Text

Attachment 1, Memo, Correction to License Authority Files
	ML050940200
Person / Time
Site:	Farley
Issue date:	03/29/2005
From:	Sean Peters; NRC/NRR/DLPM/LPD2
To:	Harris J; NRC/OCIO
	Peters S, NRR/DLPM, 415-1842
Shared Package
ML050890364	List: ML050870502; ML050940197; ML050940200;
References
	TAC MC3231, TAC MC3232
	Download: ML050940200 (18)
	v • d • e

)-0 0

40 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 29, 1999 Mr. D. N. Morey Vice President - Farley Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -ISSUANCE OF AMENDMENTS RE: STEAM GENERATOR REPLACEMENTS (TAC NOS. MA4393 and MA4394)

Dear Mr. Morey:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 147 to Facility Operating License No. NPF-2 and Amendment No. 138 to Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2. The amendments change the Unit 1 and Unit 2 Improved Technical Specifications (ITS) in response to your application of December 1, 1998, as supplemented by your letters of April 21, July 19, October 18, and November 11, 1999. The amendments revise the lTS to address changes associated with replacing the current Westinghouse Model 51 steam generators with Westinghouse Model 54F steam generators. The Unit 1 ITS set applies after you replace the Unit 1 steam generators in spring 2000 until you replace the Unit 2 steam generators in spring 2001. The Unit 2 ITS set applies after you replace both the Unit 1 and the Unit 2 steam generators.

We are also enclosing a copy of our related safety evaluation. We will include a Notice of Issuance in the Commission's biweekly Federal Register Notice.

Sincerely, IV, L. Mark Padovan, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosures:

1. Amendment No. 147 to NPF-2

2. Amendment No. 138 to NPF-8

3. Safety Evaluation cc w/ ends: See next page ATTACHMENT 1

ATTACHMENT TO LICENSE AMENDMENT No. 138 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of Facility Operating License No. NPF-8 with the attached revised pages. The revised pages are Identified by amendment number and contain vertical lines Indicating area of changes. Pages noted with an "*" have changed only due to information rolling over from one page to another.

Remove insert Remove Insert 3.3.1-17 3.3.2-11 3.4.5-2 B 3.4.5-5 B 3.4.5-6 3.4.6-2 B 3.4.6-5 3.4.7-1 3.4.7-2 B 3.4.7-1 B 3.4.7-2 B 3.4.7-4 B 3.4.7-5 3.4.13-1 B3.4.13-2 B 3.4.13-3*

B 3.4.13-4*

3.4.16-1 3.4.16-2 3.4.16-4 B 3.4.16-1 B 3.4.16-2 B 3.4.16-3 B 3.6.1-2 B 3.6.2-2 B 3.6.4-1 B 3.6.5-2 3.3.1-17 3.3.2-11 3.4.5-2 B 3.4.5-5 B 3.4.5-6 3.4.6-2 B 3.4.6-5 3.4.7-1 3.4.7-2 B 3.4.7-1 B 3.4.7-2 B 3.4.7-4 B 3.4.7-5 3.4.13-1 B 3.4.13-2 B 3.4.13-3*

B 3.4.13-4*

3.4.16-1 3.4.16-2 3.4.16-4 B 3.4.16-1 B 3.4.16-2 B 3.4.16-3 B 3.6.1-2 B 3.6.2-2 B 3.6.4-1 B 3.6.5-2 B 3.6.5-3*

B 3.6.6-3 B 3.7.16-1 5.5-5 5.5-6 5.5-7 5.5-8 5.5-9 5.5-10*

5.5-11 5.5-12*

5.5-13*

5.5-1 5.5-15*

5.5-16 5.5-17 5.5-18*

5.5-19 5.5-20 5.5-21 5.5-22 5.5-23 5.5-24 5.5-25 5.6-5 5.6-6 B 3.6.5-3*

B 3.6.6-3 B 3.7.16-1 5.5-5 5.5-6 5.5-7 5.5-8 5.5-9 5.5-10 5.5-11 5.5-12 5.5-13 5.5-14 5.5-15 5.5-16 5.5-17 5.5-18 5.5-19 Delete Delete Delete Delete Delete Delete 5.6-5 5.6-6

RTS Instrumentation 3.3.1 Table 3.3.1-1 (page 4 of 8)

Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

11.

