ML18153B886

Forwards Summary of 890720 Meeting in Atlanta,Ga Re Unit 2 Operational Readiness Assurance Program & Mods to Svc Water Sys for Plants

ML18153B886
Person / Time
Site:	Surry
Issue date:	09/06/1989
From:	Ebneter S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
References
NUDOCS 8909140196
Download: ML18153B886 (46)

Text

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• SEP O 6 1989

'~Virginia Electric and Power Company ATTN:

Mr. W. L. Stewart Senior Vice President - Power 5000 Dominion Boulevard Glen Allen, VA 23060 Gentlemen:

SUBJECT:

MANAGEMENT MEETING

SUMMARY

This letter refers to the Management Meeting held on July 20; 1989, at the Region II Office, Atlanta, Georgia.

The meeting concerned activities authorized for your Surry facility, and involved discussions of the Unit 2 Operational Readiness Assurance Program and modifications to the service water system for both Surry units.

A list of attendees, a meeting summary, and a copy of your handouts are enclosed.

In accordance with 2.790 of the NRC's "Rules of Practice," Part 2, Title 10, Code of Federal Regulations, a copy of this letter and its enclosures will be placed in the NRC Public Document Room.

Should you have any questi~ns concerning this matter, please contatt us.

Enclosures:

1.

List of Attendees

2.

Meeting Summary

3.

H~ndout - Operational Readiness Assurance Program

4.

Handout - Justification for Continued Operation cc w/encls:

W. R. Cartwright Vice President - Nuclear Operations J. P. O'Hanlon Vice President - Nuclear Services R. F. Saunders Manager - Nuclear Licensing M. R. Kansler; Station Manager Commonwealth of Virginia bee w/encls:

NRC Resident Inspector Document Control Desk RII:DRP tu-,-~L MLewis 08/26/89 RIJ;Jf~

si(a'~er 08/LS/89 RII~

PFredrickson 08/~ J /89 Sincerely, Original signed by Stewart D. Ebneter Regional Administrator Rij]~

M~kule.

• 08/'$1/89.

ee ENCLOSURE 1 MANAGEMENT MEETING LlST OF ATTENDEES Virginia }lectric and Power Company W. Cartwright, Vice President, Nuclear Operations F. Moore, Vice Presiden~, Power Engineering Services M. Kansler, Station Manager, Surry E. Grecheck, Assistant Station Manager, Surry R. Saunders, Manager, Licensing R. Blount, Superintendent, Technical Services*

B. Stanley, Staff Engineer Nuclear Regulatory Commission - Region II S. Ebneter, Regional Administrator, Region II (RII)

B. Grimes, Acting Deputy Regional Administrator, RII L. Reyes, Director, Division of Reactor Projects (DRP), RII E. Merschoff, Deputy Director, Division of Reactor Safety (DRS), RII M. Sinkule, Branch Chief, DRP, RII P. Fredrickson, Section.Chief, DRP, RII

• W. Holland, Senior R~sident Inspector, DRP, RII P. Taylor, Reactor Inspector, DRS, RII M. Lewis, Project Engineer, DRP, RII S. Shaeffer, Project Engineer, DRP, RII Nuclear Regulatory Commission - Headquarters

• B. Buckley, Senior Project Manager, Nuclear Reactor Regulation

• W. Borchardt, Regional Coordinator, Office of the Executive Director.

for Operations

• Per Telecon

.-.. -~..:_:.,..,.v;

ee ENCLOSURE 2 The NRC's and VEPCO's staffs met on July 20, 1989,' to discuss two separate issues; one being the Surry Unit 2 Operational Readiness Assurance (ORA)

Program, and the other involving modifications to the service water (SW) system for -both Surry units.

The meeting-began with opening re.marks from VEPCO's Vice President-Nutlear Operations, who. stated that the Unit 1 ORA Program was successfully completed with no significant findings.

The Vice President further stated that his staff wished to present the proposed Unit 2's program highlighting some differences from the Unit 1 ORA Program in hopes of receiving NRC's concurrence for the change in scope for Unit 2.

The Plant Manager - Surry made the* formal presentation of the Unit 2 ORA Program using the handout in Enclosure 3.

The presentation began with a summary of the Unit 1 findings resulting from the ORA Program.

The licensee identified 230 startup items, however the Plant Manager reiterated that no safety significant concerns were identified.

The discussions then focused on the Unit 2 walkdown status. The licensee stated that the Unit 2 walkdowns were approximately 40 percent complete, with no safety significant items identified to date.

In addition, startup activities continued in the area of power termination, motor operated valve progr~m, 4160 breakers, instrument air, cable tray covers, and instrument cable replacement.

The Unit 2 proposed walkdown approach and schedule were then discussed.* VEPCO plans to complete the walkdowns of Unit 2 containment before startup and proposed to comp 1 ete the wa 1 kdown of sys terns outside containment by December 31, 1989.

