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{{#Wiki_filter:'' -
{{#Wiki_filter:k RANCHO SECO UNIT 1 Vs TECHNICAL SPECIFICATIONS Limiting conditions fur Operation 3.3.3 Prior to initiating maintenan;e on any of the component (s), the duplicate (redundant) components shall be verified operable by
k                                       RANCHO SECO UNIT 1 Vs                                   TECHNICAL SPECIFICATIONS                                     '
'A checking that the surveillance test for the component (s) has been W
Limiting conditions fur Operation 3.3.3     Prior to initiating maintenan;e on any of the component (s), the duplicate (redundant) components shall be verified operable by
successfully completed and will remain in effect for the. duration of the maintenance period. Inservice testing per specification 4.2.2.1 shall not be performed on arty component (s) whose duplicate (redundant) component (s) has (have) been declared inoperable or is out of service for any reason. -
    'A                       checking that the surveillance test for the component (s) has been W                       successfully completed and will remain in effect for the. duration of the maintenance period. Inservice testing per specification 4.2.2.1 shall not be performed on arty component (s) whose duplicate                     ,
3.3.4 During power operation, hot standby, hot shutdown or startup conditions, the primary coolant system pressure isolation valves shall be functional as follows:
(redundant) component (s) has (have) been declared inoperable or is             '
1.
out of service for any reason. -
All pressure isolation valves If sted in Table 3.3-1 shall oe functional as a pressure isolation device, except as specified in 3.3.4.2.
3.3.4     During power operation, hot standby, hot shutdown or startup conditions, the primary coolant system pressure isolation valves shall be functional as follows:
Valve leakage shall not exceed the amounts indicated.
: 1. All pressure isolation valves If sted in Table 3.3-1 shall oe functional as a pressure isolation device, except as specified in 3.3.4.2. Valve leakage shall not exceed the amounts indicated.
2.
: 2. In the event that integrity of any pressure isolation valve specified in Table 3.3-1 cannot be demonstrated, reactor               ,
In the event that integrity of any pressure isolation valve specified in Table 3.3-1 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. a) 3.
operation may continue, provided that at least two valves in each remainhigh in, pressure the modeline having a non-functional corresponding                valve to the isolated    are in(and condition. a)
If Specifications 3.3.4.1 and 3.3.4.2 cannot be met, a shutdown shall be initiated, the reactor shall not rmain critical and shall be brought to a cold shutdown concition within an
: 3. If Specifications 3.3.4.1 and 3.3.4.2 cannot be met, a shutdown shall be initiated, the reactor shall not rmain critical and shall be brought to a cold shutdown concition within an
' additional 24 hours.
                                ' additional 24 hours.
3.3.5 Should the redundant equipment or system as specified ir Section 3.3.3 become inoperable, as defined in Specification 1.3, the reactor shall not remain critical and shall be placed in cold shutdown condition l
3.3.5 Should the redundant equipment or system as specified ir Section 3.3.3 become inoperable, as defined in Specification 1.3, the reactor shall not remain critical and shall be placed in cold shutdown condition               l within 48 hours,                                                                 j g         Bases The requirements of Specification 3.3.1 assure that, before the reactor can be           !
within 48 hours, j
made critical, adequate safety features are operable. Two high pressure injection pumps and two decay heat removal pumps are specified. However, only one of each is necessary to supply emergency coolant to the reactor in the event of a loss-of-coolant accident. Both core flooding tanks are required as a single core flood tank has insufficient inventory to reflood the core.(1)
g Bases The requirements of Specification 3.3.1 assure that, before the reactor can be made critical, adequate safety features are operable. Two high pressure injection pumps and two decay heat removal pumps are specified. However, only one of each is necessary to supply emergency coolant to the reactor in the event of a loss-of-coolant accident. Both core flooding tanks are required as a single core flood tank has insufficient inventory to reflood the core.(1)
The borated water storage tank is used for two purposes:
The borated water storage tank is used for two purposes:
A. As a supply of borated water for accident conditions.
A.
ru o$$             8.
As a supply of borated water for accident conditions.
As a supply   of borated water {Jcr floocing the fuel transfer canal R8'                    during refueling   operationd2 8       390,000 gallons of borated water are supplied for emergency core cooling and So g        Reactor Building spray in the event of a loss-of-core coolant accident. This Ou           amount fulfills requirements for voergency core cooling. The boraped water
ru o$$
      $0           storage tank minimum volume of 390,000 gallons is based on refueling volume n<           re qui rements. Heaters maintain the borated water supply at a temperature to           !
8.
E            prevent freezing. The boron concentration is set at the amount of boron                 '
As a supply of borated water {Jcr floocing the fuel transfer canal during refueling operationd2 R8' 8
Rg           required to maintain the core 1 percent sIJberitical at 70*F without any con n.       control rods in the core. This concentration is 1585 ppm boron while tne minimum value specified in.the tanks is 1,800 ppm boron.
So 390,000 gallons of borated water are supplied for emergency core cooling and Reactor Building spray in the event of a loss-of-core coolant accident. This Ou g
amount fulfills requirements for voergency core cooling. The boraped water
$0 storage tank minimum volume of 390,000 gallons is based on refueling volume n<
re qui rements. Heaters maintain the borated water supply at a temperature to E
prevent freezing. The boron concentration is set at the amount of boron Rg required to maintain the core 1 percent sIJberitical at 70*F without any con n.
control rods in the core. This concentration is 1585 ppm boron while tne minimum value specified in.the tanks is 1,800 ppm boron.
l
l
          .g       (a)       Motor operaten valves shall be placed in the closed position and power supplies deenergized.
.g (a)
Amendment No. 4, Of#Wf #f#/         3-21 9/#/M, 67, M , Revised 7/8/87                                         __    ____
Motor operaten valves shall be placed in the closed position and power supplies deenergized.
Amendment No. 4, Of#Wf #f#/
3-21 9/#/M, 67, M, Revised 7/8/87


