ML20080T801
| ML20080T801 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/24/1984 |
| From: | Varga S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20080T803 | List: |
| References | |
| NUDOCS 8403020058 | |
| Download: ML20080T801 (18) | |
Text
.
j UNITED STATES
,6 s )fif(j.,
1 j I NUCLEAR REGU!.ATORY COMMISSION g
- ,E WASHINGTON, D. C. 20$55 b
%f.%Jj....f VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-280 SURRY POWER STATION, UNIT NC. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 95 License No. DPR-32 1.
The Nuclear Regulatory Commission (the Comission) has found that:
A.
The application for amendment by Virgiria Electric anc Power Company (the licensee) dated September 13, 1983, as supplemerced October 6, November 30, and December 19, 1983, and January 18 and 25, 1984, complies with the standards and re Act of 1954, as amended (the Act) quirements of the Atomic Energy and the Comission's rules and regulations set forth in 10 CFR Chapter I; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Tnere 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.
B403020050 840224 PDR ADOCK 05000280 P
'O
. 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 Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 95
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately and shall be implemented no later than March 9, 1984.
FOR THE NUCLEAR REGULATORY COMMISSION teven
- arga, Operating Reactor ranch No. 1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance:
FEB 2 41984
UNITED STATES
'Y '
g-NUCLEAR REGULATORY COMMISSION
- J'
.E-WASHINGTON, D. C. 20S55 o
s,
/
VIRGINIA ELECTRIC AND POWER COMPANY DOCKET N0. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. DPR-37 1.
The Nuclear Regulatory Commission (the Ccmmission) has found that:
A.
The application for amendment by Virginia Electric and Power Company (the licensee) dated September 13, 1983, as supplemented October 6 November 30, and December 19, 1983, and January 18 and 25,1984, complies with the standards and re Act of 1954,'as amended (the Act) quirements of the Atomic Energy and the Comission'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-
' Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health anti 51fety of the public, and (ii) that such activities will be 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 pu'lic; and o
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.
~
-2 2.
Accordingly, the license-is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. DPR-37 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 94
, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective immediately and shall be implemented no later than March 30, 1984.
FOR THE NUCLEAR REGULATORY COMMISSION hi__
\\
gte %ven A.
rga, C Operating Reactors nch No. 1 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: ggg m
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ATTACHMENT TO LICENSE AMENDMENTS Af1ENDMENT NO. 95 'TO FACILITY OPERATING LICENSE N0. DPR-32 AMENDMENT NO. 94 TO FACIL1TY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:
Remove Pages Insert Pages 3.2-1 3.2-1
-3.2-2 3.2-2 3.2-4 3.2-4 3.2-5 3.2-5 3.3-1 3.3-1 3.3-2 3.3-2 3.3-3 3.3-3 3.3-5 3.3-5 3.3-9 3.3-9 4.1 4.1-7 4.1-8 4.1-8
-4.1-9 4.1-9 4.1-10 4.1-10 l
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s TS 3.2-1
.2.
CHEMICAL AND VOLUM5 CONTROL SYSTEM 3
- Applicability Applies to the operational status of-the Chemical and Volume Control System.
-Objective
- -To define'those conditions'of the Chemical and Volume Control System necessary
~
-to ensure. safe reactor operation.
Specification
^A..
When fuel is in a reactor there shall be.at least one flow path to the core for:- boric acid - injection.
The -minimum capability for boric ' acid
- injection _shall be-equivalent to that supplied from the refueling water storage. tank.
iB.
For 'one. unit operation 'the reactor shall not be critical unless the
-following Chemical and Volume Control System conditions are met:
- 1..Two charging pumps shall.be operable.
2.
Two boric acid transfer pumps shall be' operable.
' 3L.: The-boric acid. tanks (tank associated with the unit plus the common tank) together.shall contain a minimum of 6000 gallons of at least 7.0% (but not greater than 8.5%} by' weight boric ~ acid solution at
- a-temperatdre ofl at least 112*F.
Amendment Nos. 95 and 94
TS 3.2 ~
4.-
System piping and valves :shall be operable to the extent of establishing two flow paths to the-core; one flow path from the boric-acid tanks to the charging pumps and a flow path frcm the refueling water storage. tank to the charging pumps.
5.