The Regional Administrator asked why the NRC should agree to this change in the Unit 2 ORA program.

VEPCO responded by stating that they gave a good faith effort in looking at Unit 1, and the findings had little significance.

Further, because the walkdowns would be complete by December 31, 1989, the final product would not be compromised.

The Vice President - Nuclear Operations for VEPCO stated that they intended to describe the presented program in a new letter, as their presentation commitments differed from their original July 7, 1989 proposal on Unit 2 walkdowns.

The Regional Administrator concluded this portion of the meeting by stating that the staff was in agreement with the conceptual program, and that the NRC will review the program scope further when received.

The discussion then focused on the licensee's description of a propos~d SW modification.

The purpose of the presentation was two-fold:

1) to inform the NRC of the details of the modification and 2) to provide_ the basis for a planned request for discretionary enforcement to effect the modification.

VEPCO distributed a written Justification for Continued Operation (JCO) at the meeting ( see enclosure 4), which addressed the use of a temporary SW supply line during the proposed modification.

The system figures contained in the JCO

• were used as a focus of the presentation.

Surry's SW supply to the charging pumps lube oil and seal coolers and the three control and relay room air conditioning chiller units is provided by two six-inch fiberglass lines, one for each nuclear unit.

These lines are

ee 2

susceptible to silting and biological fouling, and cleaning by hydrolasing has caused internal erosion in the fiberglass lines.

In addition, because both l~nes*must remain operable during power operation of either unit, cleaning during power operation is prohibited.

VEPCO described the improvements planned for the two SW supply 1*ines, which involves replacing them with larger diameter metallic piping, and adding a third line to allow operating flexibility for periodic cleaning.

VEPCO stated that implementation of the described modification would require that one of the six-inch fiberglass lines be taken out of service in order to make tie-ins for the new system piping.

To effect the tie-ins without a dual unit shutdown, the licensee proposed a series of ste~s which involved the use of a temporary SW supply line dedicated to supply on*e control and relay room chiller SW pump.

The temporary line would not meet seismic or missile protection requirements for safety-related SW piping, and would be limited in use for four 24-hour periods.

VEPCO further described the compensatory-actions which would be put into effect during the periods the temporary line was used, including operator actions and spool piece connections.

VEPCO ~tated it was their intentions to request discretionary enforcement to use the temporary lines during the limited periods.

The NRC expressed c~ncern regarding the construction activity on site during Unit 2 startup.

VEPCO stated that they, are committed to controlling construction activity and to assuring operator access paths to safety-related

. equipment.

The NRC thanked VEPCO for their presentation.

' i, SURRY POWER STATION UNIT 2 OPERATIONAL READINESS ASSURANCE PROGRAM NRC INFORMATIONAL MEETING JUL V 20, 1989

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VIRGINIA POWER NRC MANAGEMENT M. R. KANSLER - STATION MANAGER 7

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AGENDA I. PROGRAM SCOPE & OBJECTIVES II. SYSTEM WALKDOWNS A. UNIT 1 FINDINGS B. UNIT 2 APPROACH & SCHEDULE Ill. ELECTRICAL SEPARATION VERIFICATION

• TESTING A. POWER SUPPL V TESTING B. SAFETY-RELATED PUMP & VALVE POWER VERIFICATION IV. INTEGRATED LOGIC/FUNCTIONAL TESTING V. COMMENTS & CONCLUSIONS

OPERATIONAL READINESS ASSURANCE PR.OGRAM PROGRAM SCOPE PHYSICAL WALKDOWNS OF PIPING/EQUIPMENT USED IN EMERGENCY OPERATING PROCEDURES e -

ELECTRICAL SEPARATION VERIFICATION TESTING FOR VITAL a

EQUIPMENT INTEGRATED LOGIC/FUNCTIONAL TESTING OF SAFEGUARDS EQUIPMENT*

DOCUMENT REVIEWS e

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PROGRAM OBJECTIVES PROVIDE ASSURANCE THAT STATION EQUIPMENT IMPORTANT TO SAFETY IS FULLY OPERATIONAL TO ENSURE EQUIPMENT IS LOCATED IN THE PROPER TRAIN

,1111'"'

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• ' i UNIT 1 WALKDOWN FINDINGS 3341 ITEMS OF NOTE 230 STARTUP ITEMS NO SAFETY SIGNIFICANT CONCERNS IDENTIFIED MINOR DRAWING DISCREPANCIES e -

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UNIT 1 STARTUP WALKDOWN FINDINGS TOTAL STARTUP CATEGORY FINDINGS ITEMS ITEM DESCRIPTIONS e

1) PHYSICAL CONDITIONS 1206 94 RUST, BORIC ACID DEPOSITS, CABLE

. TRAY COVERS, PACKING LEAKS, CRACKED CONCRETE, BENT TUBING, ETC.