Reactor Coolant Pump (RCP)

Breaker Position

a.

Single Loop 1(g)

I per RCP N

SR 3.3.1.12 NA NA

b.

Two Loops 1(h) 1 per RCP M

SR 3.3.1.12 NA NA

12.

Undervoltage 1()

3 M

SR3.3.1.6 Z264OV 22680V RCPs SR 3.3.1.10

13.

Underfrequency 1(

3 M

SR 3.3.1.6 2 56.9 Hz 57 Hz RCPs SR 3.3.1.10

14.

Steam 11,2 3perSG E

SR3.3.1.1 27.6%

228%

Generator (SG)

SR 3.3.1.7 Water Level -

SR 3.3.1.10 Low Low SR 3.3.1.14 I

(I)

Above the P-7 (Low Power Reactor Trips Block) Interlock.

(g)

Above the P-8 (Power Range Neutron Flux) Interlock.

(h)

Above the P-7 (Low Power Reactor Trips Block) Interlock and below the P-8 (Power Range Neutron Flux) Interlock.

Farley Units 1 and 2 3.3.1-17 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

ESFAS Instrumentation 3.3.2 Table 3.3.2-1 (page 4 of 4)

Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE TRIP FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE SETPOINT

5.

Turbine Trip and Feedwater Isolation

a.

Automatic Actuation Logic and Actuation Relays

b.

SG Water Level -

High High (P-14) 1,2 2 trains 1,2 3perSG H

SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.8 I

SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.9 NA S 82.4%

NA S 82%

c.

Safety Injection

6.

Auxiliary Feedwater Refer to Function 1 (Safety Injection) for all initiation functions and requirements.

a.

Automatic Actuation Logic and Actuation Relays

b.

SG Water Level -

Low Low

c.

Safety Injection 1.2.3 1.2.3 2 trains 3 per SG G

SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.8 D

SR 3.3.2.1 SR 3.3.2.4 SR 3.3.2.7 SR 3.3.2.9 NA 2 27.6%

NA a 28%

Refer to Function I (Safety Injection) for all Initiation functions and requirements.

d.

Undervoltage Reactor Coolant Pump

1,2 3

I SR 3.3.2.5 SR 3.3.2.7 SR 3.3.2.9 2640 volts a 2680 volts

e.

Trip of all Main Fee&dater Pumps

7.

ESFAS Interlocks 2 per pump J

SR 3.3.2.10 NA NA

a.

Automatic Actuation Logic and Actuation Relays

b.

Reactor Trip, P-4 1.2.3 1.2,3 2 trains I per train, 2 trains L

SR 3.3.2.2 SR 3.3.2.3 SR 3.3.2.8 C

SR 3.3.2.6 NA NA NA NA

c.

Pressurizer Pressure, P-11

d.

TM - Low Low, P-12 (Decreasing)

(Increasing) 1.2,3 1,2.3 3

1 per loop K

SR 3.3.2.4 SR 3.32.7 K

SR 3.3.2.4 SR 3.3.2.7 s 2003 psig S 2000 psig 2 542.6-F

543-F S 545.4F S 545'F (g) Applicable to MDAFW pumps only.

Farley Units I and 2 3.3.2-11 Amendment No. 147 (Unit 1)

Amendment No. 138 (Unit 2)

RCS Loops-MODE 3 3.4.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

One required RCS loop C.1 Restore required RCS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not in operation, and loop to operation.

reactor trip breakers closed and Rod Control OR System capable of rod withdrawal.

C.2 De-energize all control 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months rod drive mechanisms (CRDMs).

D. Two required RCS loops b.1 De-energize all CRDMs.

Immediately inoperable.

AND OR D.2 Suspend all operations Immediately No RCS loop in involving a reduction of operation.

RCS boron concentration.

AND D.3 Initiate action to restore Immediately one RCS loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Verify required RCS loops are in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.5.2 Verify steam generator secondary side water levels 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months are 2 30% (narrow range) for required RCS loops.

SR 3.4.5.3 Verify correct breaker alignment and indicated power 7 days are available to the required pump that is not in operation.

I Farley Units 1 and 2 3.4.5-2 Amendment No.147 (Unit 1)

Amendment No.138 (Unit 2)

RCS Loops - MODE 4 3.4.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

One required RHR loop B.1 Be in MODE 5.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable.

