ML20212E813

Annual Operating Rept,1986, Describing Facility Changes, Tests & Experiments

ML20212E813
Person / Time
Site:	Vermont Yankee
Issue date:	12/31/1986
From:	Capstick R VERMONT YANKEE NUCLEAR POWER CORP.
To:	Vollmer R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
FVY-87-25, VYV-87-042, VYV-87-42, NUDOCS 8703040522
Download: ML20212E813 (13)

Text

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i We-x ' ,e__ ,_ ENCLOSURE 1 ,

. , t I. OPERATIONS SUf94ARY .

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' Chances in Facility Desian:

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li The following changes required author'ization from the Commission:

h a) ..EDCR 85-01 ECN 9,' " Recirculation /RHR Piping Replacement" was completed. 06-23-86.-

Th'is change replaced the stainless steel' piping;in the.

treactor recirculation and residual; heat. removal systems.

This_ replacement was necessary due to intergranular stress corrosion cracking of the

piping.. The' pipe replacement

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(program' answered the concerns of I/E; Bulletin 83-02.

A - b) . .EDCR-84-430, - " Torus Airspace Temperature" was completed '

06-24-86.

"To meet the requirements of Regulatory Guide 1.97, this-change. upgraded the torus-airspace temperature channel for >

post accident-monitoring instrumentation.

b g h goc) EDCR:84-410, " Removal of SCRAM Air Header Pressure' Switches"'

was completed 06-03-86.

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/h '1 t .This change. eliminated.any reactor protection. system monitoring of pressure in the SCRAM air header."This precluded any automatic SCRAMS due to degraded pressure conditions.in

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_g f t the header. Amendment No. 76 to Facility Operating License No..DPR-28 for Vermont Yankee Nuclear Power Station allowed-

.the implementation of this action'.

- ' d) EDCR 84-429, " Transmitter Upgrade. Pursuant to Regulat'ory

-Guide.1.97 Commitments" was completed 06-16-86.

This EDCR specifically dealt with the upgrade / modification '

committed to in Regulatory Guide 1.97 for' torus pressure,.

suppression ~ chamber /drywell. spray flow, and LPCI flow /RHR

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system flow.- The change included-the installation of-eight environmentally qualified pressure / flow / level electronic transmitters.

2. The following changes did not require prior Commission approval but were reviewed by PORC. It was determined that each did not involve any unreviewed' safety questions as defined in 10 CFR 50.59(a)(2) based on the information presented.

a), EDCR 86-406, " Motor Operated Valve Modification" was completed

[ 06-24-86. ,

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k This change modified the logic for the opening stroke of MOV 23-14 at j 23-19 to insure that the valves are able to perform their safety functions. The control circuitry for the valves was not modified; i.e., automatic and manual initiation of valve opening remains as is.

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. - .a To prevent-an over-torque condition from occuring in motor-operated valves 23-14 and 23-19, a 95 percent open limit switch contact was connected in series with the torque switch, b) EDCR 85-407, " Salem ATWS NRC Audit Drawing Changes" was completed 06-25-86.

This change was for the modification of various plant drawings, pursuant to the findings of the 1985 NRC audit of-the Salem ATWS program.

c) EDCR 85-405, " Replacement of HPCI Pressure Switches" was completed 07-07-86.

This change replaced the existing HPCI pressure switches with environmentally qualified pressure switches so that they will survive a large break LOCA and ensure containment isolation.

d) EDCR 85-404, " Vital AC MG Set Protection Relays" was completed 06-16-86.

This design change provided a remote independent protection circuit, located in a nonharsh environment, which will auto-matically transfer the Vital AC bus loads from the Vital AC MG Set output to the alternate supply, if the MG Set output voltage and/or frequency exceeds specified limits. These actions were in response to concerns of the EQ program.

e) EDCR 85-402, " Appendix "R" Fire Stops and Conduit Wrap" was completed 05-06-86.

This design change ensures protection from fire for required safe shutdown equipment. This is accomplished in part with conduit wraps to ensure the availability for shutdown, of the RCIC system and the torus level and temperature transmitters.