2) TAGGING ISSUES 988 11 MISSiNG OR IMPROPER TAGS (IDENTIFICATION)

3) DRAWING DISCREPANCIES 479 5

INSTANCES OF MINOR EQUIPMENT NOT ON DRAWING AND CONVERSE

4) VENTILATION 554 6

BENT MATERIAL, BROKEN BOOT, DIRTY FIL TEAS, INOPERABLE DAMPERS, MISSING ACCESS COVERS, UNSEAL-ABLE BOOT JOINTS, ETC.

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5) MATERIAL 10 10 IMPROPER GASKETS IN CC SYSTEM, MISSING INSULATION, NON-QUA~IFIED

• PRESSURE GAUGES, ETC~

6) SEISMIC MOUNTING 56 56 MISSING SUPPORTS, SPRING CANS, AND BOLTS, ETC.

7) HOUSEKEEPING & MISC.

48 48 OIL ON FLOOR, DEBRIS, TAPE ON FITTINGS, ETC.

UNIT 2 WALKDOWN STATUS APPROXIMATEL V 40°/o COMPLETE 286 ITEMS OF NOTE 198 ITEMS EVALUATED 26 STARTUP ITl:MS NO SAFETY SIGNIFICANT ITEMS

• VERIFIED VALVES LOCATED IN CORRECT TRAIN

• VERIFICATION OF PHYSICAL CONFIGURATION AND CONDITIONS ONGOING e

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ONGOING UNIT 2 STARTUP ACTIVITIES POWER TERMINATIONS MOV PROGRAM 4160 BREAKERS

• INSTRUMENT AIR CABLE TRAY COVERS

• INSTRUMENT CABLE REPLACEMENT e -

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, 'i UNIT 2 WALKDOWN APPROACH & SCHEDULE SYSTEMS INSIDE CONTAINMENT-BEFORE STARTUP*

SYSTEMS OUTSIDE CONTAINMENT-12/31/89 PRIORITIZE REMAINING SYSTEMS PERFORMED UNDER STATION PROCEDURE

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e SIGNIFICANT CONCERNS FROM UNIT1 WALKDOWNS WERE e

RESOLVED FOR UNIT 2 PRE-STARTUP MANAGEMENT WALKDOWNS

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• 1 ELECTRICAL SEPARATION VERIFICATION TESTING POWER SUPPLY VERIFICATION (PEAD BUS TESTING}

OBJECTIVE:

• TO ENSURE THAT TRAIN SEPARATION EXISTS FOR SAFEGUARDS EQUIPMENT WITH RESPECT TO THEIR SOURCE OF ELECTRICAL POWER PUMP & VALVE POWER VERIFICATION

• OBJECTIVE:

• TO ENSURE PUMPS AND VALVES FOR EACH TRAIN ARE POWERED FROM THE PROPER ELECTRICAL BUS -..

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UNIT 1 POWER SUPPLY VERIFICATION METHOD:

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COMPLETEL V DEENERGIZED EACH ELECTRICAL BUS (INCLUDED 4160/480V SWITCHGEAR, 480V MCC'S, 120 VAC VITAL BUSES AND 125 VDC PANELS).

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VOLTAGE READING TAKEN PRIOR TO AND AFTER OPENING EACH BREAKER.

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j UNIT 1 POWER SUPPLY VERIFICATION RESULTS:

SEVERAL DRAWING PROBLEMS IDENTIFIED DURING RESEARCH PHASE OF WRITING PROCEDURE.

MOST TEST DISCREPANCIES WERE INSTRUMENTATION MODULES ON THE CORRECT BUS BUT ON DIFFERENT CIRCUITS FROM THOSE SHOWN ON DRAWINGS.

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OTHER DISCREPANCIES INCLUDED COMPONENT LABELING, IMPROPERLY SPARED CIRCUITS AND DUSTY/DIRTY CONDITIONS.

e MOST SIGNIFICANT DISCREPANCY WAS INTERACTION BETWEEN e

. TRAIN 'A~ AND 'B' ICCM SYSTEM, WHICH WAS CORRECTED.

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, UNIT 2 POWER SUPPLY VERIFICATION TESTING PROPOSED METHODS H & J BUS:

WILL NOT BE DEENERGIZED BASIS FOR CHANGE:

PREVIOUS BUS OUTAGES (MAINTENANCE PROCEDURES FOR 9

DEENERGIZING THESE BUSES VALIDATE THE ELECTRICAL ON-LINE e

DIAGRAMS WHICH SHOW TRAIN SEPARATION).

UNIT 1 TEST APPROACH WOULD PLACE UNIT 1 IN TECH SPEC LCO FOR HEAT TRACE AND CROSS-CONNECTED SYSTEMS

• UNIT 2 POWER SUPPLY VERIFICATION TESTING 120 VAC VITAL BUS CIRCUITS:

TEST IDENTICAL TO UNIT 1 FOR EACH CIRCUIT 125 voe CIRCUITS:

WILL NOT DEENERGIZE CIRCUITS.

