ML20078F557

Proposed Tech Specs Re Having Both Containment Airlock Doors Open Concurrently W/Fuel Handling Accident,To Support Proposed LCO 3.9.3,containment Penetrations

ML20078F557
Person / Time
Site:	San Onofre
Issue date:	01/30/1995
From:	SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20078F543	List: ML20078F541 ML20078F557 ML20078F576
References
NUDOCS 9502020155
Download: ML20078F557 (6)

Text

e 1 REFUELING OPERATIONS 3/4.9.4 CONTAINMENT BUILDING PENETRATIONS LIMITING CONDITION FOR OPERATION 3.9.4 The containment building penetrations shall be in the following status:

a. The equipment door closed and held in place by a minimum of four bolts,

b. A minimum of one door in each airlock is closed, and*

c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere shall be either:

1. Closed by an isolation valve, blind flange, or manual valve, or

2. Be capable of being closed by an OPERABLE automatic containment purge valve.

APPLICABILITY: During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or movement of irradiated fuel in the containment building.

SURVEILLANCE RE0VIREMENTS 4.9.4 Each of the above required containment building penetrations shall be determined to be either in its closed / isolated condition or capable of being closed by an OPERABLE automatic containment purge valve within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of and at least once per 7 days during CORE ALTERATIONS or movement of irradiated fuel in the containment building by:

• Both doors of the containment personnel airlock may be open provided:

a. one personnel airlock door is OPERABLE, and bl. the plant is in MODE 6 with 23 feet of water above the fuel in the reactor vessel. or b2. defueled configuration with fuel in containment (ie., fuel in refueling machine or upender).

SAN ON0FRE-UNIT 2 3/4 9-4 9502020155 950130 PDR ADOCK 05000361 P PDR

.-4_

I f 1

.a. Verifying the penetrations are in their closed / isolated condition, or

b. Testing the containment purge valves per_the applicable portions of Specification 4.6.3.2.

i 1

5 i

l

)

{

i b

i h

h

- (,

SAN ON0FRE-UNIT 2 3/4 9-4a

l

- Containment Penetrations Bases (addition; from PCN 299)

Operability of the containment airlock door requires that the door is capable of being closed; that the door is unblocked and no cables or hoses-are being run through the airlock; and that a-designated individual is continuously available to close the airlock door. This individual.must be  ;

stationed at the outer airlock door.

l

.1 1

l l

l 4

I d

l l

e i

l i

V w g .e, - , - - - -,

g TABLE 3.3-1 ..

REACTOR PROTECTIVE INSTRUMENTATION MINIMUM TOTAL NO. CHANNELS CHANNELS APP ICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MOD ES ACTION

1. Manual Reactor Trip 2 sets of 2 1 set of 2 2 sets of 2 1, 2 .

1 2 sets of 2 1 set of 2 2 sets of 2 3*, 4*, 5* 7A

2. Linear Power Level - High 4 2 3 1, 2 .2#,3#

3. Logarithmic Power Level - High

a. Startup and Operating 4 2(a)(d) 3 1, 2 2#,3#

4 2 3 3 * , 4* , 5* 7A!

b. Shutdown 4 0 233 3,4,5 4

4. Pressurizer Pressure - High 4 2 3 1, 2 2#,3#

5. Pressurizer Pressure - Low 4 2(b) 3 1, 2 2#,3#

6. Containment Pressure - High 4 2 3 1, 2 2#,3#

7. Steam Generator Pressure - Low 4/SG 2/SG 3/SG 1, 2 2#,3#

8. Steam Generator Level - Low 4/SG 2/SG 3/SG 1, 2 2#,3#

9. Local Power Density - High 4 2(c)(d)(e) 3 1, 2 2#,3#

10. DNBR - Low 4 2(c)(d)(e) 3 1, 2 2#,3#

11. Steam Generator Level - High 4/SG 2/SG 3/SG 1, 2 2#,3#'

12. Reactor Protection System Logic 4 2 3 1, 2 2#,3#

3*, 4*, 5* 7A

13. Reactor Trip Breakers 4 2(f) 4 1, 2 5 3*, 4*, 5* 7A

14. Core Protection Calculators 4 2(c)(d)(e) 3 .1, 2 2#,3#,7

15. CEA Calculators 2 1 2(e) 1, 2 6, 7

16. Reactor Coolant Flow - Low 4/SG 2/SG 3/SG 1, 2 2#,3#

17. Seismic - High 4 2 3 1, 2 2#,3#

18. Loss of Load 4 2 3 1(g) 2#,3#.

_ _ _ _ - _ _ - _ _ _ _ _ _ _ - _ _ _ _ - _ _ - - _ _ _ _ - - - - . . - - _ - - - _ _ - _ _ _ - _ . . . . ~. .- _. .._ _ _- -- .. -. _ .-

. . , ...+.-.s e. s. u. -- . .u - a na .e.,n~ ..~.....n-.. - .. .a - . . _ a n. ,. . . . ~ , . . . ~ , . - .

