Text

(Units 1 & 2) Annual Operating Rept to NRC,1986
	ML20212J474
Person / Time
Site:	Sequoyah
Issue date:	12/31/1986
From:	; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML20212J402	List: ML20212J398; ML20212J474;
References
	NUDOCS 8703090033
	Download: ML20212J474 (98)
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TEXXESSEE VALLEY AETHORITY OFFICE OF XECLEAR POWER d

THE

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SEQUOYAH NUCLEAR PLANT (UNITS 1 and 2)

ANNUAL OPERATING, REPORT l

TO THE NUCLEAR REGULATORY COMMISSION

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l JANUARY 1,1986 - DECEMBER 31,1986 l

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DOCKET NUMBER 50-327 and 50-328 LICENSE NUMBER DPR-77 and DPR-79 t

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. SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT

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y TABLE OF CONTENTS

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Page iin PREFACE p

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. I.s Sununary of Emergency Core Cooling System (ECCS) Outages 1

i SibmaryofPrimary,SystemRelieforSafetyValve II, Actuations 1

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III. Sunmary. of Facility Changes Modifications 2

Temporary Alterations 7

IV.

Sununary of Procedure Changes 40 V.

Summary of Special Tests 77 VI.' Occupational Exposure Data 81 1

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.r SEQUOYAH NUCLEAR PLANT i

ANNUAL OPERATING REPORT y

1986 l

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PREFACE Sequoyah Nuclear Plant, in an effort to improve its regulatory performance, is revising the methodology for reporting information in this report. This effort, to date, has resulted in the following.

A.

Requirement:

1 Facility Changes - Report facility. changes pursuant to 10 CFR 50.59(b), including a summary of the safety evaluation of each.

Response

The Engineering Change Notice (ECN) Closure Group reports to Site Licensing the ECNs that have been closed for inclusion in the annual FSAR update. The same ECNs will be reported in the annual operating report. Since the ECN Closure Group reports totally closed ECNs, and field complete ECNs were reported in previous annual reports, a cross-check was made. Only the ECNs not previously reported will be included in the annual operating report.

A Temporary alterations to the facility are reported based on how long the alteration-has been in' existence. Using the same criteria that is used for the FSAR update, an alteration will be reported if it has been, or is expected to be, in existence for greater than one year.

l A summary of'the safety evaluation for each ECN and alteration reported will be included.

B.

Requirement:

Procedure Changes - Report procedure changes pursuant to j

10 CFR 50.59(b), including a summary of the safety evaluation of each.

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Response

Site Licensing and the Plant Operations Review Staff (PORS) Plant

-Reporting Section are identifying procedures described in the FSAR.

Technical specification surveillance instructions (sis), abnormal operating instructions (AOIs), and emergency instructions have been determined as being " described in the FSAR."

Changes to these procedures will be reported if they satisfy one or more of the following:

1) Make a significant change to.the scope, technique, or sequential order of steps affecting results or nuclear safety.

2) Waive or violate technical specification or licensing requirements.

3) Affect a QC hold point.

4) Change or revise the review / approval authority or responsibility.

5) Implement a temporary alteration to operate CSSC equipment.

6) Change the acceptspee criteria.

Procedure changes to correct typographical errors and general s

administrative changes will not be reported.

A summary of the safety evaluation for each procedure change reported will be included.

Additional procedures may be included in future reports if they are identified as " described in the FSAR."

0352f i

t SUMMA 3Y OF EM3RGENCY CORE COOLING SYSTEM (ECCS) OUTAGES

SUMMARY

OF PRIMARY SYSTEM RELIEF OR SAFETY VALVE ACTUATIONS

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SEQUONAM NUCLEAR PLANT ISCS NRC P.NNUAL REPORT

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SUMMARY

OF-EMERGENCY CORE COOLING SYSTEM CECCS) OUTAGES No ECCS system was declared inoperable while in an applicable made of operation in 1986.

Both units wara in made S the entire year.

II.

PRIMARY SYSTEM RELIEF or SAFETY UALUE ACTUATION There were not any challenges to the primary system relief or safety valves in 1986.

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SUMMARY

OF FACILITY CHANGES MODIFICATIONS c

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.Pcg] No.

1 02/22/87 SEQUOYAH NUCLEAR PLANT 1586 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - MODIFICATIONS

-DESCRIPTION SAFETY'

SUMMARY

C*'ECN - L5184 O

DCR - 0741 R:placed door. latch mechanism Trion This change fulfilled current access OO1CR on system 30 Caux111ary building control requirements of the FSAR and g20 treatment system), with Folger Adam did not deviate from evaluated security Oltctric strike 310-2 door latch recuirements. There were no technical.

Ecchanisms.

specification changes or involvement.

o* ECN - LS212

.O DCR -

Modified all-Bettis robot arm actuators This modification does not affect which were installed sideways or upside previously evaluated safety concerns.

down by installing a spacer bushing Since there is no movement within the

.which prevents the key from falling area where the spacer was inserted, no out. Valves involved were located on wear or material failure is

'tha purge air, emergency gas treatment, anticipated. With the information Cnd chilled water systems, available, no known safety concern exists.

00 ECN - L5251

-0 DCR - 0671 Installed new typical supports at This is not a primary safety-related GlGvation 742 feet 0-inches on the system and does not create a different 2-inch risers of the fire suppression type of accident or malfunction from lEystem.

previous FSAR evaluations. The basis for any technical specification margin-of safety is not reduced by this change.

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.02/22/B7 SEQUOYAH NUCLEAR PLANT 1986'NRC ANNUAL OPERATING REPORT FACILITY CHANGES - MODIFICATIONS DESCRIPTION SAFETY

SUMMARY

Oco ECN - LS293.

o DCR - 0758-Provided attachments-to secure the These attachments secure the reactor rccctor head lifting rig during head'11fting rig during storage and Ctorage.

during a seismic event.'The reactor head lifting rig is not a

-safety-related component, nor does it interface with any safety-related system. As such, it is not addressed in the mitigation of any accident or malfunction evaluated in the FSAR.

Proper storage of the lifting-rig and stringent GA precautions keep any c

support assembly material from being inadvertently lost in the open vessel.

.There is no reduction in the margin of.

safety as defined in the basis for ang technical specification.

00 ECN - LS367.

O DCR - 0830 Exczssive noise on cable INH 200 of The spare cable used is identical to source range monitor 1-XE-92-SOO2 the cable it replaced: meets all l

CN-32) necessitated the use of spare applicable cable specifications, c2ble INM202.

separations criteria, and QA requirements. This substitution does not adversely affect any plant systems, i

and the margin of safety as defined in the basis for any technical specification is not reduced.

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'02/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - MODIFICATIONS DESCRIPTION SAFETY

SUMMARY

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ECN - L5455 b

DCR - 1039 R: moved the external vent manifold from The reciprocating charging pump does LthD reciprocating charging pump Cunit not perform a primary safety function.

1) cnd installed new cylinder heads and These modifications will provide better hacd extensions. Drilled 1/32-inch operating performance. Neither The

' orifices in each discharge valve.

technical specification nor their bases are involved.

00 ECN - L5 SOB o

DCR - 0359 Innta11ed a manway in the pressurizer The manway was designed to seismic and cnclosure roof slab, reactor building, LOCA design criteria. The margin of cicvation 775.0 feet.

safety as defined in the basis for any technical specification is not reduced, 00 ECN - L5716 o

DCR - 1276 ChEnged capacitors C3 and C4 The replacement capacitors perform the Coriginally 22 microfarads) C7 and C8 same function as the original and have Coriginally O.33 microfarads), with 0.1 equal or better qualifications.

microfarad capacitors on GE mod 111 Reducing the size of the capacitors Ctotic relays. This change will does not increase the possibility for climenate a 6 millisecond tripping time loss of offsite power or cause any dalsy, thus reducing the possibility of other increases previously evaluated in drm;ging the 500kV transmission lines.

the FSAR. There is no reduction in margin of safety since no bases are affected. -

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4 02/22/07 SEQUOYAH NUCLEAR. PLANT' 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - MODIFICATIONS-DESCRIPTION SAFETY

SUMMARY

iGO ECN

'L5756

'O DCR - 1359 r

S321 welded-the threaded pipe plugs This seal welding does not affect.the-which' seal the. hinge' pin holes on function of the check valve.-The amount

'fccdwater check valves:3-508, 3-509, of weldment added does not change the

.3-510 and 3-511 on the feedwater seismicity of the valve installation.

cyntem.

Welding was performed and controlled to TVA Class B requirements. These plugs have been a recurring leak problem. The plugs are now seal welded.

00 ECN - L5798 0

DCR - 1257 Installed flanges between the This change does not invalidate system containment spray heat exchangers and or component seismic requirements. The v21ves 1-72-535,.-536, -537, and -538.

flanges were installed on vent lines coming off the containment spray heat exchangers. The installed-flanges meet-the same requirements and qualifications as the piping in which they were installed.

