ML20086S653

Forwards Fifth Edition of Integrated Implementation Schedule for ATWS Diverse Emergency Feedwater Actuation Sys, Charging Room Components Venting to HVAC & Removal of Shutdown Cooling Autoclosure Interlock

ML20086S653
Person / Time
Site:	San Onofre
Issue date:	12/26/1991
From:	Rosenblum R SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9201030269
Download: ML20086S653 (10)

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. December 26, 1991 U. S. Nuclear Regulatory Commission Attention Document Control Desk Washington, D. C. 2055S Gentlement

Subject:

Docket Nos, 50-361 and 50-362

- Fifth Edition of the Integrated Impicmentation Schedule (!!S)

. San Onofre Nuclear Generating Station Units 2 and 3

Reference:

LetterfromT.R. Handy (SCE)toDocumentControlDesk(NRC),

dated May 22, 1991; fourth Edition of the Integrated ImplementationSchedule(IIS).

This letter provides, as Loclosures 1 through 3, the Fif th Edition of the Inte y.'ated implementation Schedule (115) for the San Onofre Nuclear Generating Statwn(SONGS), Units 2and3. License Conditions 2.C(26) for Unit 2, and 2.C(27) for Unit 3 requires Southern C6lifornia Edison (SCE) to submit the !!S to the NRC on a semi-annual basis.

These License Conditions require that projects of regulatory origin to be ranked, and their relative potential safety contribution to be determined using the Westinghouse Analytical Ranking Process (WARP) computer code. The projects are then separated into two lists: Schedule A and Schedule B.

Schedule A items have implementation date; required by either Nr,C regulations, orders, or license conditions. Schedule B items are other projects with implementation dates committed to by SCE which would rest lit'in either ja) Plant modifications:

,b) Procedure revisions; i c Changes in facility staffing requirements; -

I d It es perceived by SCE as prospective NRC requirements; Le Major tuks resulting from mandates of aqencies other than the NRC: or (f) Evaluation of major initiated issues not required by either regulation, license conditions, or orders.

In addition, a Schedule C is included listing SCE initiated plant betterment projects.

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ip Enclosure 1 lists by c t theSONGS2ScheduleA,B,andCprojects.

s.s - w-Cnclosure 2 contaIns a u 6ne,similar listing for Unit 3. As required by the License - .

i. Conditions 2ncitscre 3 lists the ongoing evaluations for major issues which havebeenInitiatedforSON">S2and3.

A com arison to the fourth Edition of the 115 (referenced) reveals that the J 1 follocing changes have occurred to the Cycle 6 and Cycle 7 schedules:

Action j$11, .CXfM EChedule Hodificalitn

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[ Completed 2 6 A Anticipated Transients Without SCRAM t (ATWS) Diverse Emergency feedwater ActuationSystem(10CFR60.62) f

!.f Completed 2 5 0 Ch'arging Room Components Venting to k Heating ventilation and air y conditioning (HVAC) (NRC Inspection ul Reports 50-361/8625,50362/86-26)

W t Completed 2 6 B AtmosphericDumpValves(ADV) Upgrades

{s to Allow Easier Valve Operation

{ (lettertoNRC, September 12,1988)

Completed 2 6 B ComponentCoolingWater(CCW)

Hodifications'From Results of SSTI to "le HitigateVoiding(LettertoNRC, j July 30, 1990)

'2 Completed 2 6 B Second Refueling Water Level Indicator a (GL8817andLettertoNRC,

,}, October 31,1990) e

! Cempleted 2 6 B Removal of the Shutdown Cooling

'[ Autoclosure Interlock (ACl) (GL 88-17 p and Letter to NRC, October 31,1990) i '

Completed 2 6 B Diesel Generator and Class 1E Battery

• Room Hi/Lo Temperature Alarm Hedifications from Results of SSFI (LetterstoNRC

Harch 14,1991), April 24,1990, and Completed 2 6 B Control Room Human factors Modifications (LER 2-89-014) ,

? Completed 2 6 B Emergency)pesponseDataSystem (GL89-15 4

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. Final testing and turnover will be completeo when the NRC computer

equipment is set up and a designated FTS-2000 phone line provided.

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Mdilitation h Completed 2 6 B Replace Crosby Relief Valves on Safety t.. -

..letter Injection to J.Tanks (11. B. Ray,date SCE, d l

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Hay 16,1991)

I l( Completed 2 6 C SnubberReduction(OngoingProgram)

Completed 2 6 C Auxiliary Feedwater Check Valve Relocation Schedule 2 7 C Turbine Building Sump Monitor low Flow

- Change Alarms I fl Completed 2 6 C Containment Purge System Blind Flange l Installation Schedule 2 7 C Secondary Chemistry Alarms l Change

) Schedule 2 7 C Auxiliary icedwater and Safety

Change' Injection Pipe Vent Relocation

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". Completed 2 6 C Hodify Diesel / Generator Turbo:harger

, Oil Filters Completed 2 6 C Install en Outage Control Center i Schedule 2 7 C PASS Skid

