ML20147F209

Annual Rept 1987

ML20147F209
Person / Time
Site:	Vermont Yankee
Issue date:	12/31/1987
From:	Capstick R VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
FVY-88-15, NUDOCS 8803070274
Download: ML20147F209 (10)

Text

r VisRMONT YANKEE NUCLEAR POWER CORPORATION

.. RD 5, Box 169. Ferry Road, Brattleboro. VT 05301 ,,,,y, ENGINEERING OFFICE f March 1, 1988 1671 WORCESTER ROAD F RAMINGH AM, MASS ACHUSETTS 01701 FVY 88-15

- tretewovit air orosioo United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555

Reference:

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

Subject:

Vermont Yankee 1987 Annual Operating Report

Dear Sir:

Enclosed 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 during the year 1987.

We trust this information is acceptable to you; however, should you have any questions, please contact us.

Very truly yours.

VERMONT YANKEE NUCLEAR POWER CORPORATION Y Z R. W. Caps ick Licensing Engineer RWC/25.407 Enclosure cc: USNRC Region 1 475 Allendale Road King of Prussia, PA 19406 USNRC Resident Inspector, VYNPC 8803070274 871231

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.' ANNUAL REPORT 1987 I. OPERATIONS SUfEARY A. . Ch'anaes in Facility Desian

1. .The following changes required' authorization from the commission (a) EDCR 87-407.-"Standby Liquid Control System Modification,"

was completed September 26, 1987.

In order to satisfy the ATWS Rule 10CFR50.62 injection requirements, an enriched boron solution was established.

This was accomplished through an increase of.the Boron-10 isotopic content in the stored sodium pentaborate decahydrate solution.

(b) EDCR 87-404, "Torus Water Temperature Indication," was completed Septr.mber 25, 1987.

This EDCR provided for the replacement of dual-junction thermocouples with three-junction thermocouples. Two new seismically qualified temperature indicators were also added to Control Room Panel 9-3. The intent of this change. was to fulfill the requirements of Regulatory Guide 1.97 addressing torus water temperature upgrade to full qualification, redundancy, continuous real time display, and use of on-site (standby) power.-

(c) EDCR 86-409, "ADS Logic Modification," was completed September 15, 1987.

In response to the requirements of NUREG-0737 Item II.K.3.18, the ADS logic was modified. This change provided a bypass for the high drywell pressure signal after a sustained low taactor level signal. In addition, manual inhibit switches for the automatic initiation of ADS and a block switch to block inadvertent initiation of ADS were installed on CRP 9-3 for Appendix R concerns.

2. The following changes did not require prior commission approval, but were reviewed by PORC. It was determined that these changes d!,d not involve unreviewed safety questions as defined in 10CFR50.59(a)(2) based on the information presented.

(a) EDCR 87-402, "ECCS Pump Room and Control Room HVAC Electrical Modifications," was completed September 24, 1987.

This EDCR modified the ECCS Pump Room HVAC controls and rerouted conduits cssociated with the Control Room HVAC.

The changes were implemented following assessments made in accordance with IE Bulletin 80-11. This addressed possible adverse affects on the operability of certain 6366R/20.429 Q [

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safety class electrical systems due to a failure of block walls during a postulated seismic event.

(b) EDCR 87-401, "CRP 908 Vital AC Indication and Supply Selector Switch," was completed August 25, 1987.

This design change accomplished two separate tasks. It first fulfilled a Vermont Yankee commitment to meet Regulatory Guide 1.97 by installing Vital AC frequency and bus voltage indication in the Control Room. Second, the Vital AC selector switch was relocated to CRP 9-8 as agreed upon during a Detailed Control Room Design Review.

(c) EDCR 86-413. "252' Elevation, Appendix R Modification,"

was completed September 18, 1987.

This design change was implemented to address 10CTR50, Appendix R concerns. Additional transfer capability was added to Control Panel 82-3 to enhance the operability of RCIC Steam Supply Isolation Valve V13-15. An alternate power source capability is provided in the event normal power is lost during alternate shutdown conditions.

(d) EDCR 86-405, "Conduit Fire Wrap," was completed August 24, 1987.

This design change installed additional fire barrier materials to electrical conduits and trays in the radwaste hallway and the northwest Corner Room, 232' elevation.