In addition, cable tray fire stops were installed in four areas to prevent the propagation of fire along the trays and ensure one train of equipment is availab7e for shutdown.

f) EDCR 84-427, " Neutron Monitoring System Upgrades" was completed 06-16-86.

This change replaced existing cabling and connectors with qualified cables and connectors to ensure LPRM operability, post accident. LPRM signals to the Control Room are unchanged. Implementation of this design change ensured that the LPRMs comply with the commitments made in Vermont Yankees' submittal to Regulatory Guide 1.97 and the concerns of the EQ program.

g) EDCR 84-423, " Modifications to Resolve NRC I/E Bulletin 80-11 Concerns at Vermont Yankee" was completed 04-08-86.

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h This EDCR addressed and removed'certain unacceptable pipe.- -

support' anchors from masonry _in-fill: walls.:

EDCR 84-402,f " Seismic Piping; Reanalysis" was completed-09-05-86.

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<' (The changes'-incorporated by this EDCR,-involved installation,-

1 modification, and/or removal of pipe' supports. These system; _

modifications. ensure the'integri_ty of_ the'affected systems: -

i while maintaining adequate l system flexibility; all.within

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allowable stress-limits. : Modifications.in this:EDCR provided

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the changes. required to address all concerns'of.I&E. Bulletin! g

, 79-02.

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i) PDCR 86_-02, " Cooling' Tower Seismic Modification" was

~ completed 06-23-86.

1This modification ensures'the cooling towers'-availability to provide an. alternate method-of cooling in conjunction with;a

. seismic event, which ensures sufficient,long term cooling to

. fulfill design ba' sis 1, 2, and 3 of Section 10.8.2.of_the.

.FSAR.(alternate cooling system). The modification: consisted of replacing the PVC fill _and providing. additional. bracing.

'j): PDCR 86-01, " Cut and Cap-Penetration X-48"'was completed-

. 05-06-86.

This design' change modified penetration X-48 into.a spare penetration and' returned the containment to.its original

-configuration. Two valvesi which~ bound the penetration, were:

removed and a welded cap installed.

The design change eliminated _ yearly local leak rate testing of the isolation valves required for this penetration.

k)E PDCR-85-06, " Torus to Reactor building Vacuum Breakers" was completed 03-05-86.-

This PDCR provides power to the pilot' solenoids on the torus

-to Reactor Building vacuum breakers-(V_-16-19-11A and V-16-19-118) from separate in' dependent power supplies.

The change is being initiated as a result of notification from General Electric that vacuum breaker valves may be inadequately separated. The concern was-also the subject of the IE Information Notice No. 85-26.

' 1) PDCR 85-05, " Radiological Effluent Technical Specifications

Modifications" was completed 01-29-86.

The NRC issued Amendment No. 83 to the Plant License j authorizing Vermont Yankee to implement the requirements of 10 CFR Part 50, Appendix I, to establish new limiting con-ditions for operation for quarterly and annual release rates t and to revise environmental monitoring programs (RETS).

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n- a. - u  ; Changes:were'made'toitheisolationcircuitry;for(the-AEOG,. ,

p radiation-monitors and-toLthe. fail relay-circuitry wiring;of .

._the'A0G-rad monitor system, m). JPDCR.85-04,f " Nitrogen CAD System" was completed 06-25-86.

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u The design ~ change conve'ted r the.exidting air: CAD system to a- ,

system which provides:the containment with nitrogen purge and" repressurization capability.

.n) :PDCR:85-03, "RPS Time Delay Replacement".-was completed 01-30-86.

This PDCR modified the RPS shutdown-SCRAM reset interlock circuit to eliminate two DC time relays from RPS' logic; panels; The relays were~being eliminated as a result of the;

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HFA relay coil' replacement effort required by I/E Bulletin No.' 84-02.

o) PDCR 85-02, " Reactor Water Clean-up. Regenerative Heat Exchanger-Replacement" was completed 05-05-86..