• Enhancements Change Completed 2 7 B Add Redundant Power Supply to the Non IEUPS(LER 2-90-016)

Completed 3 5 B Spent Fuel Pool Reracking i

Completed 3 6 B Charg n; Room Components Venting to HVAC NRC Ins 50-361/80-25,pection 50362/86-26) Reports Schedule 3 L B Add Redundant Power Supply to the Change Non-1EUPS(LER 2-90016)

Schedule 3 7 8 Steam Generator Overfill Protection Change System (SGOPS) (GL 89-19 and

. Letter to NRC, October 22. 1990')

Con.pleted 3 6 C Spent fuel Pool Purification Cross Tie

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' Implementatien deferred to Cycle 7 in SCE letter to the HRC dated July 9,1991 pending NRC Evaluation of the safety benefit of SGOPS in CE Plants.

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' Document Control Desk 1 Modificatin fi Action pjlii Cyllt Ochedule _

i~.. Replace seismic ~1nstrutxntation 2 7 C E Added

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2/3 7 B Control Room fluman factors

$ 'Added Modifier tions (Letter from F. Handy to NRC, Jut 18,1990) l, Spill Prevention Control and B

Added 2/3 7 l CountermeasuresHodifications(Letter j from H. Newton, SCE, to A. L. Coe,

'. California Water Quality Board, November 14,1991)

B Auxiliary Feedwater Steam Driven Puy kMed 2/3 7

'- CheckValve(t.ER 291-014)

The Westinghouse Analytical Ranking Process (WARP) program ranks the safety

, The WARP program was not aed because the significance of each modification. rankings are only required to determine the p could not be completed in the next refueling outage.

Approximately 60% of resources for the Unit 2 and the Unit 3 Cycle 7 refueling outages will be allocated to regulatory projects.

If you have any questions en the fifth Ed' tion of the San Onofre Units 2 and 3 115, please 13t me know.

Very truly you s I

R. H. Rosenolum lionager of Nuclear Regulatorj Affairs janicks/ntc.1tts/1156 Enclosure cc .1. Regional Administrator, NRC Region V

• B. Martin,l, C. W. Caldwel NRC Senior Resident inspector, San Onofre Units 1, 2 & 3 bcci (Seeattachedsheet) 1

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ENCtOSURE 1

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Senedule A*

There are no Schedule A items at this time.

Schedule B" There are no Schedule B items at this time.

, Schedule C*"

There are no Schedule C items at this tin-'.

el Cycle 7 SCHEDULE A*

Station Blachut Hodification (10 CFR 50.63)

(ContingentonNRCissuanceofSER)

SCHEDULE B** .

Control Room Annunciator Rearrangement Hodifications i

Compone(NUREG0700)#

nt Cooling Water (CCW) Seismic Hakeup from Results of S$f! to Mitigate Voiding (Letter to NRC, July 30,1990)

Steam Generator Overfill Protection 5 stem (SGOPS) (GL 89-19 and

',' Letter to NRC, October 22, 1990 ,

HodifyPPSTestSwitches(LEt,.1-89007)

ModifyLER290012)

(Overspeed Protection on Auxiliary feedwater Steam Powered Pumps Control Room Human Factors Mr.,difications (Letter from F. Nandy to NRC, June 18,1990)

Spill Prevention Control and Countermeasures Hodifications (Letter from H. Newton, SCE, to A. L. Coe, California Regional Water Quality Board, November 14,1991)

Auxiliary Feedwater Steam Driven Pump Check Valve (LER 291-014)

SCHEDULE C*"

Ladders and Plationns (Ongoing progrtu)+

Cross Cw.ct Shutdown Cooling and Containment Sprey '

Install Removable Digital Polar Crane Controls Install Removable Refuelinn Machine Controls Re lace Refueling Cavity Sials+ '

Re lace Seismic Instrumentation LPSI Pump Upgrades Direct Dilution of CVCS Make-up Water AddExternalTestPointstoPlantProtectionSystem(PPS) Panel Replace CFHS Computer

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i Snubber Reduction (Ongoing program)

Add Breathing Air and Communication to Steam Generator Platforms d Upgrade Blowdown Processing System and Orains+

rl( Upgrade Fire Upgrade Secur. Protection Computer ity Computer i Hodify 90-minute Emergency Control Room Lighting

Replace $$ LP Turbine Bellows

Install Contaminsted Work E1;losure Building i Turbine Building Sump M'snitor low Flow Alarms 4 Secondary Chemistry Alarms h' Auxiliary feedwater and Safety injection Pipe Vent Relocation -

7, . PASS Skid Enhancements n

NRC Rule or Order y **

Regulatory Commitment (other thLn Schedule A) f( Plant Betterment '

ii + This is a Non-Outage Related Modification

, f To be identified from evaluations based on results of the Detailed Control 2 Room Design Review per NUREG-0700 (evaluation listed in Enclosure 3).