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ECN LSOE5 DCR - 1435 Ch2nged the input range on transmitter The heater drains and' vents system is a PT-6-292 (for #7 heater drain tank pump non safety-related system located in cuction pressure) from 0-10 psia to the turbine building and does not 0-30 psia.

interface with any safety systems.

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S 02/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - MODIFICATIONS DESCRIPTION SAFETY

SUMMARY

co ECN - LS122 0

DCR - FCR2271 Pcr evaluation of CEB rigorous analysis A reevaluation of the support N2-70-19A and N2-70-18A spring supports calculations was done on the spring on DWGS H10-616, H10-890, 47A464-3-135 supports. The reevaluation proved that Cro not needed and have been voided, the supports were not needed. The Syntem involved is component coc11ng icading on the nozzle is less without watcr.

the springs. With no springs installed the seismic qualification of the piping is not invalidated. The only technical specification dealing with this system concerns itself with the operability of the component cooling water system. The changes made do not change or degrade the operability of the CCS system.

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SUMMARY

OF FACILITY CHANGES TEMPORARY ALTERATIONS i

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1 02/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

.co TACF: 0-79-0633-079 In;talled temporary grating, The original plant configuration Cpproximately 18 inches wide, in the required grating over the entire vault, north and south ends of the fuel This grating was removed for access to Ctorage vault.

the fuel assemblies. The 18-inch section retained at the north and south ends is for personnel safety. This change does_not degrade the present system or decrease the margin of

safety, 00 TACF: 0-80-0088-012 Modified the process range on auxiliary The auxiliary boiler is not governed by

. boiler B level transmitter (0-LT-129) any technical specification. This from 0-to 20-inches water column to change does not reduce the margin of 0-to 18-inches water column. This was safety as defined in the basis for the donJ to imnrave steam drum water level technical specification. This TACF is

control, scheduled to be cleared when work on ECN-LS854 is completed, past. unit 1 cycle 3.

co TACF: 0-80-0089-012 Modified the process range on auxiliary The auxiliary boiler is not governed by boiler A level transmitter (0-LT-12A) any technical specification. This from 0-to 20-inches water column to change does not reduce the margin of 0-to 16-inches water column. This was safety as defined in the basis for the don] to improve steam drum water level technical specification. This TACF is control.

scheduled to be cleared when ECN-LS854 is completed, post unit 1 cycle 3.

00 TACF: 0-81-0021-077 Novcd the waste baler to the waste The waste baler is non-CSSC. This TACF packaging area. This was done to make is scheduled to be cleared when work on room for the new laundry and combine ECN-LG598 is completed.

tha waste packaging into one area.

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' DESCRIPTION SAFETY

SUMMARY

00 TACF: 0-81-0241-067 Installed removable spac1 sections in Addition of four removable spool the ERCW supply line to the boric acid sections does not increase the trcnsfer pump and auxiliary feedwater probability of an accident. The spool pump space' cooler.2A for. monitoring sections are the same size as the ERCW pipe corrosion, original piping and add no appreciable pipe restriction. This TACF is scheduled to be cleared when ECN-LSOOS is complete, post unit 1 cycle 3.

C0 TACF: 0-B1-0297-014 Lownrad the setpoint of 0-PS-14-133 to The functions of the equipment affected cllow the switch to open valves on the by this change will remain in condensate domineralizer, accordance with the guidelines previously evaluated. No margin of safety is reduced. This TACF will be cleared when ECN-5388 is completed, post unit 1 cycle 3.

'co TACF: 0-B1-0328-077 R: moved the flapper frcm check valve This is nonsafety-related equipment.

0-77-572 to speed up the release of Removal of the valve internals does not w Ota water processed through the effect the integrity of the piping or tcmporary D.I. This allows pumping from increase the consequences of an thJ cask decontamination tank directly accident.

This TACF is scheduled to be to the monitor tank.

cleared when work on ECN-LSS11 is completed.

Co TACF: 0-81-0429-031

. Changed the setpoint of the liquid line Pressure switch 0-PDS-310-175 is for

.prC2sure switch 0-PDS-310-175 on personnel protection; the cooling 01cctric board room chiller.B-B from function described in the FSAR is not 190 psig to 130 psig to allow the affected. This TACF will be cleared i

cicctric board room air handling unit when work on ECN-LS257 is completed, j

to run. This was done because the i

CC;ociated water regulating valve would not shut.

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3 02/22/C7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

co TACF: 0-B1-0458-067 In panel 0-N-2BB, terminal block BA1, This system does not perform a t r;;inals 4, 5, S,

10, 11, and 12, safety-related function.

Equipment circs were lifted to allow monitoring that was installed in the ERCW pumping Cf the ERCW pump motor winding and station and the main control room is be: ring temperatures in the main seismically qualified.

The probability c ntrol room. This modification to the of an occurrence or the consequences of ERCW multiplexer cabinet was necessary an accident or malfunction of equipment due to the Fluke Data Aquisition System is not increased.

Cnd printer being inoperable.

co TACF: 0-81-0465-027 R placed the existing Cooling Towers This system does not perform a Dato Acquisition Control System until safety-related function.

Equipment it is working properly.

This was done that was installed in the ERCW pumping to give the operator a means of station and the main control room will conitoring pump temperatures.

be seismically qualified. The probability of occurrence or the consequences of an accident is not increased.

This change does not decrease the margin of safety as defined in the basis of any technical specification.

Co TACF: 0-81-0529-014 R moved 0-FE-14-139 from the line and The function of the equipment affected rcplaced it with piping. This was done by this change remainsin accordance to otop an acid leak in the D.I. plant, with the guidelines previously evaluated. The margin of safety is not reduced. This TACF is scheduled to be cleared when work on ECN-L5388 is completed.

00 TACF: 0-81-2442-077 R moved the internals from check valve Other isolation valves are used to 0-77-680 to allow gravity flow from the replace the check valve function. The CDWE distillate tanks to the cask change was made only to give d: contamination tank.

flexibility for operation of the system. Liquid radwaste affluent is pumped between the tanks associated with this system, so exchange of liquid poses no possibility of a different type of malfunction. This TACF is scheduled to be cleared when work on ECN-L5911 is completed.

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O2/E2/87 SEQUOYAH fiUCLEAR PLANT 1986 NRC ANNUAL' OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS

-DESCRIPTION SAFETY SUNNARY-oo TACF: 0-02-0127-077-

'In:talled a strainer in the auxiliary The installation of this strainer does wasta evaporator filter housing that not' degrade or effect any twill remove large particles and prevent safety-related systems or functions th0 plugging of the flow nozzles.-

required for the safe shutdown of-the plant. The change did not adversely affect any plant safety system. The-margin of safety as defined in the basis for any technical specification is not reduced. This TACF is schedulad' to be cleared when work on-ECN-LSS11 is completled.

CC TACF: 0-82-0130-077

.R; oved the filter element from the This change does not adversely affect w35te condensate filter housing. This any plant safety systems. The margin of t03 done to allow pumping of the floor safety as defined in the basis for any drains co11metor tank to the cask decon technical specification is not reduced.

' drains collector tank without plugging This TACF is scheduled.to be cleared th3 filter.

when work on ECN-L5911 is completed.

oo TACF: 0-82-0229-057 Installed a fire hose dryer in the The laundry area is located on 1cundry room to allow the drying of elevation 690 feet in the service fcc3 masks.

building and is not a seismic structure. The systems serving the laundry are not CSSC at the point of service to the laundry. Portions of the radwaste and fire protection system are safety-related but are'not affected by this change. The margin of safety in the technical specification is not reduced by this change. This TACF is scheduled to be cleared when work on ECN-L5237 is completed.

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SUMMARY

.c* TACF: 0-02-0258-067 Isolated 0-LDS-67-470D -477D,-482D, and At the ERCW pumping station. the level-

-437D'by lifting wires in 1-R-128 and differential switch.for the screen wash 1-R-131 to prevent the ERCW screen wash ~ system for the ERCW traveling screens purps from starting on a loss of has been replaced with a more reliable

-instrument signal.-

bubbler type level differential system.

The instrument ws11s used for.the.

diaphragm boxes are used for the sensor tubes. The change did not invalidate system or component seismic requirements. This TACF is scheduled to be cleared when work on ECN-L5750 is completed.

C0 TACF: 0-82-0275-077 R; moved the internals from check valve Administrative control of the affected 0-77-696 to allow backflushing of the section of the primary water system nazzles in the spent. resin storage tank will prevent any contamination to the-without requiring valve bonnet removal. system due to backflow. The spent resin storage tank pressure is limited to 100 psig which is less than primary water system pressure. This TACF is scheduled to be cleared when work on ECN-L5911 is completed.

co TACF: 0-02-0315-410 Documented the defeat of the interlocks Public Safety personnel have been on doors A56 and A57 Cauxiliary stationed at the doorways to serve as building entry doors).

security and fire watches and to insure the operability of the airlock. The margin of safety as previously analyzed or defined in the basis of any technical specification has not been reduced. This TACF is scheduled to be cleared post unit 1 cycle 3.