AND Two required RCS loops inoperable.

C.

Required RCS or RHR C.1 Suspend all operations Immediately loops inoperable.

involving a reduction of RCS boron concentration.

OR AND No RCS or RHR loop in operation.

C.2 Initiate action to restore Immediately one loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify one RHR or RCS loop is in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.6.2 Verify SG secondary side water levels are 2 75%

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (wide range) for required RCS loops.

SR 3.4.6.3 Verify correct breaker alignment and indicated power 7 days are available to the required pump that is not in operation.

I Farley Units 1 and 2

-3.4.6-2 Amendment No.147 (Unit 1)

Amendment No.138 (Unit 2)

.1 t

RCS Loops-MODE 5, Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 RCS Loops-MODE 5, Loops Filled LCO 3.4.7 One residual heat removal (RHR) loop shall be OPERABLE and in operation, and either.

a.

One additional RHR loop shall be OPERABLE; or

b.

The secondary side water level of at least two steam generators (SGs) shall be 2 75% (wide range).

NOTES---

1.

The RHR pump of the loop in operation may not be in operation for

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period provided:

a.

No operations are permitted that would cause reduction of the RCS boron concentration; and

b.

Core outlet temperature is maintained at least 10F below saturation temperature.

2.

One required RHR loop may be inoperable for

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided that the other RHR loop is OPERABLE and in operation.

3.

No reactor coolant pump shall be started with one or more RCS cold leg temperatures

325*F unless:

a.

The secondary side water temperature of each SG is < 500F above each'of the RCS cold leg temperatures; or

b.

The pressurizer water volume is less than 770 cubic feet (24%

of wide range, cold, pressurizer level indication).

4.

All RHR loops may be removed from operation during planned heatup to MODE 4 when at least one RCS loop is in operation.

5.

The number of operating Reactor Coolant Pumps is limited to one at RCS temperatures < 11 0F with the exception that a second pump may be started for the purpose of maintaining continuous flow while taking the operating pump out of service.

Farley Units 1 and 2 3.4.7-1 Amendment No.147 (Unit 1)

Amendment No.138 (Unit 2)

I

RCS -oops-MODE 5-.

.ooas F.'-=a I,

APPLICABILITY:

MODE 5 with RCS Ccops.fiiEo.

ACTIONS CONDITION REQUIRED ACTION

! COMPLETION TIME A.

One RHR loop I A.1 Initiate action to restore a Immediately inoperable.

i second RHR loop to OPERABLE status.

AND*i jOR Required SGs secondary side water levels not A.2 Initiate action to restore Immediately within limits.

required SG secondary side water levels to within limits.

l B.

Required RHR loops B. 1 Suspend all operations Immediately inoperable.

involving a reduction of RCS boron concentration.

OR i AND l

No RHR loop in operation.

i B.2 Initiate action to restore Immediately one RHR loop to OPERABLE status and operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 Verify one RHR loop is in operation.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.4.7.2 Verify SG secondary side water level is 2 75% (wide 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months range) in required SGs.

l Farley Units 1 and 2 3.4.7-2 Amendment No.147 (Unit 1)

Amendment No.138 (Unit 2)

RCS Specific Activity 3.4.16 3.4 REACTOR COOLANT SYSTEM- (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 APPLICABILITY:

The specific activity of the reactor coolant shall be within limits.

MODES 1 and 2, MODE 3 with RCS average temperature (Tavg) Ž 5000F.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

DOSE EQUIVALENT d

Note-----------

1-131 > 0.5 pCi/gm.

LCO 3.0.4 is not applicable.

A.1 Verify DOSE Once per4 hours EQUIVALENT 1-131 within the acceptable region of Figure 3.4.16-1.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limit.

B.

Gross specific activity of B.1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months the reactor coolant not Tavg < 5000F.

within limit.

I Farley Units 1 and 2 3.4.16-1 Amendment No.147 (Unit 1)

Amendment No.138 (Unit 2)

RCS Specific Activity 3.4.16 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and C. 1 Be in MODE 3 with 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Tavg < 500°F.

Time of Condition A not met.

OR DOSE EQUIVALENT 1-131 in the unacceptable region of Figure 3.4.16-1.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.16.1 Verify reactor coolant gross specific activity 7 days s 100/E pCi/gm.