This fire protection upgrade satisfies 10CFR50, Appendix R requirements.

(e) EDCR 86-402, "Diesel Generator Room Ventilation Design Modification," was completed on August 24, 1987.

This EDCR modified the diesel generator ventilation control circuitry to eliminate potential loss of ventilation due to fire in ene Turbine Building or the HVAC Room. This was accomplished by relocating the existing controls in the HVAC Room.

(f) EDCR 85-403, "Reactor Vessel Water Level Reference Leg Upgrade," was completed September 23, 1987.

This upgrade of the Reactor Water Level Measurement System followed an evaluation performed on the system as required by NRC Generic Letter 84-23. This EDCR replaced the Yarway Temperature Compensation Column and existing cold reference leg arrangements with a dual Cold Water Reference Leg System.

(g) EDCR 84-416. "345 kV Breaker 81-1T Replacement," was completed August 14, 1987.

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m This design change replaced one of the five existing 345 kV breakers with a new 345 kV SF6 circuit breaker.

The intent of the change was to provide a new (Cogenel),

Delle-Asthom breaker for which replacement parts are readily available.

(h) EDCR 86-03, "Elevation 280' Fire Zone Separation," was completed September 24, 1987.

This design change rerouted Emergency Core Cooling System (ECCS) cables and conduits connecting Racks 25-5 and 25-6 to their associated cable trays. This will ensure ECCS train and fire protection separation. The above changes satisfied 10CFR50, Appendix R requirements in the Reactor Building, 280' elevation.

(i) PDCR 86-08, "Reactor Protection System Alternate Power Supply Improvements," was completed September 22, 1987.

This PDCR installed a voltage regulator for the alternate RPS Power Supply and disconnected a shunt trip device in MCC 8B. These two changes increase the reliability of the Alternate Power Supply System.

(j) PDCR 86-03, "Drywell Thermocouple Upgrade " was completed September 25, 1987.

This design change upgraded the drywell temperature monitoring systems used for post-accident monitoring. The upgrade consisted of modifications to the existing drywell temperature channel, TE-16-19-30, and the addition of a second (redundant) fully qualified channel. Additionally, the torus air temperature channel, TE-16-19-34, was also upgraded. The new channel replaced the existing TE-149 1 to TE-149-8 channel used for post-accident monitoring.

(k) PDCR 85-10. "Reactor Building Fire Protection Elevation 252' and 280'," was completed August 17, 1987.

This PDCR installed and tested additional smoke detectors in the Reactor Building on the 252' and 280' elevations.

These detectors alarm back to the existing Reactor Building Pyrotronics fire panel, CP-30. The enhancement of the existing fire protection system further assures the plant's capability to obtain and maintain safe shutdown.

(1) PDCR 85-07, "Reactor Vessel Pressure and Level Recorders,"

was completed September 23, 1987.

Existing two-pen recorders were replaced with new three-pen recorders to allow for reactor vessel pressure and level to be trended on the same recording instruments. This change satisfies the requirements of Regulatory Guide 1.97 by providing redundant recording 6366R/20.429

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' instrumentation to. monitor reactor vessel pressure and

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water level.

PDCR 85-01, "RCIC-22 Replacement," was completed

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October 5, 1987.

9 v This PDCR replaced-the existing 900 lb RCIC-22 check valve with a 1,500 lb class standard swing check valve. The new-valve will' prevent leakage and steam cutting of the RCIC_20 and 21 valves. In addition, three manually-operated gate valves were installed to allow the-RCIC pump discharge piping to be easily isolated for in-service inspection, testing, and maintenance.

(n) _ PAR 87-12. "Feedwater Flushline Pipe Replacement," was completed October 6, 1987.

This PAR replaced Valves V63-22B and V63-23B with spectacle flanges for the duration of the 1987 through 1989 operating cycle.

(o) PAR 87-07, "Green Mountain Watt Hour Meters," was completed August 10, 1987.

This PAR allows the replacement of metering equipment to monitor the station service power requirements off the 115 kV Keene line.

(p) PAR 87-05, "TBCCW Water

• aatment," was completed September 1, 1987.