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6 02/22/07 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

C3 TACF: 0-82-0390-410 Rim ved the handwheel from the airlock Door A57 is still fully operable and Cida of door'A57. Door A57 is a capable of performing its intended flordmode, airlock, and fire door function as the result of Public Safety loc ted between the service building personnel being stationed at the Cnd the auxiliary building on elevation auxiliary building side of the door.

690 feet.

This person has radio communication with the person stationed at door A56 to insure A56 closed prior to opening A57. The probability of an occurrence or the consequences of an accident are not increased. The margin of safety as defined in the basis of any technical specification is not decreased. This TACF is scheduled to be cleared when work on ECN-LS855 is completed.

c* TACF 0-83-0347-057 Lifted wires from terminals 1 and 7 of Lifting the wires on the CT ground d vices 996962 and SE6962 on panel 28 protection timers does not affect any Cnd wires from terminals 1 and 7 of safety-related equipment. The safety d:vice 100642 on panel 33 (CT ground basis of the technical specification is protection timers). This was done to not altered. This TACF is scheduled to prCvent false tripping of the bus be cleared when work on ECN-L5395 is c:ction. This change involves the completed.

CC:cciated electrical systems.

co TACF: 0-83-0399-077 Jumpered out the conductivity probe on The condensate demineralizer waste tha condensate domineralizer waste evaporator water heater is non-CSSC.

Ev porator building water heater. This This TACF is scheduled to be cleared W 3 done because conductivity probes do when work on ECN-L6984 is issued and not work well with domineralized water, completed.

ThJ heater would never come on, co TACF: 0-83-0366-295 Nov:d the card reader at door A56 to The intericcks of door A56 and A57 are thJ clerk monitor's table located defeated CTACF 0-82-0315-910) and cpproximately 20 feet north of door Public Safety personnel are located at f.56.

both doces to ensure operability of the airlock. Locating the card readers at the clock monitor's table provides increased access control. The margin of safety as defined in the basis of any technical specification has not been decreased. This TACF is scheduled to be cleared when work on ECN-L5855 is completed. ;

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IDESCRIPTION' SAFETY

SUMMARY

.co TACF: 0-83-0375-030

, Ducted-in a temporary air conditioning These modifications were made in the Lunit.into'the elevation 690 feet service building which is a non-seismic ltundry room supply duct. Provided structure with-no safety-related

' power from a welding outlet and cooling equipment. The: potable water system is Lwatcr from the existing supply source.

also non-safety related.-No safety-related function or feature covered by the plant technical specification has been directly or indirectly affected by this change.

This TACF is scheduled to be cleared post Unit 1 cycle 3.

l co TACF: 0-83-0400-030 Installed a new Foxboro B34DP-HNAl-C Controller action will remain the same D/P transmitter and controller, and static pressure will not change

, Connected the output of the_. controller from the negative _ quarter inch of water to both FM-30-154 and FM-30-273. This pressure. None of the instruments involves the auxiliary building general involved are technical specification or' Cxhrust fans.

CSSC instruments. This TACF is scheduled to be cleared when ECN-L6027 is completed, post unit 1 cycle 3.

00 TACF: 0-B3-0411-241 Documented the addition of vents,

.This change uill increase the h: ters, and two thermostats to common reliability and availibility of the Ctotion service transformer

'C'.

offsite power system. The probability of an occurrence or the consequences of an accident are not increased.

The margin of safety as defined in the technical specification has not been decreased. 'The TACF will be cleared upon completion of ECN-LSSB7,' post' unit 1 cycle 3.

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02/22/C7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY SUNNARY co TACF: 0-84-0007-031 0 10-inch water column manometer was 0-PDT-31A-14A controls the control mounted on panel HV-101 and connected building pressurization fan vanes. On a in. parallel with 0-PDT-31A-14A. This control ht a lding isolation signal, the wa3 done to allow accurate monitoring control.

tding pressurization fans cf the control building pressure with isolate ft ;m the-main control

. respect to the outside, room (NCR). The installation of-the manometer does not affect control room habitability. This TACF will be cleared when work on ECN-LS1HO.is completed.

Co TACF: 0-84-0068-062 Substituted model EVHS-7-5X-12H-IS (gas The new pumps will provide the same ctripper pumps 0-PHP-62-155 and function and are built to the identical ~

2-PHP-62-153) for model EUH-15X-12H-IS. quality assurance standards as the original. This TACF is scheduled to be cleared when work on ECN-L6362 is completed.

co TACF: 0-84-0084-059 Routed stainless steel tubing in the The condensate domineralizer system is condensata domineralizer. waste a nonsafety-related system located in a cvsporator building from the nonseismically qualified structure, rceirculating pump room to the existing This TACF is scheduled to be cleared

-c mple sink. The tubing will include a when work on ECN-L6362 is completed.

Ccmple line.from vendor valve #U204, a fluch'line from the domineralized water lina and a drain line from the sample oink to the existing drain funnel.

-00 TACF: 0-84-0101-025 R: moved an eroded section of the 2-inch The line that was isolated is the raw rCw water line and plugged the tes just service water line to the ERCW pumping up Ctream of 0-ULV-26-570 to isolate station. The fire protection system

-th3 line from the main fire protection remains fully operable with this line

'h:cder.

isolated. The margin of safety as defined in the basis of any technical specification is not reduced. This TACF is scheduled to be cleared by DCR-L2155, post unit 2 cycle 3. +

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9 "02/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS

-DESCRIPTION SAFETY

SUMMARY

Go TACF: 0-84-0103-077 Removed the basket from the primary The probability of an occurrence or the watcr filter upstream of 0-77-SS3 to consequences of an accident or pecvent clogging during resin transfer. malfunction is not increased.

The margin of safety as defined in the basis of any technical specification is not decreased.

This TACF will be cleared when work on DCR-2147 is completed.

c' TACF: 0-84-0110-079 Drilled a hole in the lack spring rod, The probability of an occurrence or the on the burnable poison rod assembly consequences of an accident or tool, to accept a spacer and cotter pin malfunction is not increased. The to prevent rod binding which inhibited margin of safety as defined in the proper tool operation.

basis of any technical specification is not decransed.

co TACF: 0-85-0004-236 R: moved a 70-amp breaker from the This is a non-CSSC change. The margin 400-volt turbine vent board 1A, of safety as defined in the basis of compartment SE, and placed it in the any technical specification is not 400-volt auxiliary building common decreased.

This TACF is scheduled to board motor control center

'A',

be cleared when work on ECN-LSSSS is c:mpartment BC2.

This was done to feed completed.

thJ 125-volt vital battery board ch:rger.

A replacement breaker for the turbine building board has been ordered by the Division of Nuclear Engineering (DNE).

co TACF: 0-85-0022-241 N d3 the wiring changes necessary to This a non-CSSC change and there are no p1Cce the new Westinghouse cts in effects or limitations.

This TACF will Ccevice on PCBS84 in the 161-kV be cleared when an ECN is issued and twitchyard.

completed.

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10 02/22/C7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

Co TACF: 0-85-0040-062 R:placed the bolts on boric acid filter The bolts that were used for

'O' with ASTM A193-Grade-B7 bolts.

replacement do not have material traceability. The original bolts were badly corroded and required replacement to make the filter operational until the correct bolts for the environment can be installed. The new bolts, though lacking traceability, are of the same material as the original bolts. The probability of an accident that is not already addressed is not increased.

This TACF is scheduled to be cleared when work on ECN-L6596 is completed.

00 TACF: 0-85-0055-410 R moved the glass cover from the The cover had to be removed to allow

.intrelock defeat switch for daar C14, access to the emergency interlock 01cvation 685 feet.

release button.

This will prevent personnel from being trapped in the auxiliary instrument roon during a carbon dioxide dump.

This does not change the as-designed operation of the system or its intended function.

00 TACF: 0-85-0073-077 Installed a screen between the flange The screen assembly is constructed of Icading to the sensor bellows for the same material as the existing LT-77-98 on spent resin storage tank.

flange and will not degrade the present Thio screen will prevent any resin system. Addition of the screen will b Cds from entering the sensor housing increase the margin of safety by Cnd getting between the convolutions.

Keeping resin beads away from the sensor bellows, co-TACF: 0-85-0077-039 Changed the carbon dioxide central unit Changing the setpoint from 0 to 1 psig rcfrigerant LO pressure switch will not increase the probability of an (0-PS-39-378) setpoint from o psig to 1 accurrance or the consequences of an paig. O psig is not a practical accident. This change does not involve C;tpoint value and switch repeatability a technical specification instrument.

c0nnot be established at this setpoint. This TACF is scheduled to be cleared when a category

'D' FCR is issued and a follow-up ECN is issued and completed.

Page No'.

'02/22/C7.