This~ design change replaced the existing RWCU regenerative heat-exchangers with a U-tube,1U-shell heat. exchanger which o is designed to eliminate head leakage while maintaining the-existing heat transfer capability.

p) PAR 86-05,. " Removal of Glycol From A0G Chiller Units" was- -

completed 06-25-86.

This PAR provided the necessary'designLinput and justifica-tion-to replace the present glycol / water solution with pure

-demineralized water in the A0G chiller units..LThis. change eliminated the potential of contaminating the condensate and.

'radwaste systems with organics, which has proven to be a:

problem in'the past.

q)- PAR 86-02, " Transverse'Incore Probe System" was completed 08-16-86.

i This PAR modified the Transverse Incore Probe'(TIP) System to address problems associated with TIP failures resulting in-reduced capacity factor. ~The modification replaced an

. existing Indexer, Drive Mechanism, Control Units,.and Purge System with new updated equipment.

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'r) PAR 86-01, - "CRD Maintenance Room Door Modification" was completed 06-25-86.

This PAR modified the CRD Maintenance Room door in support of the Environmental Qualification Program. The room was struc-turally qualified for a high energy line break (HELB) occuring in the steam tunnel, by modifying the existing entrance to relieve pressure surges into the reactor building.

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,) - -PAR 185-03, J" Condensate Phase' Separator

S'parger Strainer"'

~T" b ~ :wasicompleted 08-31-86.'

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iThis change: installed a'ba'sket-type strainer in.the discharge 3

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kline of th,e Condensate' Sludge, Discharge Mixing: Pump.to; prevent.

Lfuture plugging of.the. Condensate _ Phase Separator Spargers.

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o " :t)l : PAR 85-01,n-~." Supplement 2; Reactor.Buil' ding.-High Range A'rea; i

Radiation Monitors" was completed-05-23-86.

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' o Due.to1 inductive pickup from the=24VAC relays there was' feed-

. ~back to the Eberline Remote: Monitors thatl prevented thefalarm.

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c - circuits-from functioning properly. 'It was necessary.to:

. change to aLDC circuit'.that. consists of-a new DC power?

L supply, relays, and varisters'to jumper across the' coils-and

% across;the' relay contacts. -

lu); . Temporary Electrical Lifted. Lead / Installed' Jumper'(LL/J)

, 86-1251was' installed 06-26-86 and converted:to permanent-installation 09-19-86 by EDCR~86-406;

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LM T61s LL/J changed the operation--of the HPCI Steam Supply l Valve, to de-energize the motor.when. opening from either-the' '

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t full open.ljait switch or the torque switch,Eto only.the?

~ torque switch.

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- ; _ v) Temporary Electrical. Lifted Lead / Installed Jumper.(LL/J).

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, '86-115 was installed 06-11-86 and removed 06-26-86.

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The-switches' installed pursuant to:this LL/J are a temporary means of resetting the shutdown SCRAM reset interlock. This was necessary due'to'a relay race resulting in the-intermit -

tent inability to reset a SCRAM in the manual SCRAM circuits.

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.86-100 was installed 05-29-86:and converted to a permanent

, installation-06-24-86 by EDCR 86-406.

. This LL/J changed the operation of the HPCI Injection '41ve- l to de-energize the motor when opening, from eithet- the full open limit switch or the torque switch.to only'the torque -

. switch.

-- x ) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 86-35 was-installed 02-12-86 and removed 03-07-86.

This LL/J temporarily disconnected the standpipe water flow alarmtinput to the Reactor Building Pyrotronicz fire panel. ,

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This allows receipt of other Reactor Building fire protection alarm signals which were masked by standpipe water flow resulting from the implementation of Mechanical Bypass86-008.

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k' y)' Temporary Electrical Lifted Lead / Install'ed Jumper-(LL/J)'

86-28 was installed 02-03-86 and removed 03-05-86.

This LL/J' disconnected-SRM channel 21 "A"'and IRM channel "A" for the purpose of.. testing the cables priornto andfafter openin3 of the cable vault / Reactor. Building penetration.

z) ' Temporary. Electrical Lifted Lead / Installed Jumper (LL/J) 86-05 was installed 01-08-86 and removed 05-08-86.