SR 3.4.16.2 NOTE------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 1-131 14 days specific activity s 0.5 pCi/gm.

AND Between 2 and 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after a THERMAL POWER change of 2 15% RTP within a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period I

Farley Units 1 and 2 3.4.16-2 Amendment No.147 (Unit 1)

Amendment No.138 (Unit 2)

I

RCS Specific Activity 3.4.16 275 250 225 0o -f yE (U',

-r-E CO.-

Ca 0ci 200 175 150 125 100 75 50

.I..

.I.............

I

..........N.............................

~~~~.I.......

....................... I..........Uncepal...........

"-............................. O....

eration..........

Acceptable.

......... nacetal Operatio Operation__

25 0

20 30 40 50 -

60 70 80 90 100 Percent of RATED THERMAL POWER Figure 3.4.16-1 DOSE EQUIVALENT 1-131 Primary Coolant Specific Activity Uimit Versus Percent of RATED THERMAL POWER with the Primary Coolant Specific Activity > 0.5 [tCi/gm DOSE EQUIVALENT 1-131.

I Farley Units I and 2 3.4.16-4 Amendment No.147 (Unit 1)

Amendment No.138 (Unit 2)

June 13, 2003 Mr. J. B. Beasley Vice President - Farley Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 RE: ISSUANCE OF AMENDMENTS (TAC NO. MB8229)

Dear Mr. Beasley:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 151 to Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Unit 2. The amendment consists of changes to the Technical Specifications in response to your application dated March 31, 2003, as supplemented by letter dated April 29, 2003.

The amendment modifies Surveillance Requirement (SR) 3.4.11.1, for Farley, Unit 2 only, by the addition of the following note that states, "Not required to be performed for Unit 2 for the remainder of Operating Cycle 16 for 02B31 MOV800B." In addition, a temporary Technical Specification SR 3.4.11.4 is added to provide compensatory action for this block valve while SR 3.4.11.1 is suspended. Further, this SR requires that power to the Farley, Unit 2, Power Operated Relief Valve Q2B31 MOV8000B be checked at least every 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for the remainder of Operating Cycle 16.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.

Sincerely, IRAI Frank Rinaldi, Project Manager, Section 1 Project Directorate II Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-364

Enclosures:

1. Amendment No. 151 to NPF-8

2. Safety Evaluation cc w/encds: See next page

ATTACHMENT TO LICENSE AMENDMENT NO. 151 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications and associated Bases with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Insert 3.4.11-3 3.4.11-4 B 3.4.11-7 B 3.4.11-8 3.4.11-3 3.4.11-4 B 3.4.11-7 B 3.4.11-8

Pressurizer PORVs 3.4.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F.

More than one block valve F.1 Place associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

PORVs In manual control.

AND F.2 Restore one block valve 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to OPERABLE status.

AND F.3 Restore remaining 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months block valve to OPERABLE status.

G.

Required Action and G.1 Be In MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition F not AND met.

G.2 Be In MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.1

-NOTES

1.

Not required to be met with block valve closed In accordance with the Required Action of Condition B or E.

2.

Not required to be performed prior to entry Into MODE 3.

3.

Not required to be performed for Unit 2 for the remainder of operating cycle 16 for block valve Q2B31 MOV8000B.

Perform a complete cycle of each block valve.

92 days

1 Farley Units 1 and 2 3.4.11-3 Amendment No. 146 (Unit 1)

Amendment No. 151 (Unit 2)

z.

',7 1.

Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.2 NOTE Not required to be performed prior to entry Into MODE 3.

Perform a complete cycle of each PORV during 18 months MODE 3 or 4.

SR 3.4.11.3 Perform a complete cycle of each PORV using the 18 months backup PORV control system.

SR 3.4.11.4 NOTE~

~

Required to be performed only for Unit 2 for the remainder of operating cycle 16.

Check power available to the Unit Two PORV block 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months valve Q2B31MOV8000B.

Farley Units I and 2 3.4.11-4 Amendment No. 146 (Unit 1)

Amendment No. 151 (Unit 2)