-11 SEQUOYAH NUCLEAR PLANT

1986~NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS

. DESCRIPTION' SAFETY

SUMMARY

c6~TACF:'0-85-0079-317 Rolocated card. readers 118-and 119 from This TACF'is non-CSSC. The probability

' door A152 to the table established by.

of an occurrence or the consequences of

.-Public Safety for. control of access to an accident is not increased.- The unit.1 containment on elevation 734 margin ~of safety as defined in the FCOt. ' Relocated card readers 146 and basis of any technical specification 147-from door A25 to the table has not been decreased.

This~TACF will-

.cct0blished by Public. Safety for be cleared when work on DCR-P1295 is

_ control of access to unit-1 containment complete.

en olevation 690 feet.

"00.TACF: 0-85-0090-234 LIn talled non-QA Raychem parallel heat The probability of an occurrence or the trOca on the sense line to the baric consequences of an accident previously

<ccid evaporator

'A' LIC-62-178 as a evaluated is not increased because the

'r placement for the existing Therman heat trace being installed is more series-heat trace. Bypassed the Thermon reliable than the original heat trace.

OtOpdown transformer and installed No new accident or malfunction is sufficient length of heat trace to created and the margin of safety as cdrquately heat the sense line near the defined in'the basis of any technical t nk.

specification is not decreased.

The TACF will be cleared upon completion of ECN-L5599.

00 TACF: 0-85-0097-234-R:placed Thermon series heat trace with The parallel heat trace has the same non-QA Raychem Chemlex semi-conducting wattage as the original heat trace and Calf. regulating heat trace.

This is more reliable. This change will not change was made on heat trace circuits increase the probability of an SOP and SOS on 1A-A baric acid transfer occurrence or the consequence of an pump.

accident.

The margin of safety as defined in the basis of any technical l

specification is not reduced. This TACF

~

is scheduled to be cleared when j

DCR-2182 is approved and work on it is completed, l'

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LPage No.

12,

0E/22/B7 SEQUOYAH NUCLEAR PLANT

'1986 NRC ANNUAL OPERATING REPORT

' FACILITY-CHANGES - TEMPORARY ALTERATIONS

.....b..b..

co TACF: 0-BB-0005-079

Reworked _the fuel transfer tube wafer-The impact of this change has been valve manual actuator to allow better evaluated and no new accident or Cnd more reliable valva operation.

malfunction was created. However, the auxiliary building secondary containment enclosure would-be affected-if work was being performed while-either unit was operating.-The TACF.is scheduled to be cleared prior to either unit entering made 4.

00 TACF: 0-06-0018-031 Ficx home was added to each air outlet-The system is not functionally changed in the plant computer room to lower the or adversely affected. No cir discharge points to approximately safety-related system covered in any

.cight feet above the room's floor. This plant technical specification was w 0 done to provide increased cooling effected. The TACF only lowered the air sto the safety parameters display system discharge points of the balancing-computer.

dampers. This TACF is scheduled to be cleared when work on DCR-P2281 is completed.

C' TACF: 0-06-0019-317 Provided temporary mobile office space No CSSC equipment is affected by this

'with power provided from the office and TACF. This change is independent of pow r stores facility. This was done to safety-related equipment. The margin of hauze additional personne1' required for safety as defined in the basis of any picnt startup, technical specification is not decreased.

This TACF is expected to be cleared by November 15, 1987.

00 TACF: 1-79-0348-040 Connected a clock to the contactor. coil This TACF is non-CSSC and will be for evaluation of total flow from the cleared by DCR-2028.

ctstion sump. This involves the station drainage system.

Page No.

13 02/22/L7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

c3 TACF: 1-80-0152-079 In talled temporary air lines to the The temporary lines are rated to unit 1 manipulator crane gripper withstand the normal pressures and the C:sembly.

gripper fails closed if the air supply is lost. The probability of an accident is not increased. This TACF is scheduled to be cleared post unit 2 cycle 3.

CO TACF: 1-80-0576-062 Adjusted the heat trace resistance on The adjustment to the resistgance to the sample line to the boric acid provide more heat will prevent the Cv porator level transmitter sample line from solidifying thereby (1-LT-62-178) to provide more heat.

operating as designed and evaluated.

The probability of an occurrance or the consequence of an accident is not increased by this change. This TACF will be cleared when DCH-2182 is completed.

co TACF: 1-80-0625-068 R moved the high level and high Removing these trips does not affect pr csure trips from the breaker for the total heater requirements of peccsurizer heater 1C. This was done to Technical Specification 3.9.9. This Cinimize the opening and closing of the TACF in scheduled to be cleared when 6.9 kV shutdown board breakers caused work on ECN-L5902 is completed.

by fluctuations of pressurizer level switches. This change involves the rc:ctor coolant system.

co TACF: 1-81-0011-077 Rzplaced

'A' cask decontamination tank No technical specification is involved.

pump with a temporary replacement pump. This equipment is used to handle low Thio was done to repince lost capacity level radwaste and is contained within until a new pump is received and the auxiliary building. This is in talled.

non-CSSC piping and equipment. This TACF is scheduled to be cleared when work on ECN-L5916 is completed.

Page No.

14 02/22/87 SEQUDYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY SUNNARY co TACF: 1-81-0215-055 Installed screens on 1-N-21 The function and qualification of the (Cnnunciator and sequential events annunciators will remain the same. In rcc rding system) to increase cooling addition the reliability of the Cnd reduce annunciator failures, annunciators will be enhanced by this change. The margin of safety as defined in the basis for any technical specification has not been reduced since none are affected. This IACF is scheduled to be cleared when work en ECN-L6006 is comoisted.

co TACF: 1-81-0467-062 Add:d a flange and 90 degree pipe with No safety system has been affected that o chut off valve to the boric acid would lessen the ability to contain cv porator bottom sample point to allow radioactive liquid. The only condition c pling without spilling boric acid.

changed was the made of sample, and the possibility for an accident or malfunction not previously evaluated was not created. This TACF is scheduled to be cleared when work on ECN-L5739 is completed.

co TACF: 1-81-05d0-077 Inntalled a 150-gallon per minute pump Increasing the cask decon tank pump in place of two 10-gallon per minute flow rate does not affect the basis of c Ck decantamination tank pumps. This any technical specification. This TACF will allow faster processing of the is scheduled to be cleared when work on w tcr in the cask decontamination tank. ECN-L5916 is completed.

00 TACF: 1-82-0062-002 R moved the hotwell pump motor trip During accident conditiors, safety CCp; ration relay fuses so the hotwell injection and high steam generator pump will continue to run during a level, and folicwing a reactor trip, C f ty injection signal or a high steam the feedwater isolation, regulator, and g:ncrator level, bypass valves close and the main feedwater pump turbines trip. The hatwell and condensate booster pumps could not overcome the steam generator pressure above or equal to 620 psig if the valves failed to close. The safety analysis report was evaluated for couldown and it was determined that no other malfunction or consequences should occur. This TACF is scheduled to be cleared upon completion of UCR-1S05.

i

'Page No.

15 02/C2/C7 SEQUOYAH NUCLEAR PLANT-1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

CO TACF: 1-82-0103-234 Installed temporary heat trace on the The installation of heat trace on the c ndensate domineralizer caustic lines caustic lines prevents plugging, to prevent plugging.

therefore, no margin of safety is reduced. This TACF is scheduled to be cleared when work on ECN-LS388 is completed.

co TACF: 1-82-0107-090 R: routed tubing to and from containment Correct routing of the tubing will purge radiation monitors 1-RM-90-130 allow the instruments to perform as Cnd 1-RM-90-131. The tubing had been they were designed. This TACF is routed incorrectly, scheduled to be cleared when work on ECN-LS894 is completed.

Co TACF: 1-82-0140-090 Ch nged FA-90-2128 to actuate only when The alarm will be actuated during loco of sample flow occurs during the applicable time periods. The time the turbine building sump pumps probability of an occurrence or the tra pumping. This will* enable the consequence of an accident or op:rator in the main control room to malfunction of equipment important to datcrmine if sample flow is lost.

eafety has not been increased. This TACF is scheduled to be cleared when work on ECN-LSB22 is completed.

co TACF: 1-82-0154-062 Substituted Allis Chalmers pump in The boric acid evaporators are handling picce of the existing Raychem pumps fcr radioactive materials but are contained baric acid evaporator

'A' concentrate in their own room in the auxiliary pu2ps 1 and 2. Existing Raychem pumps building. The system has a maximum tra no longer available. The Allis operating pressure of 12 psig. Since Chalmers pumps and associated piping this is the rupture disc value, non-QA cro non-CA.

pumps and piping are sufficient. This TACF is scheduled to be cleared when work on ECN-L6217 is completed.

Page No.

10 02/ 2/L7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

J c' TACF: 1-82-0168-062 Inztalled a non-CSSC valve bonnet and a The flow medium is separprod from the Grinnel 1 and 1/2-inch diaphram valve bonnet by a diaphragm. The bonnet has in class D piping of the chemical and the same pressure rating and is valume control system (1-FCU-62-170).

functionally the same design.