1 TABLE 3.3-1 (Continued) i TABLE NOTATION  !

• With the protective system trip breakers in the closed position, the CEA i drive system capable of CEA withdrawal, and fuel in the reactor vessel. i

• • Thess6srceirarige:Eneutiron3f1 EKnoni torsi ma9? biTGsedli n? Modes [3,Wsand ? SIM th j thelreactor{tripicirdsitibrskersiopeniordthe?C5ntrol(Element Ass 6mbig(CEA)f ' * ~

i DriMyste,m nggcapablegf(CEA(withdrawali , ,

1. The provisions of Specification 3.0.4 are not applicable.

(a) Trip may be manually bypassed above 10-*% of RATED THERMAL POWER; bypass  !

shall be automatically removed when THERMAL POWER is less than or equal to .

10-'% of RATED THERMAL POWER. i i

(b) Trip may be manually bypassed below 400 psia; bypass shall be  !

automatically removed whenever pressurizer pressure is greater than or i equal to 400 psia. I (c) Trip may be manually bypassed below 10-'% of RATED THERMAL POWER: bypass shall be automatically removed when THERMAL POWER is greater than or i equal to 10-'% of RATED THERMAL POWER. During testing pursuant to l Special Test Exception 3.10.2 or 3.10.3, trip may be manually bypassed j below 5% of RATED THERMAL POWER; bypass shall be automatically removed when THERMAL POWER is greater than or equal to 5% of RATED THERMAL POWER.

(d) Trip may be bypassed during testing pursuant to Special Test i Exception 3.10.3.-

l (e) See Special Test Exception 3.10.2.  !

I (f) Each channel shall be comprised of two trip breakers; actual trip logic I shall be one-out-of-two taken twice. 3 (g) Trip may be bypassed below 55% RATED THERMAL POWER.  ;

ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by _'

the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in  ;

at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the  ;

protective system trip breakers, j t

ACTION 2 - With the number of channels OPERABLE one less than the Total i Number of Channels, STARTUP and/or POWER OPERATION may continue  !

provided the inoperable channel is placed in the bypassed or i

tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. If the inoperable channel is bypassed, the desirability of maintaining this channel in the bypassed condition shall be reviewed in accordance with  !

Specification 6.5.1.6e. The channel shall be returned to '

OPERABLE status no later than during the next COLD SHUTDOWN. +

SAN ONOFRE - UNIT 2 3/4 3-4 AMENDMENT NO.

l

TABLE 3.3-1 (Continued)

TABLE NOTATION

2. Pressurizer Pressure - Pressurizer Pressure - High High Local Power Density - High DNBR - Low

3. Containment Pressure - Containment Pressure - High (RPS)

High Containment Pressure - High (ESF)

4. Steam Generator Steam Generator Pressure - Low Pressure - Low Steam Generator AP 1 and 2 (EFAS 1 and 2)

5. Steam Generator Level Steam Generator Level - Low Steam Generator Level - High Steam Generator AP (EFAS)

6. Core Protection Local Power Density - High Calculator DNBR - Low STARTUP and/or POWER OPERATION may continue until the performance of the next required CHANNEL FUNCTIONAL TEST. Subsequent STARTUP and/or POWER OPERATION may continue if one channel is restored to OPERABLE status and the provisions of ACTION 2 are satisfied.

ACTION 4 - With the number of channels OPERABLE one or?morelless than required by the Minimum Channels OPERABLE requiremeritfimmediatelycsuspend all op'erations involving positive reactivity changesfand withini4 hours . and ionceT perL 12: hours 4hereaf.ter perfo rm ' shutdown margi n v e ri f i ca ti on. Ji n - a cco rd anc e wi th Speci fi cati onT441.1.1. lli f;Thf' i s

~

greaterrthan1200*F or Specification"4.1.1.2^

i_f i g isiless,thanforceqyalito 20.0aF.

ACTION 5 - With the num er of channels OPERABLE one less than required by the Minimum .hannels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 6 - a. With one CEAC ino)erable, operation may continue for up to 7 days provided t1at at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, each  !

CEA is verified to be within 7 inches (indicated position) of all other CEA's in its group. After 7 days, operation may continue provided that Action 6.b is met.* If the exemption to Specification 3.0.4 is used, Action 6.b must be met.

b. With both CEACs inoperable, operation may continue provided that:*

i

1. Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> the DNBR margin required by I Specification 3.2.4.b (COLSS in service) or i Specification 3.2.4.d (COLSS out of service) is  !

satisfied. '

• Note: Requirements for CEA position indication given in Technical Speci fication 3.1.3.2.

SAN ONOFRE-UNIT 2 3/4 3-6 AMENDMENT NO. j