INITIAL VOLTAGE READINGS TAKEN AT FIELD POINTS. BATTERY THEN PLACED ON EQUALIZE CHARGE. SAME FIELD POINTS RECHECKED TO ENSURE VOLTAGE READINGS MATCH THE NEW HIGHER BUS VOLTAGE.

OPPOSITE TRAIN-DC BUS VOLTAGE AND ESF CIRCUITS WILL BE

• MONITORED TO ENSURE VOLTAGE DOES NOT CHANGE.

BASIS FOR CHANGE:

METHOD STILL VERIFIES TRAIN SEPARATION.

VERY FEW DISCREPANCIES FOUND DURING PERFORMANCE OF UNIT 1 TESTS. SIMILAR DISCREPANCIES IN UNIT 2 WOULD BE IDENTIFIED VIA THIS METHOD.

ALLOWS 4160V SWITCHGEAR TO REMAIN ENERGIZED.

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UNIT 2 POWER SUPPLY VERIFICATION TESTING CONCLUSIONS ON UNIT 2 APPROACH:

UNIT 1 DISCREPANCIES WOULD HAVE BEEN IDENTIFIED VIA THIS METHOD.

PLANT WILL NOT BE PLACED IN AN ABNORMAL CONDITION WITH MINIMUM SAFEGUARDS TO PERFORM TESTING.

WILL NOT REQUIRE SPECIAL PLANT CONDITIONS.

STILL VERIFY LOAD LIST ON VITAL BUSES.

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UNIT 2 POWER SUPPLY VERIFICATION TESTING PROPOSED UNIT 2 TEST SCHEDULE:

• PERFORM TESTING ON 'B' TRAIN THIS OUTAGE.

COMPLETE'RESEARCH PHASE OF 'A' TRAIN THIS OUTAGE AND ACTUAL TESTING AT NEXT REFUELING.

BASIS FOR CHANGE:

UNIT 1 TESTING DISCREPANCIES WERE INSIGNIFICANT AND NOT TRAIN SEPARATION PROBLEMS EXCEPT FOR ICCM. (ICCM PROBLEM.ALREADY CORRECTED ON UNIT 2).

MOST PROBLEMS WITH ELECTRICAL DRAWINGS FOUND DURING TEST DEVELOPMENT. DRAWING DISCREPANCIES FOUND DURING TESTING DEVELOPMENT WILL BE CORRECTED.

SIGNIFICANT PROBLEMS IDENTIFIED ON 'B' TRAIN WILL BE INVESTIGATED ON 'A' TRAIN.

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METHOD:

SAFETY-RELATED PUMP & VALVE POWER SUPPL V VERIFICATION*

• VERIFICATION OF SWITCH, BREAKER, AND COMPOf"ENT ON PROPER TRAIN *.

SAME TEST METHOD USED FOR BOTH UNITS.

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UNIT 1:

e UNIT 1 PUMPS, VALVES, FANS AND DAMPERS TESTED.

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• _COMMON PUMPS, VALVES, FANS AND DAMPERS TESTED.

NO DISCREPANCIES FOUND. OVER 400 COMPONENTS TESTED..

PUMP & VAL VE POWER SUPPL V VERIFICATION UNIT 2:

TEST 60 OF APPROXIMATEL V 300 COMPONENTS BASIS e -

A SAMPLE OF 60 WITH NO DISCREPANCIES GIVES A 95°/o CONFIDENCE LEVEL THAT LESS THAN 5% DISCREPANCIES EXIST.

e THE SAMPLE SIZE WILL BE INCREASED IF DISCREPANCIES ARE ti FOUND.

INTEGRATED LOGIC/FUNCTIONAL TESTING OBJECTIVE:

FUNCTIONALLY TEST THE OPERATION AND SEQUENCING OF SAFEGUARDS EQUIPMENT FOR CLS/LOOP UNDERVOLTAGE (UV) INITIATION (LOOP) TO OCCUR AT DIFFERENT TIMES TO ENSURE PROPER OPERATION. OF LOAD SEQUENCE MODIFICATION.

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UNIT 1.

INTEGRATED LOGIC/FUNCTIONAL TESTING TEST1:

e SIMULTANEOUS INITIATION OF ESF AND UV (COINCIDENT CLS/LOOP).

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• , COMPONENTS OPERATE EXCEPT PUMP BREAKERS IN TEST.

TEST 2:

ESF ACTUATION WITH UV SIGNAL 2-1/2 MINUTES LATER.*

COMPONENTS OPERATE EXCEPT PUMP BREAKERS IN TEST, EDG

. START SIGNAL DEFEATED AND SWAPOVER FROM OFFSITE POWER TO EOG DEFEATED.

e TEST 3:

ESF ACTUATION WITH UV SIGNAL 5 MINUTES LATER.

COMPONEINTS OPERATE INCLUDING PUMPS RUNNING ON RECIRCULATION.