Larger motors were installed on the TBCCW pumps. This modification improved system reliability by achieving single pump operation, and enhanced performance monitoring of the TBCCW heat exchangers. Temperature and pressure indication instruments were added to the heat exchangers, and the TBCCW pump control circuitry was modified.

i (q) PAR 87-04, "HVAC Equipment Room Block Wall Modifications,"

was completed October 7, 1987.

This PAR installed modifications to portions of three masonry walls separating the individual HVAC Equipment Rooms. These modifications addressed NRC I&E Bulletin 80-11 concerns and ensured that any safety-related equipment in the vicinity of these block walls will not be adversely affected by a seismic event.

(r) PAR 87-01, "Condensate Storage Tank Sump Pump Timer," was completed June 17, 1987.

A Hobbs hour meter was installed in MCC-10B to monitor the operation time of the CST Sump Pump, P93-1A.

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'(s ) PAR 86-03, "Intake and Discharge Gate Hydraulic Actuators," was completed January 2, 1987.

This PAR replaces the existing Limitorque motor operators with hydraulically-operated actuators on the "A" Intake Gate, at the Intake Structure, and the Recirculation Gate at'the Discharge Structure.

(t) PAR 85-11. "Diesel Generator Expansion Tank Fill Line Modification," was completed' January 9, 1987. ,

This PAR changed the makeup / water supply from the TBCCW to the demineralized water. The change enhanced corrosion control measures in the DG Cooling Water System.

(u) PAR 85-05, "Toxic Gas Improvements," was completed October 1, 1987.- ,

This PAR made changes to the Toxic Monitoring System to enhance system operation, calibration, and maintenance.

(v) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 87-0155 was installed September 30, 1987 and removed September 30, 1987.

This LL/J provided bypasses for pump operation permissives I associated with the RHR and Clean-Up pumps during maintenance activities on the system.

(w) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 87-0081 was installed August 24, 1987 and removed September 24, 1987.

This LL/J bypassed an interlock for RHR V10-18, inboard isolation valve. It provided the necessary permissive function while the V10-18-control circuitry was being repaired. [

(x) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 87-0036 was installed July 14, 1987 and removed September 14, 1987.

This LL/J installed a relay annunciator circuit for the HI/LO level alarms on the B recirculation pump in order to isolate grounds detected in the level switches from the DC Annunciator System.

(y) Temporary Electrical Lif ted Lead / Installed Jumper (LL/J) 87-0029 was installed June 17, 1987 and removed July 13, 1987.

This LL/J allowed bypass of the refuel crane load cell monitor in the "HI/LO circuit." With supplementary visual monitoring, this bypass increased the safety of operating 6366R/20.429

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the crane while performing refuel floor activitles. during the 1987 refueling outage.

(z) Temporary Electrical Lifted Lead / Installed Jumper (LL/J) 87-0028 was installed June 16, 1987 and removed June 17, 1987.

This LL/J allowed bypass of the refuel crane load cell monitor in the "HI/LO circuit." With supplementary visual monitoring, this bypass increased the safety of operating the crane while performing refuel floor activities, during the 1987 refueling outage.

(aa) Temporary Electrical Lifted Lead / Installed Jumper (LL/J)86-157 was installed December 29, 1986 and removed August 22, 1987.

This LL/J provided known environmentally qualified Drywell-and Torus temperature inputs into the Technical Specification required recorder, TRI-16-19-145. Equipment qualification of the existing input was indeterminate.

(ab) Temporary Electrical Lifted Lead / Installed Jumper (LL/J)86-156 was installed December 29, 1986 and removed August 22, 1987.

This LL/J provided known environmentally qualified Drywell and Torus temperature inputs into the Technical Specification required recorder TRI-16-19-45. Equipment Qualification of the existing input was indeterminate.

(ac) Temporary Electric Lif ted Lead / Installed Jumper (LL/J)86-154 was installed December 8, 1986 and converted to permanent installation September 29, 1987.

This LL/J established the documentation for two cables installed by MR 87-0073 which eliminated a circulating currents problem affecting the RPS distribution panel.

These cables were made permanent under LL/J 87-0074.

(ad) Temporary Electrical Lifted Lead / Installed Jumper (LL/J)86-137 was installed August 29,'1986 and removed September 14, 1987.

