both PORVs are inoperable and it is impossible to manually open at least one PORV, additional administrative controls shall be implemented to prevent a pressure transient that would exceed the limits of Appendix G to 10 CFR Part 50.
The requirements of this specification are only applicable when the Reactor Vessel head is bolted. When the Reactor Vessel head is unbolted, a RCS pressure of < 100 psig will lift the head, thereby creating a relieving capability equivalent to at least one PORV.
Amendment Nos. 204 and 204
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