RESISTIVE. LOAD BANK USED TO SIMULATE ACTUAL LOAD IN 1J BUS.

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UNIT 2 INTEGRATED LOGIC/FUNCTIONAL TESTING TEST1 IDENTICAL TO UNIT 1 TEST2 DELETE TEST BASIS INTENT WAS TO VERIFY THAT NEW LOAD SEQUENCING

• MODIFICATION DID NOT AFFECT ORIGINAL START SEQUENCE OF e -

OUTSIDE RECIRCULATION SPRAY PUMP.

e SUCCESSFUL PERFORMANCE OF THIS TEST ON BOTH TRAINS ON e

UNIT 1 VALIDATES NEW DESIGN.

UNIT 2 SEQUENCING MODIFICATION SAME AS UNIT 1.

POST-MODIFICATION TESTING WAS PERFORMED.

TEST3 IDENTICAL TO UNIT 1 EXCEPT LOAD BANK NOT UTILIZED.

VIRGINIA POWER COMMENTS & CONCLUSIONS e -*

INTEGRATED LOGIC/FUNCTIONAL TESTING CONCLUSIONS ON UNIT 2 APPROACH:

DISCREPANCIES FOUND DURING UNIT 1 TESTING WOULD HAVE BEEN IDENTIFIED VIA THE PROPOSED TEST METHOD.

COMPLETE FUNCTIONAL OPERATION OF ESF SYSTEM (SI, HI CLS, HI-HI CLS) WITH AN UNDERVOLTAGE SIGNAL WILL STILL BE VERIFIED.*

EOG LOAD CAPABILITY ALREADY VERIFIED EITHER BY ACTUAL TESTING OR CERTIFICATION.

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ENCLOSURE 4 ee ee JUSTIPICATION roe CONTINUED OPEftATION IUePIY PQWEft l'UTlQN

• UNITS 1 AND Z IJIILIZADOH Of A IENPQB6ftY BEftYICE WAilft IYPPLY LIN~

1.0 BAQKOBAYNP Service water for Surry Unite 1 and 2 11 1upplled from the main circulating water 1y1t1m1 upl1ream of the 98-lnch Isolation varv,, at the condenaera on each

• unit. Service water la provided to various component, by gravity flow dut to the elevatlon difference between th* Intake canal and the dlecharge-canal, and In some cues la uslatld by In-One pump,. Equipment and 1ystem1 cooled by

• service water Include the recJrculatton epray heat 1xchang1r1, component coollng heat exchangers, bearing cooling htat exchangers, control room air condttJonlng chiller eond1ns1rs, charging pump service water aubaystema, and vartoue other h1at loada. S1rvtce water to the charging pump aarvtc. water subsystem* and the control and relay room air condlJlonlng chm,, condenaera Is suppRtd by two alx*lnch flbergfau Rnea, one from each unit. Each of thtH llnea, e*-WS-42*138 (Unit 1) and 8"-WS-161.*131 (Unit 2), 11 buried under the turbine bulktng floor-tnd le efusifltd u nuct,ar ufety related. Th*** Six-inch lines art ustd to provide coonng water to the charging pump lube oil c:oolera and Intermediate seal cootera u well u the thrtt control room air conc:tttlonlng chlller unfta.

The existing six-Inch piping la susc1ptlblt to slltlng and blologlcal fouling, causing reduced auction pressure at tht Inlet of the charging pump 1ervic1 water pumps. Thia buildup of sediment and blologlcal prodUC11 hu required cleaning of the flberglua pipe to maintain adequate pump auction condition,.

The method of cleaning hu_ utilized hlgh pre11ure water (hydrolaalng) which hu caused Internal erosion in tht flb1rglaa1 piping. The existing fibtrglasa piping layout also makes cleaning using this method dlfflcult due to lt1 arrangement and length aa well ** the laek of acctu point1 for cleaning equipment. Following at,ydrolu1r cleaning In early 1987, th, Unit 2 service water pfpt wu replaced when through wall leakage wu detected. Since both llne1 muat remain operable to allow power operation of either unlt and since periodic cleaning la required, the present piping 1yat1m n1td1 lmprovtment.

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ee To resolve the above concern, a Ceslgn Change Package wae prtpartd to replace the six-Inch ftberglas* piping with larger diameter metallic piping.

• A third supply llnt wa1 1110 Included 11 part ot thle design change to provide

• operating flexlblllty through the use* of a spare line durtng periodic cleaning.

• Implementation of the abovt dt1lgn Improvement* will require that one of the exlltlng 1hc*lnch flberglau tin** be taken out of aervice In order to make t1e-in1 for the new 1y1t1m piping. lmpltmtn1atlon also requlr** u11 of tht action 1tat1m1nta allowed by Technical Specifications 3.1,.c and 3.23.C <***

dlscu11lon of Technical Specification, In Section 3.0.