-LL/J 86-05 bypassed.PCIS. interlocks to allow operation of the

~ main steam line drain; valve while a Group;1 isolation signal is present due to low low reactor water level during the- .

'1985-86 refueling outage.

aa) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 85-99 was installed 11-20-85 and removed 04-30-86.

This LL/J bypassed PCIS interlocks to allow operation of Reactor Building ventilation drywell equipment, and floor drain sump pumps after de-energization of RPS/PCIS during the 1985-86 refueling outage.

ab). Temporary Electrical Lifted Lead / Installed Jumper (LL/J)85-093.was installed 11-12-85 and removed 05-14-86.

The removal of the neutron monitoring coaxial cabling for qualification testing was covered in this LL/J.

ac) Temporary Electrical Lifted Lead / Installed-Jumper-(LL/J) 85-92 was installed 11-05-85 and removed 11-05-85.

This jumper bypassed the function of.a relay to allow valve.

testing-in the RHR shutdown cooling system during the-1985-86 refueling outage.

ad) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 85-86 was installed 10-19-85 and removed 05-12-86.

This LL/J bypassed the Reactor Building air lock door logic, such that the inner door could be operated with the electric controls during the 1985-86 refueling outage.

ae) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 85-75 was installed 10-11-85 and removed 05-08-86.

This LL/J provided a temporary power supply for the temporary sump collection pumps during the 1985-86 refueling outage.

af) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 85-73 was installed 10-22-85 and removed 03-31-86.

This LL/J removed the isolation valve interlocks for starting the Recirc MG Sets, and removed the low reactor level trip from the field breaker during the 1985-86 refueling outage.

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Lag)[.TemporaryElectricaltLifted: Lead / Installed! Jumper"(LL/J).

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'85-68-was: installed 10-06-85 and removed 03-07-86.

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-R . ?This LL/JLa11 owed th$ opera _ tion of the RHR_ system in;the; augmented, fuel. pool cooling mode during:the_1985-86 refueling

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_ outage. <

.,'ah)f. Temporary Electrical Lifted. Lead /Insta11ed'Jumperf(LL/J)-

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53 was installed 10-05-85'and removed ~04-26-86. ,

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'_LL/J,85-53 allowed'the~ removal of. multiple control. rod assemblies and did--not affect the rod block function ontthe

' remainder of the rod block system-during the.1985-861 Trefueling' outage.~ '

l ai) ITemporary Electrical Lifted. Lead / Installed Jumpert (LL/J)-

. 385-49 was installed 09-10-85-and removed 04-16-86. ~ -

s 4 This-_LL/J allowed operation of'the reactor recire pump during.

.the 1985-86 refueling outage.

aj)'. Temporary Electrical Lifted Lead / Installed Jumper.(LL/J). ,

185-48 was_ installed 10-12-85 and removed 04-12-86.

A. temporary. instrument-loop was installed to-provide l, level-indications below the range of the operational instrumen-tation. This occurred due to the. pipe replacement program gg during the_ 1985-86 refueling outage.

,, i O ~ ak) Temporary Electrical Lifted Lead / Installed Jumper-(LL/J) '

47 was installed 10-17-85 and_ removed 04-29-86.

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This LL/J disabled all low reactor waterLlevel SCRAM, PCIS isolations, and ECCS initiations during the 1985-86 refueling outage.

al) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 85-22 was installed 04-01-85 and converted to permanent wiring modification by PDCR 85-05, 01-29-86.

This LL/J removed the isolation circuitry for'the.AEOG

_ radiation monitors and recorders.. These functions are no longer required due to RETS (Tech._ Spec. Amendment 83).

am) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 85-21 was installed 04-01-85 and converted to permanent

. wiring modification by PDCR 85-05, 01-29-86.

> - Changes to the fail relay circuitry wiring of the A3G rad monitor system were specified in this LL/J. This is-also due to RETS-(Tech. Spec. Amendment 83).

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an)[; Temporary Electrical

Lif ted Lead /Instailed Jumper :(LL/J)s

'Q m 20 was installed 04-01-85 aad convertedtto permanent

-- wiring . modi fic'at ion .by, PDCR . 85-05, 01-29-85'

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'.Same as! LL/J 85-21.