Traceability of the valvo is not availabia. This TACF Ts scheduled to be cicared when work on ECN-L6217 is cumpleted.

co TACF: 1-82-0213-062 Pervided power supply for now baric Ninor flux conduit rarcuting was ccid evaporator

'A' concentrator pump required to connect the lands to the motors 1 and 2.

pumps. The possibility of an accident or malfunction of a different typo than previously avaluated was not cr' anted.

s co TACF: 1-82-0214-062 Installed heat trace on the new baric The temporarg heat trace'will ccid evaporator

'A' concentrato pumps adequately maintain tempHenture on the piping.

suction and dischargo piping to innuro thoro is no baron precipitation or plugging in the lino. This TACF is scheduled to be cleared when work On ECN-L6217 is complotod.

co TACF: 1-02-0290-079 Installed an underwater TV camera Thu installation of this Wast'tnghousa sy3 tem on the unit 1 manipulator crano. Video system will not denradd a1y plant safety system or function. Thir/ TACF is schedulod to be cinarod when 93r:4 on DCR-1718 is complatud.

Co TACF: 1-02-0242-062 Drilled and tappad the boric acid The structural integrity of the nhaft Cv porator concontrator pump 1 and 2 has boon incrooned by onlarging the ch:fts at the broken location and shaft size. The now configura;1on in as in talled an enlarged shaft extension good or bottor than the or10tnni (3/8-inch to 9/16-inch). Installed a configuration. This TACF in schudulod k;yway on the new shaft extension and to be cleared when unre on ECN-L6H17 is drilled out and installed a keyway in completed.

thJ 1mpo11er.

Ptge No.

17-GE/EE/C7 SEQUOYAH NUCLEAR PLANT 1986'NRC ANNUAL OPERATING REPORT FACILITY CHANGES -. TEMPORARY' ALTERATIONS p

i-DESCRIPTIDN SA'FETY SunnARY

\\

4

~

co TACF: 1-82-0266-077 Installed a:2-inch bull home between This change does not adversely affect

.the wasta evaporator feed pump any plant-safety sQ1tems. The margin of discharge and the primary water header safety as defined ih the basis for any section on elevation ESS feet, and used technical specification is not reduced, cn isolated section of the primary

-This'TACF is scheduled to be cleared

. W ttr hearier to provide a' flow path to when work on ECN-L5911.is completed.

'" -the temporary RAD D.I. in the auxiliary This. change allows processing of xbuilding cask loading area.-

radweste water through the temporary k

rad *D1 and allows the use of the CDWE distillate tank in the flow path. No additionmi-limitations or actions are required as the resuit of,this change.

l?O.TACF: 1-8E-0330-006 Removed flow transmitters 1-FE-6-107 These modifications do not affect.the Cnd 1-FT-E-107 for installation and use function of the naisture separator cf Westinghouse turbine bench mark test reheaters (MSR) or"the e 3 heater drain equipment.

tank. The piping is no'risaismic and is t

located in the turbine building which is nonseismic. These systems arp not needed to mitigate an accident. The

'l loss of the MSR or # 3 heater drain

(

tank will not unduly challenge any safety system or Jeopardize the safe S

shutdown of the plant. These systems i

are not covered by the basis of,any technical specification. The margin of safety as defined in the basis of any technical specification is not reduced.This TACF is scheduled to be cleared upon completion of ECN-L5696.

r.-

co TACF:( i-82-0341-U1'3 In:talled a comparary claap to the The small weialt added te thu HCP spray.

0-irt.h fire protection hood I-beam for shimid I-beam will not invalidate its accdringta retractable lifeline over seismic support qualification! This CCch of the unit 1 RCr motors, device will not affect any technical specification and will be cleared when-i*

work on DCR-1711 is completed.

't in L

b

~

y.

(Page No.

18 4 02/22/G7-SEQUOYAH NUCLEAR PLANT

-1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS ~

DESCRIPTION SAFETY

SUMMARY

[

i 00 TACF: 1-82-1001-090

'Chsnged the 1.by 1-inch NAI crystal Although the range and sensitivity of d2tcctor in RE-90-104 to a 1/2-by RE-SO-104 is specified in table 11.4-1 d

-1/2-inch crystal' detector.. The original of the FSAR, the 1-by 1-inch datector cructal was.too sensitive for the maintains a count rate in.the upper Cpplication.

region of the radiation analyzer during normal plant operations and would not be as useful for leakage detection as ths 1/2-by 1/2-inch detector. The margin cf safety as defined in the basis of any technical specification is not reduced since 1-NM-SO-104-is a non-technical specification instrument-and has been svaluated to be non-CSSC.

This TACF is scheduled to be cleared when work on DCR-1SSG is completed.

oo TACF: 1-83-0004-067-Ch nged the setpoint:af 1-PDIS-67-490 The probability or consequences of an Cnd 491 E/F, F/E on essential raw accident is not increased by this cooling ' dater headers A and B to 6 change. This.TACF is scheduled to-be

'pzid. This was done to permit proper cleared when work on ECN-LSS12 is op; ration of the essential raw cooling completed.

WOtcr strainer backwash.

00 TACF: 1-83-0007-062

-R:placed inadequate permanent heat The boric acid evaporators are not trccing on

'B' boeic acid evaporator safety-related equipment. This TACF is I

'1cval transmitter sense line with new scheduled to be cleared post unit 2 i

coif limiting heat tape. This prevents cycle 3.

plugging of the sense line.

00 TACF: 1-83-0026-0S0 Ran temporary hypochlorite lines from The lines were constructed of CPUC and 1

I ths ERCW pumping station to the ran on top of the ground. This hypochlorite building.

temporary condition does not effect safety-related equipment. This IACF is scheduled to be cleared when work on ECN-LSS6B is completed.

i e

i-f

'l i.'

24-f

~

..h.___--,._._..._,m.. _, _.. _ ~.

_ _ - - _ - -. -.,,, ~, - -

L 19

' ~

PagnLNo.

102/22/07 SEQUOYAH NUCLEAR PLANT 1986-NRC ANNUAL OPERATING REPORT FACILITY CHANGES -- IEMPORARY ALTERATIONS

. DESCRIPTION SAFETY

SUMMARY

=co TACF: 1-83-0367-245 Inctalled s jumper to elininate open This change will not alter the

. door. detection printouts for functionality of.the doors as a' fire

' continuously-monitored door ASE.

barrier. This change-does not decrease the margin of safety as defined in-the basis of any technical specification.

This TACF is scheduled to be cleared when work on ECN-LS855 is completed.

Co TACF: '1-84-0001-062 7qDisconnected'Thermon heat trace on the.The parallel heat trace has the same j srcondary-sids of the heat trace wattags as tha original heat trace and

_ " trcnsformer and connected Chemlex heat is more reliable. This change will not -

trKce to the primary side of the increase the probability of an

~trcnsformer on-boric acid evaporator occurrence or the consequence of an prckage:'B' accident. The margin of safety as defined in the basis of any technical specification is not reduced. This-TACF f

is scheduled to-be cleared when work on ECN-L6217 is completed.

C*TACF: 1-84-0002-062 Disconnected Therman heat trace on The. parallel. heat trace has the same boric acid evaporator package

'B' and wattage as the original heat trace and rgplaced with Chemlex heat trace.

is more reliable. This change will not increase the probability of an occurrence or the consequence of an accident. The margin of safety as defined in the basis of any technical specification is not reduced. This TACF is scheduled to be cleared when work on ECN-LE217 is completed.

l.

b l

1C* TACF: 1-84-0039-031 Modified fire damper 0-31C-1744 so that The damper was installed according to j

-it would fit properly inside the vendor requirements and an acceptable-ductwork._The modification consisted of post modification test was performed.

chartening the frame and one side of The damper functioned properly and this L 'two curtain damper sections, modification does not affect the j

acceptability of this damper as a functional fire damper. This TACF will l

be cleared when work on ECN-LS847 is completed.

Pcg:2.No.-

20:

02/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING. REPORT FACILITY CHANGES - TEMPORARY ALTENATIONS

. DESCRIPTION SAFETY

SUMMARY

co.TACF:-1-84-0040-058 Cut a 2-inch diameter. access hole in This TACF is non-CSSC and is scheduled

.th3 bottom of the unit 1 generator bus to be cleared by ECN-L6664, work plan links to. allow access to the bus link 12158.

bolts. This change involves the gLn;rator bus cooling stystem.

c' TACF: 1-84-0052-085 Mavrd cable 1RR292 CRPI F2), from Connection 95 has a high resistance and p2nstration 25, connection 95 to this change allows RPI-F2 to operate

. connection 94. Moved cable 1HR295 (RFI properly. The probability of an F4),- from connection Si to connection occurrence or tne consequences of an 95. -

accident or malfunction is not increased. The margin of safety as defined in the basis of-any technical specification is not reduced.-FCR-2613 has been issued and this TACF will be cleared when an ECN is issued and completed.