Two. channels of heat tracing shall be operable for the flow paths requiring heat tracing.-
C.
For two unit operatton the-reactor shall not be critical unless the following Chemical and Volume Control System conditions are met:
1.
Two charging pumps:shall be operable per unit.
2.
Three boric acid transfer pumps shall be operable.
3.When the common tank _is~in service, it shall be assigned to_only one unit at a.-time.-;For that unit which has usage of the common tank, the boric acid ' tauks (unit's tank plus common tank) together shall contain a minimum of;6000 gallons of at least 7.0% (but not greater than 8.5%) by weight boric acid solution at a temperature
~ of at least 112*F.
For that unit which does not have usage of the common tank, the unit's own' tank shall contain a minimum of 6000 gallons of at j
-least 7.0% (but not greater than 8.5%)- by weight boric acid solution rat a temperature of at least il2*F.
When the common tank is-assigned to one unit, valves shall be
. positioned to establish a flow path to that unit and prevent flow
-to the other unit.
Amendment flos. 95 and 94
~
- asis 7$ 3.2 2 The Chemical and Volume Control System provides control of the Keactor Coolant System Boron inventory.
This is normally accomplished by using boric acid
' transfer pumps which discharge to the suction of each unic's charging pumps.
The Chemical and. Volume _ Control System contains four boric acid transfer
. pumps '.
Two of these pumps are normally assigned to each unit but valving and
-- ~
piping arrangements allow pumps to.be shared such that 3 out of 4 pumps can service either unit.
An alternate (not normally used) method of boration is to use - the charging pumps-takf ug suction directly from the refueling water storage tank. There are two sources of borated water available to the suction of the charging pumps through two different paths, one from the. refueling water storage-tank and one from the discharge of the boric acid. transfer pumps.
A.
The boric acid transfer pumps can deliver the boric acid tank
. contents _(7.0% solution of boric acid) to the charging pumps.
B.:.The charging' pumps can take suction from the volume control tank, the boric acid transfer pumps and the refueling water storage-tank.
Reference ~is made to Technical Specification 3.3.
The quantity of-boric acid in storage from-either the boric acid tanks or the refueling _ water-storage tank is sufficient to borate the reactor coolant -in order to reach cold shutdown at any time during core life.
Approximately 6000 gallons of the 7.0% solution of boric acid are required to meet cold shutdown conditions.
Thus, a minimum of 6000 gallons in the boric acid tank is specified.
An-upper concentration limit of 8.5% boric acid in i
Amendment Nos. 95 and 94 i
'~
TS 3.2-5 the tank is specified to maintain solution solubility at the specified low temperature limit of 112*F.
For redundancy, two channels of heat l
tracing are installed on lines normally containing concentrated boric acid solution.
The - Boric Acid Tank (s), which are located above the Boron Injection Tank (s), are supplied with level alarms, which would annunciate if a leak in the system occurred.
. References FSAR Section 9.1 Chemical and Volume Control System Amendment Nos. 95 and 94
~ _
TS 3.3-1 v-3.3 SAFETY INJECTION SYSTEM e
Applicability
. Applies to the operating status of the Safety Injection System.
Objective
. To define those limiting conditions for operation that are necessary to provide sufficient borated cocling water to remove decay heat from the core in emergency situations.
Specifications A.
_A' reactor shall not be-made critical unless the following conditions are met:
1.
The refueling water storage tank contains not less than 387,100 gal of borated water. The boron concentration shall be at least 2000 ppm and not greater than 2200. ppm.
2.
Each accumulator system is pressurized to at least 600 psia and 3
3 contains a minimum of 975 ft and a maximum of 989 ft of borated water with a boron concentration of at least 1950 ppm.
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Amendment Nos. 95 and 94 4
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TS 3.3-2 3.
Two chanc.els of heat tracing shall 'oe available for the flow paths.
l 4.
Two charging pumps are operable.
-l 1
5.-
.Two low head safety injection pumps are operable.
6.
All valves, piping, and interlocks asJociated with the above l
components which are required to operate under accident condi-tions are operable.
7.
The Charging Pump Coaling Water Subsystem shall be operating as l
follows:
a..
Make-up water from the Component Cooling Water Subsystem shall be available.
b.
Two charging pump. component cooling water pumps and two charging pump. service weter pumps shall be operable.
c.