f,.
f,.
l l
l l
l                   Mr. G. Carl Andognini                   Rancho Seco Nuclear Generating Chief Executive Officer, Nuclear         Station Sacramento Municipal Utility District cc:                                                                         l Mr. David S. Kaplan, Secretary         Mr. John Bartus and General Counsel         Ms. JoAnne Scott Sacramento Municipal Utility           Federal Energy Regulatory Commission District                     825 North Capitol Street, N. E.
l Mr. G. Carl Andognini Rancho Seco Nuclear Generating Chief Executive Officer, Nuclear Station Sacramento Municipal Utility District l
6201 S Street                         Washington, D.C. 20426             j P. O. Box 15830 Sacramento, California 95813 7homas A. Baxter, Esq.
cc:
Shaw, Pittman, Potts & Trowbridge                                           i 2300 N Street, N.W.                                                         1 Washington, D.C. 20037 Mr. John V. Vinguist Acting Manager, Nuclear Licensing Sacramento Nunicipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, California 95638-9799 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident inspector / Rancho Seco                                             i I
Mr. David S. Kaplan, Secretary Mr. John Bartus and General Counsel Ms. JoAnne Scott Sacramento Municipal Utility Federal Energy Regulatory Commission District 825 North Capitol Street, N. E.
c/o V. S. N. R. C.
6201 S Street Washington, D.C.
14440 Twin Cities Road Herald, California 95638 Regional Administrator, Region V                                             i U.S. Nuclear Regulatory Commission                                           l 1450 Maria Lane, Suite 210                                                   l Walnut Creek, California 94596 Mr. Joseph 0. Ward, Chief                                                     j Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814 Sacramento County                                                             i Board of Supervisors                                                         !
20426 j
827 7th Street, Room 424                                                     !
P. O. Box 15830 Sacramento, California 95813 7homas A. Baxter, Esq.
Sacramento, California 95814                                                 I Ms. Helen Hubbard P. O. Box 63 Sunol, California 94586 l
Shaw, Pittman, Potts & Trowbridge i
2300 N Street, N.W.
1 Washington, D.C.
20037 Mr. John V. Vinguist Acting Manager, Nuclear Licensing Sacramento Nunicipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, California 95638-9799 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident inspector / Rancho Seco i
I c/o V. S. N. R. C.
14440 Twin Cities Road Herald, California 95638 Regional Administrator, Region V i
U.S. Nuclear Regulatory Commission l
1450 Maria Lane, Suite 210 l
Walnut Creek, California 94596 Mr. Joseph 0. Ward, Chief j
Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814 Sacramento County i
Board of Supervisors 827 7th Street, Room 424 I
Sacramento, California 95814 Ms. Helen Hubbard P. O. Box 63 Sunol, California 94586 l
_ _ _ _ _ - - _}}
_ _ _ _ _ - - _}}

Latest revision as of 05:13, 3 December 2024

Revised Tech Spec Page 3-21,adding Paragraph 3.3.5
ML20235J528
Person / Time
Site: Rancho Seco
Issue date: 07/08/1987
From:
SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20235J517 List:
References
NUDOCS 8707150623
Download: ML20235J528 (2)


