ML20207A015

Amends 153 & 144 to Licenses NPF-10 & NPF-15,respectively, Modifying TSs to Allow Refueling Operation with 20 Ft of Water Level in Refueling Cavity for Many Operating Conditions & at 12 Ft of Water Level for Certain Conditions

ML20207A015
Person / Time
Site:	San Onofre
Issue date:	05/13/1999
From:	Stephen Dembek NRC (Affiliation Not Assigned)
To:
Shared Package
ML20207A019	List: ML20207A015 ML20207A021
References
NUDOCS 9905260086
Download: ML20207A015 (8)

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 30606 4001 SOUTHERN CAllFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CAllFORNIA THE CITY OF ANAHEIM. CAllFORNIA DOCKET NO. 50-361 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.153 License No. NPF-10 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Southern California Edison Company, et al.

(SCE or the licensee), dated May 8,1996, as supplemented by letter dated January 13,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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.

9905260086 990513 PDR ADOCK 05000361 P

PDR

O d 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-10 is hereby amended to read as follows:

(2)

Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.153, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the' Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION s

tephen Dem ek, Chief, Section 2 Project Directorate IV-2 & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance: May 13, 1999

T ATTACHMENT TO LICENSE AMENDMENT NO.153 FACILITY OPERATING LICENSE NO. NPF-10 DOCKET NO. 50-361 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginallines indicating the areas of change.

REMOVE INSERT 3.9-6 3.9-6 3.9-7 3.9-7 3.9-8 3.9-8 3.9-9 3.9-9 3.9-9a n

_ m an mm.

.mn w -o n.+ w

-ws-

SDC and Coolant Circulation-High Water Level 3.9.4 s

3.9 REFUELING OPERATIONS 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level LC0 3.9.4 One SDC loop shall be OPERABLE and in operation.

---

.------..-. NOTE----------------------------

With the upper guide structure removed from the reactor vessel the required SDC loop may be removed from operation for s 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period, provided:

a.

The maximum RCS temperature is maintained s 140'F.

b.

No operations are pemitted that would cause a reduction of the RCS boron concentration.

~

c.

The capability to close the containment )enetrations with direct access to the outside atmospiere within the calculated time to boil is maintained.

d.

The reactor cavity water level is maintained a 20 feet above the top of the reactor pressure vessel flange, or, for core alterations, 2.23 feet above the top of the reactor pressure vessel flange.

...........................-N0TE--.-------------------------

A containment spray pump may be used in place of a low pressure safety injection ) ump in either or both shutdown cooling loops to provide s tutdown cooling flow.

APPLICABILITY:

MODE 6 with the water level a 20 ft above the top of the l

reactor vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

SDC loop requirements A.1 Suspend operations Immediately not met.

involving a reduction in reactor coolant boron concentration.

A!E (continued)

SAN ONOFRE--UNIT 2 3.9-6 Amendment No. 127, 153 l

I

== =:= = =-

SDC and Coolant Circulation-High Water Level 3.9.4 a

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2 Suspend loading Immediately irradiated fuel assemblies in the Core.

M A.3 Initiate action to Immediately satisfy SDC loop requirements.

M A.4 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or penetrations within the providing direct calculated time access from to boil, containment whichever is atmosphere to outside less atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one SDC loop is in operation and I2 hours circulating reactor coolant at a flow rate of a 2200 gpm.

1 I

i SAN ON0FRE--UNIT 2 3.9-7 Amendment No. 127, 153 l

SDC and Coolant Circulation-Low Water Level

,[

3.9.5 o

3.9 REFUEL 1HG OPERATIONS 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level LCO 3.9.5 Two SDC loops shall be OPERABLE, and one SDC loop shall be in operation.

---

NOTE----------------------------

A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling loops to provide shutdown cooling flow.

or One loop of shutdown cooling shall be OPERABLE and operating

{

under the following conditions:

1)

The reactor has been shutdown for at least 6 days.

2)

The water level above the reactor vessel flange is 12 feet or greater.

/

3)

The associated loop of Salt Water Cooling (SWC) is OPERABLE and operating.

4)

The associated Component Cooling Water (CCW) pump and the CCW swing pump are OPERABLE, and the associated CCW loop is OPERABLE and operating.