00 TACF: 84-0057-085 Raplaced cable 1RR332 (RPI H12) with This change does not increase the csble 1RR346 CRPI K4) and replaced probability of an occurrence or the c3ble 1RR260 CRPI C9) with cable 1RR278 consequences of an accident-or CRPI D10). These cables were replaced malfunction. The margin of safety as Ct the reactor head and rerouted inside defined in the basis of any technical tha RPI instrument rack. Cables 1RR346 specification is not reduced. This TACF Gnd 1RR278 are now RPI H12 and RPI CS, is scheduled to be cleared when DNE rsspectively.

issues an ECN and work on the ECN is completed.

- TACF: 1-84-0065-050 Movsd wire No. 44 from normally closed This is non-CSSC and does not effect contact pin No. 4 to normally open the margin of safety as defined in the contact pin No. 3 located in the basis of any technical specification.

hypochlorite control panel. This was Electrical maintenance has issued don 2 to allow power to the hypochlorite FCR-3669 and they are waiting for UNE injnction starters.

to issue an ECN. This TACF will be cleared when work on the ECN is completed.

t ~

,PagJ No.

21-02/22/07 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

0* TACF: 1-84-008'l-062

<In:talled a thermocouple lead wire from Installation of a thermocouple lead Etha junction-box of each charging _ pump wire from the. Junction box terminal Ector CIA-A and 18-B) to a location blocks to an area outside the C-zone

.outside the C-zone.-This change was will not increase the probability of.an

' mad 2 in order to monitor motor bearing occurrence or the consequences of an tcmperatures.

accident or degrade the margin of

? ~

safety as defined in the basis of any technical specification. This TACF is scheduled to be cleared when ECN-L5059 is issued to 'hardwire' these thermocouples to a plant computer.

00 TACF: 1-04-0107-003 Rsmoved the-0.8-amp fuses from the This is non-CSSC and does not decrease 400-U turbine MOV board 1A, compartment the margin of safety. This TACF is 118 and replaced them with 2.0-amp scheduled to be cleared when work on funss. FCR-1756 added a motor heater to DCR-1633 is completed.

tha. circuit which blows the 0.8-amp fuzzs.

00 TACF: ~1-85-0006-003 Rrmoved hand controllers from MCR panel The only safety function of.the startup 1-M-3 and replaced with level bypass valves is that they close within indicating controllers. This was done 8 seconds of receiving a steam to allow =the operators to have generator high level signal. This cutomatic control of feedwater during function will not be affected by this

'otartup.

TACF. None of the trip functions associated with the steam generator water level will be affected; all trip functions will be available to maintain the unit within its design basis. The startup bypass valves are not covered by any technical specification and this TACF is limited to the controllers for these valves. The margin of safety as defined in the basis for any technical specification is not reduced. This TACF is scheduled to be cleared when work for ECN-L6193 is completed.

1 PagJ No.-

22 02/22/87-

",. 4 SEQUOYAH NUCLEAR PLANT 1986.NRC ANNUAL OPERATING REPORT' FACILITY CHANGES - TEMPORARY ALTERATIONS.

DESCRIPTION SAFETY

SUMMARY

co TACF: :1-85-0048-057 AddId a clamp-on current transformer to This:is non-CSSC and does not decrease-th3 high. side of the unit 1 main the margin of safety.-This.TACF is g2n2rator neutral grounding scheduled to be cleared when electrical

'trensformer. This was done to provide maintenance submits a maintenance information about radio frequency waves request to make the change permanent.

g:n2 rated by.the generator._This information can be used to detect-crcing in the generator. This change involves the associated-electrical tystems.-

00 TACF: 1-85-0059-234 Rsplaced_the Therman heat trace on the The Raychem heat trace performs the boric: acid transfer pump suction line same function as the Thermon and is b3 tween 1B-B and 2A-A, with non-QA more reliable. No margin of safety sus Raychem Chemlex auto regulating heat defined in the basis of any technical trcce.

specification is. reduced.

This TACF is scheduled to be cleared when work on DCR-2182 is completed.

i.

00 TACF: 1-85-0060-234 Ch2nged heat _ trace circuits 87P and 875 The wattage of the auto regulating heat i

-on'1B-B boric acid' transfer pump from trace is equal to or greater than the tha existing.Therman series heat trace wattage of the heat trace being to Raychem Chemlex parallel auto replaced.

A post maintenance test was rIgulating heat trace.

Changed the performed to insure the pump is wiring on current sensing relay to maintained at a temperature that is Eccomodate the new heat trace.

equal to or greater than 170 degrees F.

The auto regulating heat trace is more reliable and will decrease the chance of an accident.

This TACF is scheduled to be cleared when work on DCR-2182 is completed.

s 0

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JPOC3 No.

23

-02/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES 1-TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

IC* 'TACF: 1-85-0063-094 Ralocated the termination points for Relocating the termination point for

' field cables INM 720 and INM 1180 in the two field cables does not affect tha junction box on panel 1-L-BB from the operability of.the system. This point 54 to spara point SP-2. The does not decrease the margin of safety

_ Junction box had a broken screw which as defined in the basis of any prcvented. termination. This involves technical specification.

This IACF is tha in-core flux detectors system.

scheduled to be cleared when work on ECN-LS1BS is completed.

Co TACF: 1-85-0054-046

. Changed the setpoint of pressure The setpoint chanpe is in the switches 1-PS-95-5A,

-SD,

-30A, and conservative direction. The pump that

-30D from'115 psig decreasing to 140 is not running will start earlier on a

_paig decreasing. These setpoints are on low discharge oil pressure signal from tha.feedwater control system.

the pump that is running.

This does not decrease the margin of safety.as defined in the basis of any technical specification.LThis_TACF is scheduled to be cleared during unit 1 cycle 9.

1 o* TACF: 1-85-0055-025 Installed a Chicago fitting with a pipe This condition does not cause any tca on the discharge of vent valve limitations on the raw service water 536. One leg of the tee has a hose system. As the ultimate heat _ sink installed which is going to the ERCW temperature approaches technical pump station floor. drain. The other leg specification limits this method of i-.his an RTD temperature probe installed measurement provides a more accurate i

cnd connected to a Fluke 2180A instant reading on an AI-31 (M&TE l -tgmperature indicator. ULU-25-635 will' program) instrument. This TACF is ramsin open with the runoff going to scheduled to be cleared when ECN-LS848

-thm floor drain.-

is completed, post unit 2 cycle 3.

00 TACF: 1-85-0067-025 Installed a Chicago fitting with a pipe This condition does not cause any tra on ULU-25-633. One leg of the tee limitations on the raw service water h2s a hose installed which is going to system and emergency raw cooling water tha ERCW pump station floor drain. The system. As the ultimate heat sink

'othsr leg has an RTD temperature probe temperature approaches technical i

installed and connected to a Fluke specification limits this method of i

2180A temperature indicator.

measurement provides a more accurate

.ULU-25-633 will remain open with the instant reading on an AI-31 CM&TE l

runoff going to the floor drain.

program) instrument. This TACF is scheduled to be cleared when ECN-LS898 is completed, post unit 2 cycle 3.

l

P;giINo..

24 02/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES -. TEMPORARY ALTERATIONS

. DESCRIPTION SAFETY

SUMMARY

co.TACF: 'l-85-0069-013

' Lifted leads 225A and B an'd 226A and B This TACF is non-CSSC and and does not-Cnd placed an end-of-line device across decrease the margin of safety as ccch. The Pyrotronics module 2N-30 was. defined in the basis of any technical

.Oltcred to remove zones 454 and 455 in specification. Electrical maintenance tha new office and power stores must issue a work request-to-return

'fccility from service to prevent pyrotronics module 2N-30 to its cpurious alarms.

original configuration before this TACF can be completed.-

- TACFi 1-85-0070-030

-This TACF' replaces and adds to work None of the instruments involved are parformed on TACF 0-83-0400-30. This technical specification or CSSC

.TACF has disconnected the output.from

' instruments. This TACF is scheduled to both FM-30-277A and FM-30-168A from I/P be cleared when work is completo on modules FM-30-277 and FM-30-168

'ECN-L6027.

raspectively. Installed a new Foxboro

-834DP-HNAl-C DP transmitter and controller and connected the output of ths controller to both FM-30-168 and FM-30-277.

4 co TACF: 1-85-0084-079 Allowed the flexatallic gasket with a The flexatallic gasket pressure nonstainless steel centering ring to retaining capability is unchanged. The rcmmin installed in the wafer valve spool piecegis consistant with the cpool piece during unit 1 cycle 3 fuel design of the system and a catastrophic movsment. Also, allowed the spool piece failure of the spool piece is not to remain installed during fuel likely. The probability of an accident movement.

is not increased. FCR-4788 is approved and DNE is working on an ECN which will clear this TACF.

00 TACF: 1-85-0085-317 Walded a pad eye Clifting lug) tc the The pac. eye is used to lift the valve

'Embrdded plate above 1-FCV-63-157.

operator and will have no attachments during plant operation.