To effect tht tle*Jn of the new 1y1t1m without requiring a two-unit shutdown. It 11 propoeed that a temporary aervlct water aupply nn, be provided to tn1Ur9 a.

. euffleJent supply of 11rvtce water la provided to permit operating two control and relay room aJr conditioning chllltr unite and two charging pump aervlce water pump* at their d111gn condition,. The temporary un, wlll be dec:Hcated to providing full flow to on, control and relay room chiller service water pump. h will be required to UH the temporary llnt 4 time, during operating pertod1 of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 1,11 to effect the necessary tlt*ln1 of the upgraded service water Dnee.

2.0 seQYENCE Qf WQBK The following sequence outllnea the major st1p1 and dlseusaes the contingency m1a1ure1 requlrtd baaed on performing the major portion of the construcUon work during power operation of Unit 1 and/or Unit 2. Prior to any entry Into a 24-h_our action atattmtnt the t1mporary llnt wfll be plaetd In 11rvlc1.

QaouNGffoa St<l,*aoe 4 /.

Remove existing Unit 2 Une from aervlca and enter 24*hour ac:tlon 1tat1mtnt. enmtnate the crou connect llnt In the Unit 2 SW vaJvt pit.

• Thia allow* the two Unit 2 1ourci1 to be 1,otated Independently. Reinstate the Unl1 2 Un* (via 2*SW*11) and exit the l**hour action statement.

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Prefabricate the new common line and the new Untt1 1 and 2 Ines to maximum practical extent.

2-~ Prefabricate th, new Unit 1, Unit 2, and tht new common One eight-Inch pipe section* to be located In the Turbine Bulldlng*

Mechanlcal Equipment Room (TB*MER).

3 y.

Aemove plates, excavate and enlarge existing Unit 2 trench and core drill TB-MER and MER*3 wall1.

During excavation, the existing operating lln1 will ~ protected by backfill and the existing me1al plate. The following contingency measures will be in place during thl1 work.

Flrt watch11 posted u required.

b.

No heavy llftlng outside the ecope of thl1 replacement wtH bl permitted over or near the excavation white It II open.

Uftlng of m1t1rlal required tor thl1 replactmtnt project over the exlltlng flbtrglau lne wtll be minimized.

Install new common tine In trench and tl*ln new a* common llne to the new common Une aource (valve 2-SW-474) at Unit 2 SW vatve pH. Ourtng An* Installation, the existing operating llne will bl protected by backflll and a 1te,1 plat,.

a.

A1mov1 Unit 2 tine from 11rvtce and enter the 24-hour action statement. Install a temporary jumper between new e* common Hn1 and existing Unit 2 flberglaaa Ant In the trench. The Unit 2 a1temat1 flow path now consl1t1 partially of e* copper*nlckel and partlaJty e* flbtrglaSI. Exit the 2**hour action statement.

7.

Install new a* Unit 2 llnt In trench, at the TB-MER wan and tie-in new a* Unit 2 line to the new Unit 2 l*lnch source (&* valve 2-SW*

11) at the Unit 2 SW valve pit. The onglnal I Inch valve 2-sw-11 11 blanked off.

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Remove Unn 2 alternate nn, from service and enter 2'9hour action statement. Make tle*ln through new core dr111 In the TB-MER/MER*

3 wall. Shift flow from the altematt Unit 2 Une to the new Unit 2 nn,. Exit the 2-i-hour action atatement.

• 9.

Replace the temporary Jumper of step 8 with permanent a* Cu-NI piping. Complete ln1tallatlon of new a* common Dnt.

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Remove ihe existing Unit 1 Hnt from M~lce and enter 24-hour action statement. Make the permanent Cu-NI tie-In for the Unit 1 tint In tht TB-MER 3 room. At this point, two new. Independent flow paths txlat. Both originate In the Unit 2 SW vatv, pit from separate sources, travel In 1eparatt Ines and supply the MEFl-3 compon1nt1. Exit tht 2*-hour action atatement.

11.

Install the permanent Unit 1 8*1nch Un* without any Impact on 1y1t1m operation I.e., inatallatlon of the new Unit 1 llne wlll not require u11 of th, 2*-hour action statement.

12.

During the next Unit 2 refuellng outage. 1top-1oQ ecreenw,11 2A and permanently remove the ortglnal 8-inch Unit 2 euppty valve (2*SW*11) and upstream piping In the Unit 2 SW valve pit.

Upon completion of thla work. three new et;ht*lnch c:oppar-nickll supply line, will bl operab~.

The tempcrary Nn1 wlll be fabricated and Installed In accordance with the design crtt,rta given In Section,.o and routed u 1hcwn by the 1k1tch11 given in Section 8.0. The temporary lln, emanates 11 a e Inch llne from a Mrvlce water vAlvt ptt downstream of **rvlce water valve 2-SW-MOV*202A. The S Inch llne runa through the Unit 2 turtlnt building to the wall of tht tur1>1nt building mtchanic&I equipment room (TB-MER), where It 11 reduced In 8111 to -4 inch11.