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, .'a'o).) Temporary.-Electrical Lifted Lead / Installed Jumper'(LL/J)l

85-019:was installed 03-19-85 and removed 07-14-86.

?LL/J'85019,was for the' purpose._of; supplying-_aEtemporary.

Jpower. feed to theinew Construction office building.~

cap),1 Temporary-Electrica'1; Lifted Lead / Installed Jumper (LNJ)

??84-113 was installed 07-25-84.and converted lto4a permanenti <

wiring change by EDCR~85-01,-06-23-86.-

_This LL/J was.. instituted due:to a physical interference-which

. precludes.the installation 1of a qualified motor _onithis valve-

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(MOV~2-668).

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aq). Temporary.Electrica'l Lifted Lead / Installed Jumper (LL/J)

s. 84-53 was installed-07-06 and was removed 07-17-86.

The purpose of this LL/J was to provide a temporary power ~

supply.to the Construction office building.

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-ar) Mechanical Bypass 86-37 was installed;10-01-86 and was

- removed .10'-06-86.

This bypass provided a means for sampling condenser off-gas and injecting helium to the-condenser during reactor low power operation.-

as) ' Mechanical Bypass 86-36 was= installed 08-30-86 and was removed 09-01-86.

The purpose of this bypass was to isolate a section-of piping

. to allow repair'of an RWCU valve.

at) Mechanical Bypass 86-34 was installed 08-08-86 and was removed 11-17-86.

This bypass provided' service water to a temporary cooling fan for pump motor air cooling.

au) Mechanical Bypass 86-33 was installed 08-11-86 and was removed 08-15-86.

This tied in a temporary demin skid to the MUD system during

1. the 1985-86 refueling outage.

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av)ll Mechanic $11Bypassf86-31 was installed _06-24-86'and:wasi -

L'1 removed 06-28-86.

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iThis'MB? provided'a'.tieiin'for;a. temporary demin-skid.to the.

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LMUD system during the 1985-86 refueling outage.

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f , 4-aw)c Mechen.ical Bypass 186-30 was installed 06-25-86 and)was- '

?  : removedi07-08-86.' '

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. - This bypass provided a 'methdd : for. sampling . condenser ' of f-ga's .-

, i and'-injecting helium to'~the condenser;during (reactor (low - .

power operation.-

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Jax)~ MechanicallBypass:86-26wasl installed'05-29-86 and was-

_ removed 06-03-86.

'This MB provided.a drain line to remove water due to-al , ,

1eakage ofLisolation valves. This allowed repairs to-be made.

L ay) . Mechanical . Bypass '86-25 was- installed 05-09-86 'and was -

,1 removed 05-14-86.

• A connection was made from the MUD system to.a-temporary demin skid.

az): ' Mechanical Byp' ass 86-23 was installed 05-03-86 and was.

removed 05-05-86.

MB 86-23 relieved' abusive duty to the RWCU pumps caused b -

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. frequent clogging of the pump suction strainers.'

[ ba) > Mechanical Bypass 86-21 was installed 05-01-86 and-was-removed 06-01-86.

This MB provided an alternate path for condensate water transfer.

bb) Mechanical Bypass 86-19 was installed 04-24-86 and was

, removed 06-01-86.

This MB provided an alternate path for condensate water transfer.

bc)- Mechanical Bypass 86-18 was installed 04-17-86 and was

.. -removed' 05-31-86.

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R~ This provided an alternate path for discharge from the waste

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sample tanks to the hotwell.

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bd) _ Mech'anical Bypass 86-15 was-installed 04-14-86 and was removed 04-21-86.

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A connection was made between the-temporary demin skid and the MUD system.-

be) Mechanical Bypass 86-12 was installed.03-08-86 and was removed 03-14-86.

Temporary connecticas were made between the demin. skid and the MUD system.

-bf) Mechanical Bypass 86-10 was. installed 02-13-86 and was s

removed 02-18-86J

-This MB provided a connection between the terporary demin skid and the MUD system.

bg) Mechanical Bypass 83-09 was installed 02-08-86 and was removed 02-27-86.