Two charging pump intermediate seal coolers shall be operable..
8..
. During power operation the A.C. power shall bc removed from the l
following motor operated valves with the valve in the'open position:
Unit No. 1 Unit No. 2 MOV 1890C.
MOV 2890C 9..
During power operation the A.C. power shall be removed from the l
. following motor operated valves with the valve in the closed
. position:
Unit No. 1 Unit No. 2 MOV 1869A-MOV 2869A MOV 1869B MOV 2869B MOV 1890A MOV 2890A MOV 1890B MOV 2890B Amendment Nos. 95 and 94 3
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TS 3.3-3 10.
The accumulator discharge valves listed below in non-isolated loops shall be blocked open by de-energizing the valve motor operator when the reactor coolant system pressure is greater than 1000 psig.
Unit No. 1 Unit No. 2 MOV 1865A MOV 2865A MOV 1865B MOV 2865B MOV 1865C MOV 2865C 11.
Power operation with less than three loops in service is prohibited.
l The following loop isolation valves shall have AC power removed and be locked in open position during power operation.
Unit No.~1 Unit No. 2 MOV 1590 MOV 2590 MOV 1591 MOV 2591 MOV 1592 MOV 2592 MOV 1593 MOV 2593 MOV 1594 MOV 2594 J
The total system uncollected leakage from' valves, flanges, and pumps l
located outside containment shall not exceed the limit shown in Table 4.11-1-as verified by inspection during' system testing.
Individual component leakage may exceed.the design value given in Table 4.11-1 provided that the total allowable system uncollected
~
leakage is not' exceeded.
Amendment Nos. 95 and 94 Li.
TS 3.3-5 6.
One charging pump component cooling water pump or one charging pump service water pump may be out of service provided the pump
-is 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 />.
7.
One charging pump intermediate seal cooler or other passive component may be out of service provided the system may still operate at 100 percent capacity and repairs are completed within
-48 hours.
8.
Power may be restored to any valve referenced in Specifications 3.3.A.9 and 3.3.A.10 for the purpose of valve testing or maintenance provided that no more than one valve has power restored and provided that testing and maintenance is completcd and power removed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
9.
Power may be restored to any valve referenced in Specification 3.3.A.ll for the purpose of valve testing or maintenance provided that no more than one' valve has power restored and provided that testing or maintenance is completed and power removed within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
10.
~The total uncollected system leakage for valves, flanges, and pumps located outside containment can exceed the limit shown in Table 4.11-1 provided immediate attention is directed to making repairs and system leakage is returned to within limits within 7 days.
4 f
Amendment Nos 95 and 94
TS 3.J-9
~
The accumulators (one for each loop) discharge into the cold leg of the reactor' coolant piping when Reactor Coolant System pressure decreases below accumulator pressure, thus assuring rapid core cooling for large breaks. The linegfrom each accumulator is provided with a motorized valve to isolate the accumulator during reactor start-up and shutdown to preclude the discharge of.the contents of the accumulator when not required. These valves receive a signal to epen when safety injection is initiated.
To assure th'at the accumulator valves satisfy the single failure criterion,'they will be blocked open by de-energizing the valve motor operators when the reactor' coolant pressure exceeds 1000 psig. The operating ~ pressure of the Reactor Coolant System is 2233 psig and safety injection is initiated when this pressure drops:to 600 psig.. De-energiz-ing-the motor operator when the pressure exceeds 1000 psig allows.
sufficient _ time during normal startup. operation to perform the actions required.to.de-energize the valve. This procedure will assure that there is an operable ^ flow path from each accumulator to the Reactor Coolant-System during power operation and that. safety injection can be accom-
~
-plished.
The removal of power from the valves listed in the specification will-assure that the systems of which they are a part satisfy the single failure criterion.
Amendment Nos'. 95 and 94 e
TABLE 4.1-1 (Crntinuid)~
. Channel Description Check:
Calibrate
' Test i.ema rks 10.
Rod Position Bank Counters S (1,2):
N.A.
N.A.
- 1) Each six inches of rod motion
'when data logger is out of' service
- 2) With analog rod position
- 11. ' Steam Generator Level S
R M
12.
Charging Flow.
N.A.
R-N.A.
13.
Residual Heat. Removal Pump-Flow
.N.A.