It then pa1S11 through the TB*MER and 1nt1ra MER*3 where It 11 connected via a removable spool piece to tht suction of control and relay room chiller aervtce water pump 1*VS-P*1C. The temporary nnt wll be lnatalled Pf'k)r IO performing Sttp 1.

.. :*.J*-.-;-.

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Th* 24-hour JCO p*rtod1 for use of the temporary fine occur during the performance Of steps 1, e, a, 10.

The temporary line wtll be temporarily dlsoonnected vta the 1pool plec. In the lint following the completion of 1t1p1 1, e and a. The tamporary llne will be permanen1"., l'lmoved following the completion of atep 1 o.

3.0 EVALUATION OF TECHNICAL SPECIFICATIONS Technloal Sptclflcatlon 3.14.A.5 requires that two **~lea water flow paths to tht charging pump aervfce water subsystem of a unit be operable whenever the reactor 11 cr1tlcal or ACS temperature and pre11ure are above 3SO-F and *so pslg, r11pectlvely. Technical Specification 3.14.C permlta unit operation with only one operable flow path to the charging pump 1ervlce water aubayatam. If two flow paths are not reatored within 24 houra, the reactor mult be placed In a hot 1hutdown co_ndltlon.

Th1r1fort, tht r1qulr1m1nt1 of Ttchnlcal Specifleatlona 3.14 which addreaa the Charging pump aervlce water system can be met If one existing e* supply llne 11 taken out of 11rvlce for leaa than 2, houri.

Interim Technical Speclffcatlon 3.23.C. 1 addreue1 operation of the control and relay room chiller unttt. All three chiller untta must be operable whenever eithtr unit 11 above cold 1hutdown. If* one chlller unit become, Inoperable, it must t>e r11tortd to operable statue within 7 day, or both unftl must be placed In a hot shutdown condition. In addition to thla Interim technical 1ptciflcatlon, system operating re1trictlon1 have been placed on the control and relay room air.

conditioning 1y1tem until permanent 1y1tem lmprov1m1nt1 have been lmplem,nttd. The re1triC1lona Include rtquiring the operation of two chiller un~~. However, uat of only on, 11rvtce water auppty llne 11 not sufficient for operation of two Chllllt"I and two charging pump ltrvlc. water pumpa. A temporary source of service water Is required during tho,, penodl of t1m1 ln which on, permanent service water supply 11 taken out of 11rvlce to make the new ayat1m tie-Ina.

• 5 *

i.

Uae of the temporary e1rvlet w11ter supply lln1 wlll ~ r,atn~id to four 24-hour per1odl. It wfll bt ultd In conJunctlcn with on, permanent service wa1er header to supply the chlllel'I and charging pump nrvlce water pumP9. Becaua1 thl1 condition 11 not expllcltty addreutd In any Technical Specification limiting condition for operation, dfaetetlonary enforcement la requested to permit thia operating configuration.

,.o QEStQN CQNSIQERATIQNS OF THE IEMPPRABY SEBYICE WATER UNE The temporary service water supply In* to the control and relay room chlller 11rvlee ¥tater pump (1*~*P*1C) hu been designed with the followlng 1,ature1:

1.

The Int la fabricated and Installed In accordance with Surry Plant Piping Specification NUS*20 for 1afety-r11ated piping and Plpt Cla11 Design Standard STD*MEN-0004 for CIUI 151 piping.

2.

Claaa 151 (150 t, carbon ltttl) 11 aultable for the dellgn condition

. - of 25 pllg and H*F. Carbon ltltl 11 IUltable for UN with llrvlct water In this appllcatlon.

Corro1lon of carbon steel la not a eoneem since the Ina will be In 11rvlce for short duration,.

3.

Pi~ng matertal1 are apedfltd to ASTM requirements. CMTR1 -are rtqUlrld for all pre11ure retaJnlng component,.

4.

The temporary lln1 11 teated prtor to u11 In accordance with the dtalgn change P8C*IG* r9qulrement1.

5.

The nn, generally meet, the *1afety*relatecr requirements of 11rvlcl water piping, except the llne la not 1el1mlc and la not mlulll protected.

The ratlonala for acctptlng tht temporary llne u operable atthough nonaelamlc and nonml11ne protected 11 baaed on the following considerations and expeaed plant condition* when tht Int 11 In nrvlce.

. e

• 1, ee

1.

The 11rvtc1 water system 11 1 modtrat, energy 1y1t1m, and

• postulated faJlure of the piping 1, lmlted to through wall crack,.

Tht Impact of the floOdlng of 1afetyertlattd componenta due to fallurt of the circulating water piping hu been evaJuattd In tht UFSAA and 1xcttd1 the potential flooded volume of the temporary llnt and lt therefore boundln;.

2.