The pad eye has no effect on plant equipment or seismic integrity and is used for maintenance rigging purposes only. This TACF is scheduled to be cleared during unit 1 cycle 3.

4

=. -

...-L -^

. :L

1

.Pzg3 No.

25

O2/22/87 SEQUOYAH NUCLEAR PLANT i

1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

co TACF: 1-85-0088-062 In2talled compression fittings in the The compression fittings does not 3/8-inch stainless steel tubing between degrade the connection between the thJ bottom of beric acid evaporator

'A' evaporator and the level transmitter.

cnd 1-LIC-62-178.

There is no increase in the possibility of an accident. This TACF will be cleared during unit 1 cycle 3.

c' TACF: 1-85-0091-030 R2placed Agastat model 7012 PH timer The new 7012 PF relay meets the 10 Crcnge 3 to.30 minutes) with an Agastat minute. plus or minus 1 minute. deiau modal 7012 PF timer Crange 1 to 10 start time requirement of the technical minutes) This timer starts the specification and provides better containment air return fan 10 minutes assurance that the plus or minus 1 (plus or minus 1 minute) after a phase minute tolerance can be maintained. The B isolation signal.

margin of safety as defined in basis of any technical specification is not reduced.

o* TACF: 1-85-0092-026 Tcck welded the yoke to the bonnet in The valves will pass post maintenance four places approximately 90 degrees testing CSI-166.6 and SI-158.1) of cpart on FCU-26-240 and FCU-26-243.

SUMMARY

P

- TACF: 1-86-0006-068 R21ocated 1-TE-68-67A from its existing Three spare. holes are provided.on.each hole to-a spare hole in the RID manifold. The' calibration of-the loop COnifold and' capped-the original hole.

and the response time of the element will not ba affected. The margin of safety as defined in the basis of the technical specification is not reduced.

This TACF is scheduled to be cleared when work on ECN-L6653 is completed.

- TACF: 2-80-0537-090

'Plcced a 0.22-microfarad capacitor The monitor still performs the same

~ccross the. buzzer of radiation monitor function and the margin of safety is

.2-RE-90-100 to eliminate spikes when not reduced. This_TACF is scheduled to th3 buzzer sounds.

be cleared when work.pn ECN-L5822 is completed.

00 TACF: 2'-81-2298-014 Wired an operator to valve 2-14-38 so The functions of the equipment affected that the. valve will not open on high by these changes remain in accordance differential pressure. System involved with the guidelines as previously is-the condensate.demineralizer, evaluated. No margin of safety is reduced. This TACF will be cleared when ECN-L5388 is completed.

00 TACF: 2-81-2341-087 Lifted-a wire on accumulator weight The accumulator weight indicating indicating switch 2-WIS-87-29 to switch has been declared defective by

dicsble the alarm input to annunciator Westinghouse. Defeating the alarm input 2-XA-55-SC/28.

from this system will not cause the probability of an occurance or consequences of an accident or malfunction to increase. This TACF is scheduled to be cleared when work on ECN-L6657 is completed..

_1

m

~ _

PigJ"No._

27 02/22/87' SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY' ALTERATIONS DESCRIPTI'ON SAFETY

SUMMARY

ic'ITACF: '2-81-2342-087 Lifted-a wire on-accumulator weight The accumulator: weight indicating indicating switch.2-WIS-87-22 to switch has been declared defective by dischle the alarm input to annunciator Westinghouse.. Defeating the alarm input 2-XA-55-EC/28.

from this system will not cause.the probability of an occurance or consequences-of an accident or-malfunction to increase._This TACF is-scheduled to be cleared when work on ECN-LSS57 is completed.

C*

TACF: 2-81-2343-087

. Lifted a wire on accumulator weight The. accumulator weight indicating indicating switch 2-WIS-87-23 to

~ switch has been declared defective by diesble the alarm input to annunciator Westinghouse. Defeating the alarm input 2-XA-55-SC/27.

From this system will not cause the probability of an occurance or consequences of an accident or malfunction to increse. This TACF is scheduled to be cleared when work on ECN-L6657 is completed.

l

- TACF: '2-81-2344-087 Lifted a wire on accumulator weight The accumulator-weight indicating indicating switch 2-WIS-87-21 to switch has been declared defective by i.

disnble the alarm input to annunciator Westinghouse. Defeating the alarm input

~2-XA-55-SC/27.

from this system will not cause the probability of an occurance or consequences of an accident or malfunction to increase. This TACF is scheduled to be cleared when work on l

ECN-L6657 is completed.

i.

- TACF: 2-81-2564-001 Addsd heat trace and insulation to the This is non-CSSC and no safety-related c;nse lines of 2-PT-1-132 to prevent system is affected. This TACF is froszing.

scheduled to be cleared following completion of work on the moisture separator reheaters, ECN-L1779, post unit 1 cycle 3.

1 l - - ---

f A

~

4 da e

~

J

--ra.

b

-,,L)-r P;g:1 No.

28 102/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

c* TACF:-2-81-2565-001-Addsd heat trace and insulation to the This is non-CSSC and no. safety-related conie lines'of 2-PT-1-122 to prevent system is affected. This TACF is r

frGszing.

scheduled _to be cleared following completion of work on the moisture-separator reheaters, ECN-L1779,. post unit 1 cycle 3.

-** TACF: 2-81-2565-001 AddId heat trace and insulation to the This is non-CSSC and no safety-related

_-cante lines of 2-PT-1-127 to prevent system is affected. This TACF is ferazing.

scheduled to be cleared following completion of work _on the moisture separator reheaters, ECN-L1779, post.

unit 1 cycle 3.

So TACF: 2-81-2581-055 R; moved the annunciation input to The cables lifted are de-energized and 2-XA-55-1C/35 from open breaker 26 of out of service. They were originally instrument power rack A to allcw intended to provide power to-panels

-tzating of the other annunciation associated with the part length control inputs to the window. Breaker 26 is for rod system which was never installed.

tha part length control rod drive This has no detrimental affect on any cystem which-is not installed at

. safety-related system and the SHquoyah Nuclear Plant.

probability of occurrence or the l

consequences of an accident are not increased. No technical specification requirements are affected. This TACF is scheduled to be cleared when work on ECN-L6350 is completed.

oo TACF: 2-81-2507-055 R moved the solid covers and installed This is non-CSSC and no margin of scrcens on panel 2-M-21 cabinets to safety as defined in the basis of any increase _ cooling and reduce annunciator technical specification is decreased.

)

failure.

This TACF is scheduled to be cleared when work on ECN-L6005 is completed.

__ _ _. -.. ~ _ -

_.. _ - - - - ~,. _.... _... - _ _

IPiga No,-

,29 02/22/87, E

SEQUOYAH NUCLEAR PLANT-1986 NRC ANNUAL OPERATING REPORT

. FACILITY-CHANGES - TEMPORARY ALTERATIONS DESCRIPTION' SAFETY

SUMMARY

0-TACF: 2-82-2039-002 RImoved the hotwell pump motor trip During accident conditions, safety

- tsp 2 ration relay fuses so the hotwell injection and high steam generatcr pump will continue to run during a level, and_following a reactor trip,

-COfcty injection: signal or a high steam the feedwater isolation, regulator, and g3ncrator level.

bypass valves close and the main feedwater pump turbines trip. The hotwell and condensate booster pumps 4

could not overcome the steam generator pressure above or equal to 620 psig if the valves failed to close. The safety analysis report was evaluated for cocidown and it was determined that no other malfuncticn or consequences should occur. This TACF is scheduled to

be cleared upon completion of DCR-1 SOS.

- TACF: 2-82-2050-068 R; moved the high level and high This change does not affect'the total l

_ prcnsure trips from the breaker for heater requirements of Technical pracsurizer heater 2C. This was done to Specification 3.4.9.

This TACF 1s minimize the opening and closing of scheduled to be cleared when work on

- E.9-kV shutdown board breakers caused ECN-L5902 is completed.

by fluctuations of the pressurizer inval switches. This change involves tha reactor coolant system.

Co TACF: 2-82-2077-090 Rsrouted tubing to and from containment Correct routing of the tubing will purge radiation monitors 2-RM-90-130 enable the instruments to perform as Cnd 2-RM-90-131. The tubing had been they were designed. This TACF is routed incorrectly, scheduled to be cleared when work on e

ECN-5899 1s completed.

- TACF: 2-83-2001-057 Chnnged the setpoint of 2-FDIS-67-490 The probability or consequences of an cnd 491 E/F, F/E on essential raw accident is not increased by this cooling water headers A and B to 6 change. This TACF is scheduled to be paid. This was done to permit proper cleared when work on ECN-L5512 is l

op2 ration of the essential raw cooling completed, watar strainer backwash.

l t

, = -.