5)

The Shutdown Cooling system is operating using the containment spray pump, and the associated high pressure safety injection pump and the low pressure safety injection pump are OPERABLE and at ambient temperature, available for injection from the RWST.

6)

The RWST contains the volume of water required to raise the level to 20 feet above the reactor vessel flange.

7)

The associated Emergency Diesel Generator is OPERABLE.

8)

The water temperature of the SDC system is maintained less than 120*F.

APPLICABILITY:

MODE 6 with the water level < 20 ft above the top of reactor l

vessel flange.

SAN ONOFRE--UNIT 2 3.9-8 Amendment No. 127, 153

9 SDC and Coolant Circulation-Low Water Level 3.9.5 w

ACTIO i CONDITION REQUIRED ACTION COMPLETION TIME l

A.

One SDC loop A.1 Initiate action to Imediately inoperable, restore SDC loop to OPERABLE status,.

(Applicabletoinitial conditions of two shutdown Dft cooling loops OPERABLE)

A.2 Initiate actions to Imediately establish a 20 ft of l

water above the top of reactor vessel flange.

B.

One SDC loop operable, B.1 Initiate actions to Imediately less than 20 feet of establish a 20 fee?

water above the of water.

reactor vessel flange.

I and any of the 8 requirements not met (Applicable to initial conditions of one shutdown cooling loop OPERABLE and operating with

)

requirements 1-8)

C.

No SDC loop OPERABLE C.1 Suspend operations Imediately l

or in operation.

involving a reduction in reactor coolant boron concentration.

E i

(continued) 1 SAN ONOFRE--UNIT 2 3.9-9 Amendment No. 127,153

U SDC and Coolant Circulation-Low Water Level l

3.9.5 ACTIONS

' CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2 Initiate action to Immediately l

restore one SDC loop to OPERABLE status and to operation.

Alul C.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or penetrations within the providing direct calculated time access from to boil, containment whichever is atmosphere to outside less atmosphere.

4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify required SDC loops are OPERABLE 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and one SDC loop is in operation and circulating reactor coolant at a flow rate of 2 2200 gpm.

9 SAN ONOFRE--UNIT 2 3.9-9A Amendment No. U7,153

: ~..-- -..- -. -.- - -.. -..- -,.

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p UNITED STATES g

}

NUCLEAR REGULATORY COMMISSION o

WASHINGTON, D.C. 30se640tH SOUTHERN CAllFORNIA EDISON COMPANY SAN DIEGO GAS AND ELECTRIC COMPANY THE CITY OF RIVERSIDE. CALIFORNIA THE CITY OF ANAHEIM. CAllFOBNIA j

DOCKET NO. 50-362 SAN ONOFRE NUCLEAR GENERATING STATION. UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.144 License No. NPF-15 J

1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Southern California Edison Company, et al.

(SCE or tFa licensee) dated May 8,1996, as supplemented by letter dated January 13,1999, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 j

amendment can be conducted without endangering the health and safety of the l

public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; 4

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.

e

• 2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-15 is hereby amended to read as follows:

(2)

Technical Soecifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.144

, are hereby incorporated in the license. Southern California Edison Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of the date of its issuance and shall be implemented within 30 days of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

. 44 N

Step n Dembek, Chief, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: May 13, 1999

Q ATTACHMENT TO LICENSE AMENDMENT NO.144 FACILITY OPERATING LICENSE NO. NPF-15 DOCKET NO. 50-362 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by amendment number and contain marginallines indicating the areas of change.

REMOVE INSERT 3.9-6 3.9-6 3.9-7 3.9-7 3.9-8 3.9-8 3.9-9 3.9-9 3.9-9a s.

_n,7

.~~

I SDC and Coolant Circulation-High Water Level 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Shutdown Cooling (SDC) and Coolant Circulation-High Water Level LC0 3.9.4 One SDC loop shall be OPERABLE and in operation.

---

~~-----------------NOTE----------~~---------

With the upper guide structure removed from the reactor

- vessel the required SDC loop may be removed from operation for s 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> per 8-hour period, provided:

a.

The maximum RCS temperature is maintained s 140*F.

b.

No operations are permitted that would cause a reduction of the RCS boron concentration.

c.

The capability to close the containment penetrations with direct access to the outside atmosphere within the calculated time to boil is maintained.

d.

The reactor cavity water level is maintained a 20 feet above the top of the reactor pressure vessel flange, or, for core alterations, a 23 feet above the top of the reactor pressure vessel flange.