8 This bypass changed the input to the heat exchangers on the RBCCW.

bh) -Mechanical Bypass 86-08 was installed 01-30-86 and was removed 02-27-86.

MB 86-08 directed Fire Protection System Water to the service water side of the RBCCW heat exchangers for cooling of the fuel pool during the 1985-86 refueling outage.

bi) Mechanical Bypass 86-06 was installed 01-17-86 and was removed 01-18-86.

This MB provided a temporary connection between the demin skid and the MUD system.

.bj) Mechanical Bypass 85-48 was installed 11-06-85 and was removed 02-27-86.

MB 85-48 provided a temporary supply of service water to TBCCW, house heating boiler radiation monitor, and the Laundry, while the Turbine Building service water system was isolated during the 1985-86 refueling outage.

bk) Mechanical Bypass 85-23 was installed 10-09-85 and was removed 04-11-86.

This MB provided an alternate water source to the reactor during the recirc pipe replacement project.

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!b1[ Mechanical' Bypass 85-22 wasiinstalled 10-07-85 and was 1 -

~ : removed'05-31-86.

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.This bypass provided'a: path to. drain.the reactor' vessel

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5through the fuel pool'demin system during the 1985-86 J' refueling outage. .

.be); Mechariical Bypass 85-21 waslinsta11ed:10-08-85 an'd was

= removed-05-09-86.

e This MB provided an alternate path'of drywell sump.. flow:

during-the 1985-86 refueling outage.

bn)- Mechanical. Bypass 85-20 was installed 10-09-85 and was-

-removed 05-09-86.

1This MB was;used to control' water level in accordance,with

- ' 'VYOP 1123 during'the.1985-86 refueling outage. -

bo) = Mechanical. Bypass 85-19 was. installed 10-04-85 and was.

removed, 05-09-86.

MB 85-19 provided-level indication for the' reactor vessel 1 bottom head during the.1985-86 refueling outage.

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bp)- Mechani, cal Bypass 85-11 was installed 12-06-85.and was removed 10-08-86.

This provided an additional closed loop!1ine which routed a

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small portion of Turbine Building water through an-ultra-violet water treater.

bq) Instrument Setpoint' Change 86-18 was completed 06-28-86.

This change was made to' allow an additional margin for error,-

to account for instrument inaccuracies as a result of changes in environmental conditions during a LOCA or HELB.

br) Instrument Setpoint Change 86-17 was completed 06-28-86.

This change was made to allow an additional margin for error, to account for instrument inaccuracies as a result of changes

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in environmental conditions duririg a LOCA or HELB.

bs) Instrument Setpoint Change 86-16 was completed 06-28-86.

This change was made to allow an additional margin for error, to account for instrument inaccuracies as a result of changes in environmental conditions during a LOCA or HELB.

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VhRMONT YANKEE NUCLEAR POWER CORPORATION

. VYV 87-042

. RD 5, Box 169, Ferry Road Brattleboro, VT 05301 gyg87-25 g ENGINEERING OFFICE 1671 WORCESTER ROAD

. FRAMINGHAM, MASSACHUSETTS 01701

• TELEPHONE 6174724100 March 1, 1987 United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 Attention: Mr. Richard Vollmer Regional Administrator

References:

(a) License No. DPR-28 (Docket No. 50-271)

Subject:

Vermont Yankee 1986 Annual Operating Report

Dear Sir:

Enclosed herewith please find one copy of the Vermont Yankee Nuclear Power Corporation Annual Operating Report, submitted in accordance with 10CFR50.59(b). This report describes the facility changes, tests, and experiments conducted without prior NRC approval dueing the year 1986.

We trust this information is acceptable to you; however, should you have

! any questions, please contact us.

Very truly yours, VERMONT YANKEE NUC EAR POWER CORPORATION t

N J4 l

R. W. Capstick Licensing Engineer RWC/bam Enclosure cc: U.S. Nuclear Regulatory Commission l

Office of Inspection and Enforcement Washington, DC 20555

[h7

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