Text

k RANCHO SECO UNIT 1 Vs TECHNICAL SPECIFICATIONS Limiting conditions fur Operation 3.3.3 Prior to initiating maintenan;e on any of the component (s), the duplicate (redundant) components shall be verified operable by

'A checking that the surveillance test for the component (s) has been W

successfully completed and will remain in effect for the. duration of the maintenance period. Inservice testing per specification 4.2.2.1 shall not be performed on arty component (s) whose duplicate (redundant) component (s) has (have) been declared inoperable or is out of service for any reason. -

3.3.4 During power operation, hot standby, hot shutdown or startup conditions, the primary coolant system pressure isolation valves shall be functional as follows:

1.

All pressure isolation valves If sted in Table 3.3-1 shall oe functional as a pressure isolation device, except as specified in 3.3.4.2.

Valve leakage shall not exceed the amounts indicated.

2.

In the event that integrity of any pressure isolation valve specified in Table 3.3-1 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. a) 3.

If Specifications 3.3.4.1 and 3.3.4.2 cannot be met, a shutdown shall be initiated, the reactor shall not rmain critical and shall be brought to a cold shutdown concition within an

' additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.3.5 Should the redundant equipment or system as specified ir Section 3.3.3 become inoperable, as defined in Specification 1.3, the reactor shall not remain critical and shall be placed in cold shutdown condition l

within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, j

g Bases The requirements of Specification 3.3.1 assure that, before the reactor can be made critical, adequate safety features are operable. Two high pressure injection pumps and two decay heat removal pumps are specified. However, only one of each is necessary to supply emergency coolant to the reactor in the event of a loss-of-coolant accident. Both core flooding tanks are required as a single core flood tank has insufficient inventory to reflood the core.(1)

The borated water storage tank is used for two purposes:

A.

As a supply of borated water for accident conditions.

ru o$$

8.

As a supply of borated water {Jcr floocing the fuel transfer canal during refueling operationd2 R8' 8

So 390,000 gallons of borated water are supplied for emergency core cooling and Reactor Building spray in the event of a loss-of-core coolant accident. This Ou g

amount fulfills requirements for voergency core cooling. The boraped water

$0 storage tank minimum volume of 390,000 gallons is based on refueling volume n<

re qui rements. Heaters maintain the borated water supply at a temperature to E

prevent freezing. The boron concentration is set at the amount of boron Rg required to maintain the core 1 percent sIJberitical at 70*F without any con n.

control rods in the core. This concentration is 1585 ppm boron while tne minimum value specified in.the tanks is 1,800 ppm boron.

l

.g (a)

Motor operaten valves shall be placed in the closed position and power supplies deenergized.

Amendment No. 4, Of#Wf #f#/

3-21 9/#/M, 67, M, Revised 7/8/87

f,.

l l

l Mr. G. Carl Andognini Rancho Seco Nuclear Generating Chief Executive Officer, Nuclear Station Sacramento Municipal Utility District l

cc:

Mr. David S. Kaplan, Secretary Mr. John Bartus and General Counsel Ms. JoAnne Scott Sacramento Municipal Utility Federal Energy Regulatory Commission District 825 North Capitol Street, N. E.

6201 S Street Washington, D.C.

20426 j

P. O. Box 15830 Sacramento, California 95813 7homas A. Baxter, Esq.

Shaw, Pittman, Potts & Trowbridge i

2300 N Street, N.W.

1 Washington, D.C.

20037 Mr. John V. Vinguist Acting Manager, Nuclear Licensing Sacramento Nunicipal Utility District Rancho Seco Nuclear Generating Station 14440 Twin Cities Road Herald, California 95638-9799 Mr. Robert B. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident inspector / Rancho Seco i

I c/o V. S. N. R. C.

14440 Twin Cities Road Herald, California 95638 Regional Administrator, Region V i

U.S. Nuclear Regulatory Commission l

1450 Maria Lane, Suite 210 l

Walnut Creek, California 94596 Mr. Joseph 0. Ward, Chief j

Radiological Health Branch State Department of Health Services 714 P Street, Office Building #8 Sacramento, California 95814 Sacramento County i

Board of Supervisors 827 7th Street, Room 424 I

Sacramento, California 95814 Ms. Helen Hubbard P. O. Box 63 Sunol, California 94586 l

_ _ _ _ _ - - _