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055-OOMi November 30, 1999 Mr. D. N. Morey Vice President - Farley Project Southern Nuclear Operating Company, Inc.

Post Office Box 1295 Birmingham, Alabama 35201-1295

SUBJECT:

JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2-ISSUANCE OF AMENDMENTS RE: CONVERSION TO IMPROVED STANDARD TECHNICAL SPECIFICATIONS (TAC NOS. MA1364 and MA1365)

Dear Mr. Morey:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 146 to Facility Operating License No. NPF-2 and Amendment No. 137 to Facility Operating License No.

NPF-8 for the Joseph M. Farley Nuclear Plant, Units 1 and 2. The amendments change the Unit 1 and Unit 2 Technical Specifications (TS), TS Bases, and Facility Operating Licenses in response to your application of March 12, 1998, as supplemented by your following letters:

April 24, 1998

-August 20, 1998 November 20,1998

-February 3, 1999 February 20, 1999 April 30, 1999 (two letters)

-May 28, 1999

-June 30, 1999

-July 27, 1999

-August 19,1999

-August 30,1999 September 15, 1999 September 23, 1999 The amendments fully convert your Current TS (CTS) to Improved TS (ITS) based on NUREG-1431, Standard Technical Specifications, Westinghouse Plants," Revision 1, of April 1995. The amendments add two new Additional Conditions to Appendix C of the Unit 1 and Unit 2 Facility Operating Licenses. The first new Additional Condition authorizes you to relocate certain CTS requirements to Southern Nuclear Operating Company-controlled documents. The second new condition addresses the schedule for performing new and revised ITS surveillances.

Wo

?-1L AWCLC(

D-

-)3qs

Mr. D. N. Morey November 30, 1999 We have also enclosed a copy of our related safety evaluation. We will include a Notice of Issuance in the Commission's biweekly Federal Register Notice.

Sincerely, Original signed by:

L. iMark Padovan, ProJect Manager, Section 1 Project Directorate 11 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364

Enclosures:

1. Amendment No.1 46to NPF-2

2. Amendment No.1 37o NPF-8

3. Safety Evaluation

4. Notice of Issuance cc w/encls: See next page DISTRIBUTION w/Technical Specifications:

Docket File PUBLIC GHill (4)

MPadovan WBeckner DISTRIBUTION wo/Technical Specifications PD 11-1 R/F ACRS OGC PSkinner, Ril CSchulten RScholl (E-mail SE)

HBerkow DOCUMENT NAME: G.\\PDii-1\\Farley\\Farley ITS amd rev5.wpd *No major changes to SEs.

To receive a copy of this document, Indicate In the box: "C" = Copy with SE but no TS "E" = Copy with enclosures "N" = No copy

. OFFICE PDII-1/PM PDI1-1ILA C

1QMB/BC

/

SPLB/SC

/

SRXB EELB/SC NAME MPadova CHawes.

SE d SEs dcd' SEs dat SE d DATE

1 ID/99 1

'I99 9/10/98 1 7/26/99 5/19, & 7/23/99 28199 EMCB/SC

/ EEIB/SC

/

IOLB/SC

/

IOLB/SC

//

RTSBIBC lPlD41 1 PII-1/SC SE ed SE d

SEd d

SE d

WBeckner h e4 REmch

//899 6/16/99 6/28/99 6/28/99

/

9 11/30199 OFFICIAL RECORD COPY A

I

LTOP System 3.4.12 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Two or more charging A.1

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

pumps capable of Two charging pumps injecting into the may be capable of RCS.

injecting into the RCS during pump swap operation for s 15 minutes.

Initiate action to verify a Immediately maximum of one charging pump is capable of injecting into the RCS.

B.

An accumulator not B.1 Isolate affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolated when the accumulator.

accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

C.

Required Action and C.1 Increase RCS cold leg 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion temperature to > 3250F.

Time of Condition B not OR met.

C.2 Depressurize affected 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months accumulator to less than the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.

Farley Units 1 and 2 3.4.12-2 Amendment No. 146 (Unit 1)

Amendment No. 137 (Unit 2) 4

v t e Letter Sequence Other
TAC:MC3231, (Open) TAC:MC3232, (Open)
Initiation Acceptance... Administration Questions Answers Results Approval... Other: ML050870502, ML050870607, ML050940197, ML050940200
MONTHYEAR2005-03-29 [Table View]

ML050940200

Text

SUBJECT:

Dear Mr. Morey:

Enclosures:

SUBJECT:

Dear Mr. Beasley:

Enclosures:

SUBJECT:

Dear Mr. Morey:

Enclosures:

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