This LL/J installed a Relay Annunciator circuit for the HI/LO level alarms on the B recirculation pump in order to isolate the grounded level switches from the DC Annunciator System.

t (ae) Temporary Electrical Lifted Lead / Installed Jumper (LL/J)86-032 was installed February 13, 1986 and converted to permanent June 3, 1987.

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'This LL/J changed the alarm configuration, from parallel to series, of the isolated phase bus low cooling water flow switches FS-104-3A, and 3B. The change will prevent low flow in_the isolated standby IPBC unit from masking the TBCCW nperating unit.

(af) Mechaalcal bypass, 87-0021, was installed August 21, 1987 and was removed September 21, 1987.

This bypass provided Reactor Building; Air Conditioning

_(RBAC) cooling during Service Water valve maintenance.

(ag) Mechanical bypass, 87-0020, was installed August 18, 1987 and was removed August 20, 1987.

This bypass allowed temporary draining of the RHR-SW seal cavity to a leak-off drum.

(ah) Mechanical bypass, 87-0019, was installed August 13, 1987 and was removed September 19, 1987.

This bypass allowed connection of a temporary air compressor system to the service air system during the outage. In addition, it provided dry air purge for stator cooling in support of high potential testing on the main generator.

(ai) Mechanical bypass, 87-0015, was installed August 25, 1987 and was removed September 12, 1987.

This bypass allowed temporary drainage of Line SW-9 (20")

via Valve V70-193 into a drum.

(aj) Mechanical bypass. 87-0013, was installed August 16, 1987 and was removed October 9, 1987.

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

(ak) Mechanical bypass, 87-0012, was installed August 14, 1987 and was removed August 17, 1987.

This bypass allowed for an alternate cooling water supply to the Reactor Building Air Conditioning (RBAC) units during the isolation of their normal service water supply for valve maintenance.

(al) Mechanical bypass, 87-0010, was installed August 13, 1987 and was removed September 23, 1987.

This bypass maintained Reactor Water Cleanup (RWCU) operability during the installation of V-13-22, (PDCR 85-01).

6366R/20.429

. (am) Mechanical bypass, 87-0007, was installed May 18, 1987 and was removed May 22, 1987.

This bypass allowed the removal of piping required to disassemble the C-RHR pump. This maintenance activity occurred during the RHR pump impeller replacement.

(an) Mechanical bypass, 87-0005, was installed April 17, 1987 and was removed May 26, 1987.

This bypass fulfilled the requirements for relief of Technical Specification, Paragraph 4.7.A.3. The bypass provided additional pressure indication between the RHR 17 and 13 valves during RHR maintenance activities.

(ao) Mechanical bypass, 87-0004, was installed March 3, 1987 and was removed May 19, 1987.

This bypass provided service water to a temperature cooling fan for the P-7-1A pump motor.

(ap) Mechanical bypass, 87-0002, was installed January 29, 1;87 and was removed February 24, 1987.

This bypass was used to install a heater in the A0G Penthouse.

(aq) Mechanical bypass. 86-0043, was installed December 5,1986 and was removed May 7, 1987.

This bypass installed plywood panels on the outside of the A0GCCW heat exchangers located in the A0G Building Penthouse. The plywood would decrease the probability of freezing in the A0G Closed Cooling Water System or its supplied components due to low ambient temperatures.

(ar) Mechanical bypass85-003, was installed April 4, 1985 and was removed March 5, 1987.

This bypass was installed to set up a temporary decant system in the cask room to facilitate liner filling prior to shipping for burial.

(as) Instrument Setpoint Change 87-11 was completed September 29, 1987.

This change reduced Recirculation MG Set Foam System time delay for initiation from three minutes to less than or equal to two seconds. This new setting resulted from Appendix R fire zone analysis reviens of the area protected.

B. Test Experiments

1. None.

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C. Safety and-Relief Valve Challenges and/or Failures

1. :None.

! Special Test Procedures

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1. Special test procedure, 87-02, was released for execution-July 16, 1987 and was tested July 20, 1987.

This procedure ascertained through testing, the correct operation of the Computer Monicore Software on Version 4.4 of~

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the VAX/VMS Operating System. Although the process computer is a non-safety related item, certain calculations performed by_the computer ensure compliance with Technical Specification Operating Limits. A safety evaluation was performed to ensure that there were no unreviewed safety questions.

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6366R/20.429