R
.N.A.
14.
Boric Acid Tank-Level
- D R
N.A.
15.
Refueling. Water Storage Tank Level S
R H
16.
Volume Control Tank Level N.A.
R.
N.A.
17.
Reactor Containment Pressure-CLS
- D R
M (1)
- 1) Isolation Valve signal and spray signal 18.
Process and Area' Radiation Moni-toring System
- D R
M 19.
Boric Acid Control N.A.
R d.A.
, 20.
Containment Sump Level N.A.
R N.A.
mi 21.
Accumulator Level and Pressure S
R N.A.
5 3 22.
Containment Pressure-Vacuum Pump
- l System S
R N.A.
p
=
O S
R M.
4 L.
23.
Steam Line Pressure
, 24.
Turbine First Stage Pressure S
R M
S 25.
Emergency Plan Radiation Instr.
- M R
M q3a
TABLE 4.1-1 (Centinued)'
Chrnnel Description Check Calibrate Test
~ Remarks 26.
. Environmental. Radiation-Monitors
- M_
N.A.
N.A.
TLD Dosimeters 27.
Logic. Channel: Testing N.A.
N.A.
M 28.
Turbine Overspeed Protection Trip _
N.A.
R R
Channel (Electrical) 29, Turbine Trip Setpoint N.A.
R R
Stop valve closure or low EH fluid pressure 30.
Seismic Instrumentation M
R H
31.
Reactor Trip Breaker N.A.
N.A.
M 32.
Reactor Coolant Pressure N.A.
R N.A 33.
Steam Generator Water Level S
R M
Low-Low b.
R M
c.
S.I.
(All Safety injection surveillance requirements) d.
Station Blackout N.A.
R N.A hf e.
Main Feedwater Pump Trip N.A.
N.A.
R g S - Each shift M - Monthly D - Daily P - Prior to each startup if not done previous week d
2g W - Weekly R - Each Refueling Shutdown p
NA - Not applicable BW - Every two weeks e SA - Semiannually AP - After each startup if not done previous week 4
Q - Every 90 effective full power days EL e* *See Specification 4.lD
m
. TABLE 4.1-1'(Continu7.d)
-Chrnnel Description Check-Calibrate Test Remarks 34.
Loss'of Power a.
~4.16 KV' Emergency Bus.
N.A.
R M
undervoltage (Loss of voltage).
b.
4.16'KV Emergency Bus N.A.
R M
undervoltage (Degraded voltage) 3 4
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TS 4.1-10 TABLE 4.1-2B MINIMUM FREQUENCIES FOR SAMPLING TESTS FSAR SECTION DESCRIPTION TEST FREQUENCY REFERENCE 1.
Reactor Coolant Liquid Radio-Chemig Monthly (5)
Samples Analysis Gross Activity (2) 5 days /weg)(5) 9.1 Tritium Activity Weekly 9.1
- Chemistry (CL, F & 0 )
5 days / week 4
2
= Boron Concentration Twice/ week 9.1 Semiannuallyf f Determination Once/2 weeks (5 DOSE EQUIVALENT I-131
}
Radio-iodine Once/4 hours Analysis (including I-and-(7) below 131, I-133 & I-135) 2.
Refueling Water Storage Tank Water Sample Boron Concentraeion Weekly 6
3.
Boric Acid Tanks
- Boron Concentration Twice/ Week 9.1 4.
Chemical Additive Tank NaOH Concentration Monthly' 6
l 5.
Spent Fuel Pit'
- Boron Concentration Monthly 9.5 l
6.
' Secondary coolant Fifteenminutedegagd Once/72 hours 10.3 l
b and q activity DOSE EQUIVALENT I-131 Monthly (
Semiannually (8) 7.
Stack Gas Iodine and
- I-131 and particlate Weekly l
-Particulate Samples radioactive releases l
-8.
-Accumulator Boron Concentration Monthly 6.2 OSee Specification 4.1.D
(
A radiochemical analysis will be made to evaluate the following corresion products:
Cr-51, Fe-59, Mn-54, Co-58, and Co-60.
-( }
A gross beta-gamma degassed activity analysis shall consist of the quanti-tative measurement of the total radioactivity of the primary coolant in units of uCL/cc..
Amendment Nos. 95 and 9a
-