U11 of the temporary line wlll bt llmlted to four 24*hour time per1od1. Th* probablllty of a seismic,vent during thla period 11 small. Although the lne h11 not been uiamicalty designed, ita faJlur, during I MiamJc event 11 not expected.

5.0 CONSTRUCTION QQNSIPEBAIIQNS OF TEMPQMBY LINE Tht temporary 1Jn1 wlll be utilized during four 24-hour time pertoda.

Conatructlon work requiting the uae of thlt One wtn be completed within 1h11 time period dut to the followlng conaldtratlon1.

1.

All required repraeement tqulpment wfll be on hand prior to starting work.

2.

OttaJltd echtdule1 dtfine the work to be accompRahed during _the 24-hout time perfod1.

3.

Pre-1t1glng r1qulrement1 tn1ur1 that. proper procedure,,

peraonntl and equipment are coordinated to meet or exceed the 11f1bll1h1d 1ehtdule1.

Pre-1taglng includ11 contingency meuurea such u the availabiAty of patch kits for ftberglasa pipe In tht unllk1ly event that a flbergla11 pipe 1u1talnld localized damage during conatructlon.

8.0 QPEMIIQNAL CQNSIPEBADQHS QE JUMPER Continued operatJon of two 1,rv1e, water auppty Rn11 II neceuary when either unit 11 at power. Thi potential Impact of a lou of Nrvlce water to the control

• 7

• l" ee and relay room chlller unite hu been rov:Qwtd. The following action, Will b*

taken to reduce tht vulnerability to a loae of 11rvfce water:

1.

Operator, will be 11algned to control and monitor 1y1t1m operation when the temporary ane 11 In MNfoe. The operators wtll carry out actions u dlrtded by the Control Room.

2.

Prior to 1nt1rtng tht 2'*hour JCO periods, the operating 1hlft1 will.

be brltftd on the Abnormal Procedure, and Emergency Operating Procedure, that would be uNd upon loll of se~lee water.

3.

Anticipated operatlonal concern, are minimized by the short duration (24 houra or lea) of uee of the temporary an,.

4.

Final conntctJon of the temporary eupply an, to the nrvlcl water aystem In MEF1*3 la madt by UM of a flanged 1poolplece. When the temporary tint 11 not In Hrvlce, lt1 laolatlon vatvn wtll be cloHd and the apoolplece wtn be removed.

5.

In the 1xtr1m1ty unHkely event of failure of the temporary ine du*

to a allamlc event, tht line would be Isolated If directed by the control room. Shutdown of both units would proceed it two service water tupply lln11 111 not avaJlab11.

7.0 YNBEVJEWEQ SAFEIY QUESTION QONSIQEBAIIANS Installation of the temporary 11rvfc1 water supply lint to the control and relay room Chiller 11rvlc1 water pump do11 not con1tltut1 an *unrevltwed Safety Question* u defined In 1 o CFR 50.59. Operation of the anemate service water flow path dotl not:

1.

lncreu1 the probability of occurrence or the con1equ1nce1 of an accident or malfunctlon of equipment Important to safety and prtvloully evaluated In the UFSAR.

. 8 *

• ~

Ii ee The probablllty of a IOU of service water to the control and r11ay room chlll*r service water pump 11 not 1lgnlf1cantly lncreutd 1lnce the temporary nn, wm be lnatalled and op1r1ttd In accordance with the compensatory mea1ure1 Identified In the JCO which 1stabn1h11 rt1atlve equivalence tor the temporary nne.

2.

Create a posalblRty for an accident or malfunctlon of a different type than any pmloualy evaluated In the UFSAR.

The p011lblllty for accident, or malfunctlone crtattd by th111 actlvltl11 has been evaluated in the UFSAR. Flooding of aatety*

r1lattd component, due to failure In the olrculatlng water 1yat1m hu b11n evaluated In the UFSAA. The flooding 1ource which would r11ult from a crack In the temporary llne 11 bounded by tht cu~nt 1Y1lultlon.

3.

Fleduct the margin of 11f1ty ** defined In the ball1

• for any Ttchnlcal Spectflcation.

The temporary nn, will be u1ed only for 1hot1 periods of time (l1s1 than 2, houra).

Operation ot the temporary llne under the conditions imposed will provide 1ufflclent 11rvlc1 water flow to meet the design bull requirement, for two unit operation.

Con1tructlon of the temporary llne

• wlll b* 1ccompll1hed. In accordance with applicable station procedures to ensure that plant aattty II malntainld.

a.o C.ONCLYSIQN The txlltlng ahc-lnch flbtrgla11 p.pfng to the control and relay room chllltr 11rvlce water pump and the charging pump 11rvlct water pump1 ha1 experienced problem, with respect to udlment and blo~lcal fouUng. Thia buildup of aedlment and biological producta ha1 required cleanlng ot the flberglUI pipe to maintain adequate pump suction conctlt1on1. The method ot

• cleantng hu utilized high pressure water (hydrola11na) which has caus.c:t

. I *

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