............................-N0TE-.-...------..-.--.--.--..--

i A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling loops to provide shutdown cooling flow.

APPLICABILITY:

MODE 6 with the water level a 20 ft above the top of the l

reactor vessel flange.

ACTIONS i

~~~

CONDITION REQUIRED ACTION COMPLETION TIME A.

SDC loop requirements A.1 Suspend operations Innediately not met.

involving a reduction in reactor coolant boron concentration.

ale (continued)

SAN ONOFRE--UNIT 3 3.9-6 Amendment No. ffi,144 E...~%.?N

-w-.-~,-

%.~

---.4

'-~'~'I'Y~

As-I

o SDC and Coolant Circulation-High. Water Level 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(contice:)

A.2 Suspend loading Immediately irradiated fuel assemblies in the l

core.

M I

A.3 Initiate action to Immediately satisfy SDC loop requirements.

M A.4 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or penetrations within the i

providing direct calculated time access from to boil, containment whichever is atmosphere to outside less atmosphere.

m i

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify one SDC loop is in operation and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> circulating reactor coolant at a flow rate of it 2200 gpm.

4 SAN ON0FRE--UNIT 3 3.9-7 Amendment No. ffi, 144

=

=. =.

SDC and Coolant Circulation-Low Water Level 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Shutdown Cooling (SDC) and Coolant Circulation-Low Water Level LCO 3.9.5 Two SDC loops shall be OPERABLE, and one SDC loop shall be in operation.

....................--------N0TE----------------------------

A containment spray pump may be used in place of a low pressure safety injection pump in either or both shutdown cooling loops to provide shutdown cooling flow.

or

' One loo) of shutdown cooling shall be OPERABLE and operating under tie following conditions:

1)

The reactor has been shutdown for at least 6 days.

2)

The water level above the reactor vessel flange is 12 feet or greater.

3)

The associated loop of Salt Water Cooling (SWC) is OPERABLE and operating.

4)

The associated Component Cooling Water (CCW) pump and the CCW swing pump are OPERABLE, and the associated CCW loop is OPERABLE and operating.

5)

The Shutdown Cooling system is operating using the containment spray pump, and the associated high pressure safety injection pump and the low pressure safety injection pump are OPERABLE and at ambient temperature, available for injection from the RWST.

6)

The RWST contains the volume of water required to raise the level to 20 feet above the reactor vessel flange.

7)

The associated Emergency Diesel Generator is OPERABLE.

8)

The water temperature of the SDC system is maintained less than 120*F.

APPLICABILITY:

MODE 6 with the water level < 20 ft above the top of reactor vessel flange.

SAN ONOFRE.-UNIT 3 3.9-8 Amendment No. ff6, 144

SDC and Coolant Circulation-Low Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One SDC loop A.1 Initiate action to Imediately inoperable.

restore SDC loop to OPERABLE status, t

(Applicable to initial

{

conditions of two shutdown DR cooling loops OPERABLE) 1 A.2 Initiate actions to Imediately establish 2 20 ft of l

water above the top of reactor vessel

~

flange.

B.

One SDC Loop Operable, B.1 Initiate actions to Imediately less than 20 feet of establish 2 20 ft of

)

water above the water reactor vessel flange and any of the 8 requirements not met (Applicable to initial conditions of one shutdown cooling loop OPERABLE and

{

operating with requirements 1-8)

C. No SDC loop OPERABLE C.1 Suspend operations Imediately l

or in operation.

involving a reduction in reactor coolant boron concentration.

AND

-(continued)

SAN ONOFRE--UNIT 3 3.9-9 Amendment No. ff6, 144 t

m.,*4.=e-

.a 4w

,,e.

..-w-

SDC and Coolant Circulation-Lot;s Water Level 3.9.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2 Initiate action to Immediately l

restore one SDC loop to OPERABLE status and to operation.

Atin C.3 Close all containment 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or penetrations within the providing direct calculated time access from to boil, containment whichever is atmosphere to outside less atmosphere.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Verify required SDC loops are OPERABLE 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and one SOC loop is in operation and circulating reactor coolant at a flow rate of a 2200 gpm.

SAN ONOFRE--UNIT 3 3.9-9a Amendment No. ff6,144

. ~.. -_

..... _. _ _ _ _ _