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l SONGS 3 Ils Cycle 6 Schedule A*

ATWSDiverseEmergencyfeedwaterActuationSystem(10CfR50.62)f Schedule B**

ADV Upgrades to Allow Easier Valve Operation (letter to NRC, September 12,1988)

CCW Hodifications From Results of SSFI,to Hitigate voiding (Lettar to NRC, Jul 30,1990)

Second Refueling ('ater Level Indicator (GL 88-17 and Letter to NRC, October 31,1990)

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Removal of the Shutdown Cooling Autoclosure Interlock (ACI)

(GLB8-17andLettertoNRC, October 31,1990)

Diesel Generator and Class 1E Battery Room Hi/Lo Temperature Alarm HodificationsFromResultsofSSFI(letterstoNRC, April 24,1990, and March 14, 1991 Control Room Human factors Hodifications)(LER 2-89-014)

Emergency Response Data System Tanks (GL 89-15) (H. B. Ray, SCE, letter to J. B.

Replace Crosby Relief Valves on SIS Hartin, NRC, dated flay 16,1991)

Add Redundant Power Supply to the Non-1E UPS (tsR 2-90-016) liRC Rule or Order RegulatoryCommitment(otherthanScheduleA)

• • • Plant Betterment ,

+ This is a Non-Outage Related Modification i To be installed at Unit 3 during the Cycle 6 outage, which is s:tr .uled start on January 18, 1992, but no later than January 31, 1992. (Letter to the NRC, November 20,1991) 9

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(f SONGS 3IIS(Cont'd)

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Cycle 6(Cont'd) -

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' SnubberReduction(OngoingProgram)lowAlarm.

Turbine Building Sump Honitor Low F

l. Sewage Plant Upgrade +

Containment Purge System Blind Flange Installation t Auxiliary Feedwater Check Valve Relocation

Holsture Selarator Reheater Modification

' A. Condensate  : low Distribution Hodification 4 Safety Injection Pipe Vent Relocation

'e Hodify Diesel /Generetor Turbocharger Lube Oil Filters

[,. Replace SS LP Turkine Bellows f

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• NRC Rule or Order g

• • RegulatoryCommitment(otherthanScheduleA)

"* Plant Betterment l, + This is a Non Outage Relcted Modification

-i # To be installed at Unit 3 during the Cycle 6 refueling outage. Thq l outage is scheduled to start on Januaiy 18, 1992, but no later thsn January 31,1991 (Letter to the NRC, November 20,1991)

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4 SONGS 3 IIS (Cont'd)

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Schedule A*

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4 Station Blackout (10 CFR 50.03) (Contingent on NRC issut.nce of SkR) l4; Schedule B**

Control Room Annunciator Rearrangement Modifications i (NUREG0700 #

Component Cooling) Water (CCW) Seismic Makeup From Results of 9 SSFItoMitigateVoiding(LettertoNRC, July 30,1990)

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Modify PPS Test Switches (LER 3-89-007) b.1 ModifyLER290-012)

(Overspeed Protection on Auxiliary feedwater Steam Powered Pumps

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Add Redundant Power Supply to the Non IE UPS (LER 2-90016) i; Steam Generator Overfill Protection System (SGOPS) (GL. 89-19 and Letter

[;, toNRC, October 22,*.990)

Control Room Human Factors Modifications (Letter from F. Handy to'NRC, t

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, June 18, 1990)

" SpillPreventionControlandCountermeasuresModifications(Letterfrom H. Newton, SCE, to A. L. Coe, California Water Quality Beard,

( November 14,1991) h Auxiliary Feedwater Steam Driven Pump Check Valve (LER 2-91-014) p Schedule C"*

Ladders and Platforms (Ongoing program)+

e Cross Connect Shutdown Cooling and Containment Spray

4. - Install Removable Olgital Polar Crane Controls Install Removable Refueling Machine Controls

, Replace Refueling Cavity Seals +

, LPSI Pump Upgrades

! Direct Dilution of CVCS Hake-up Water

Add External Test Points to Plant Protection System (PPS) Panel i Replace CFliS Computer SnubberReduction(Ongoingprogram)

Add Breathing Air and Communication to Steam Generato: Platforms Upgrade Blowdown Processing System and Drains +

Upgrade Fire Protection Computer Upgrade Security Computer NRC Rule or Order RegulatoryCommitment(otherthanScheduleA)

Plant Betterment

+ This is a Non-Outage Related Modification '

f To be identified from evaluations based on results of the Detailed Control Room Design Review per NUREG 0700 (evaluation listed in Enclosure 3).

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CNCLOSURL 3 Ongoing O $[uations of Hajor Issues (50NGS"2"In'd'3) ~

GL'88520- --

Individual Plant Examination for Severe Accident'

, . Vulnerabilities, to be completed by 8/29/92.

GL 8910 Safety Related Motor-Operated Yalve Testing and Surveillance, to be completed by 6/28/94 or three refueling outages after

, 12/28/89.

GL 89-13 Service Water System Problems Affecting Safety-Related Equipment, to be completed for Unit 2 and Unit 3 by the end of cycle 6 refueling outages, respectively.

Annunciator Evaluations Based on Results of Detailed Control Room Design Review (NUREG 0700), modifications to be completed .by the end of the Cycle 7 refueling outage for each unit.

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