Paga:No.-

30-l02/22/87 SEQUOYAH NUCLEAR PLANT

.2 4

1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES

. TEMPORARY ALTERATIONS

. DESCRIPTION SAFETY

SUMMARY

c* TACF: 2-83-2022-079 R2 Vised the Dillon load cell readout to Electrical maintenance has sent op; rate.in the fail-safe mode. This was FCR-5056 to the DNE to issue an ECN.

l don 3 to ensure safe operation.of the This TACF will'be cleared when the ECN

Cyntem in case-of a relay failure.

is issued and completed.

4 Jt Oo'TACF: 2-83-2036-062 L ft 2-PDT-62-8 and -47 installed and The alarm function is still within the in Service with the-top 25 percent of specified tolerance. This change does tha span slightly out of tolerance, not. adversely effect the operation of the reactor coolant pumps. No technical

. specification is affected. This.TACF is scheduled to be cleared when work on l

ECN-L6350 is completed 4

- 'TACF: 2-83-2047-062~

R2placed the old valve bonnet on The bonnet installed was identical to 2-FCU-62-170 with a new stainless steel the original bonnet. This TACF is bonnet that was non-QA material.

scheduled to be cleared when work on ECN-L6217 is completed.

'o* TACF: 2-83-5057-068

-Lifted cable 2CR432 which is normally With this change.there is no decrease connected to the spare A phase stator in the margin of safety. This TACF is RTD;5. Relocated cable 2CR362 from the scheduled to be cleared by ECN-L6664

normal'A' phase stator RID #2, which is when RTD repairs by Westinghouse are i

d:fsctive, to the spare A phase stator completed. This is scheduled for unit 2 RTD25.'This work was performed on cycle 3.

~rccctor coolant pump motor # 3 A phase Ototor.

i f

00 TACF: 2-84-0115-003 Pulled defective cabis 2PM4481 and This new route has been approved by DNE i

rCplaced it with a new cable.

This and will in no way effect safety.

No

'chinge rarautes cable 2PM4481 because safety-related systems covered by the

~

tha conduit it originally ran through plant technical specification will be

.wt3 full.

adversely affected by this change.

The margin of safety as defined in any technical specification has not been reduced.

This TACF is scheduled to be

[

cleared when ECN-Ld352 is completed.

I

=PZCO-No.

31~

02/22/87

( -

-SEQUOYAH NUCLEAR PLANT-1985 NRC ANNUAL OPERATING REPORT FACILITY CHANGES

. TEMPORARY ALTERATIONS

'DESCsiPTION SAFETY

SUMMARY

'C*-TACF: 2-84-2004-062 Installed _ temporary pressure gauges on With this change there is no decrease th3' inlet and outlet side of the boric in the margin of safety as defined in Ccid transfer pumps 2AA and 2BB and on the basis of any technical aboric acid filter

'B'.

This was done to-specification. This TACF is scheduled giva operations an indication of pump to be cleared when work on DCR-2182 is Cnd filter performance.

completed.

Go TACF:~ 2-84-2008-013 A txmporary-clamp was installed to the The small. weight added to the RCP spray S-inch fire protection hood I-beam for shield I-beam will not invalidate occuring a retractable lifeline over technical specification seismic support

-Ccch of unit 2's reactor coolant pump qualification..This device does not

motors, affect any technical specification and will be cleared when work on DCR-1711 is completed.

- TACF: 2-84-2010-062 R placed boric acid concentrate pump The function of the evaporator package (2-PMP-62-1SS,158) motors which were is to remove nitrogen, hydrogen, and-Crene Champump, with non-CSSC Allis fission gases and then concentrate the Chalmers model CSO.1-1/2 x 1 x 6 with weak boric acid solution for reuse.

dynImic' seal. This involves the Since this process is not important to ch:mical and volume control system.

safety, nor is it required to mitigate an accident, there'is no effect on equipment important to safety. This TACF is scheduled to be cleared when work on ECN-LS217 is completed.

i 00 TACF: ~2-84-2016-OS2 In2talled a thermocouple lead wire from There is no decrease in the margin of tha Junction box-of each charging pump safety with this change. This TACF is i

I motor (2A-A and 28-B) to a location scheduled to be cleared when work on outside the C-zone.-This was done to ECN-LSOSO is completed.

monitor motor bearing temperature.

i

F:Ca;No.

32 02/22/07-SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT FACILITY CHANGES - TEMPORARY ALTERATIONS DESCRIPTION SAFETY

SUMMARY

-co TACF: 2-84-2039-003 R moved hand controllers 2-HIC-3-3SA, The only safety function of the startup

-4BA, -90A, -103A and replaced them.

bypass valves is that they close within with level irdicating controllers. This 8 seconds.cf receiving-a steam

_w20 done to allow the operators to have generator high level signal. This tutomatic control of the feedwater function will not be affected: by this

-during startup.

TACF.-None of the trip functions associated with the steam generator water level will'be affected; all trip functions will be available to maintain the unit within its design basis. The startup bypass valves are not covered-by any technical specification and this TACF is limited to the controllers for these valves. The margin of safety as defined in the basis for any technical specification.is not reduced. This TACF is scheduled to be cleared upon j

completion of ECN-LS193 during unit 2 cycle 3.

4 "C

TACF: 2-84-2046-001 R placed the overspeed reset soleniod This is non-CSSC and is scheduled to be l-volve body on main feed pump turbine 2B cleared during unit 2 cycle 3.

with a larger orificed valve body part number 8320A1BS.

l l

oo TACF: 2-85-2007-030 Installed a non-qualified motor on Based on the safety evaluation, the 4

rC2ctor building lower compartment margin of safety as defined in the cooler fan 2A-A.

basis for Technical Specification 3/4.6.1.5 (Containment Air Temperature) l or any other technical specification is

~

not reduced. The cooler is not required to operate under accident conditions.

This TACF is scheduled to be cleared when DCR-972 is completed.

[

I i

LPigaLNo..-

33

' 0 2 / 2 2 / 8 7 --

.SEQUOYAH NUCLEAR PLANT

.1985 NRC ANNUAL OPERATING REPORT

. FACILITY > CHANGES - TEMPORARY ALTENATIONS DESCRIPTION SAFETY

SUMMARY

c' TACF: 2-05-2009-062

' I'n a t a l l e d xnon-QA Raychem Chemlex-The Raychem type heat trace is more p2rc11e1 type heat trace on 2A-A boric. reliable and the baric acid. transfer

~

ccid transfer pump in place of the pumps will perform as designed. This original'Therman series: heat trace.

TACF is scheduled to be cleared when DCR-2182 is completed.

00'TACF: 2-85-2015f-077

- Chinged the' cable from existing MX# WHD The new type of cable, MK#-WHD-1, is to WHD-1 (Panel 0-L-2, 2-FCU-77-415).-

better qualified than the old type.

Tha existing cable became defective and This change does not increase the 0 nrw cable had to be. installed. The probability of an occurrence or the.

Original type of cable, MK# WHO, is no consequences of an accident. The margin longer available. The system involved of safety as defined in the basis of-Lie waste disposal.

any technical. specification is not reduced.

fhis TACF is-scheduled to be cleared when work on ECN-LB387 is completed.

- 'TACF: 2-85-2015-030 R;placed Agastat model 7012 PH timer The new 7012 PF relay meets the 10 Crange 3 to 30 minutes) with an Agastat minutes, plus or minus 1 minute, delay cod 21 7012 PF timer Crange 1 to 10 start time requirement of the technical minutes)..This timer starts the' specification and provides better containment air return fan 10 minutes assurance the plus or minus 1 minute (plus or minus 1 minute) after a phase tolerance.can be maintained. The margin B 1Eclation signal.

of safety as defined in the basis of any technical specification is not reduced. This TACF will be cleared when a category

'D' FCH is issued and a follow-up ECN is issued and completed.

So TACF: 2-85-2002-234 Installed non-QA Raychem parallel heat The probability and consequences of an trace in place of the existing Thermon accident are not increased as the heat

.h Ot trace and bypassed the Therman trace being installed is more reliable GtIp down transformer.

and the installed thermostat will maintain t:e as-designed line temperature. This TACF is scheduled to be cleared when work on DCR-2182 is completed.......,.......

k

SUMMARY

OF PROCEDURE CHANGES 4

,-r

ww--e

-,n-,..

,w_,+--.,-,,.-..-

'Pagl'No.

-1

02/22/07 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES-DESCRIPTION SAFETY.

SUMMARY

o PROCEDURE: ADI -- 007 o-PROBABLE MAXIMUM FLOOD REV

.This instruction was revised to add.The probability of an occurrence or 11 a: statement concerning safe storage the consequences-of.an. accident are of. quality assurance documents in not increased because this. change the office and pcwer stores building only affects the storage of' in the event of a-flood, documents and records in the office and power stores facility.

o* PROCEDURE: AOI - 010 0

LOSS OF: CONTROL AIR REV This instruction was revised to add The addition and deletion of-this.

11 the

'B' train vacuum relief valves information does not increase the.

to table 1 and delete a statement probability of an accident.;The concerning the reactor cavity margin of safety as defined in the ventilation support cooling which is basis of'any technical. specification not required by AOI-10.

is not decreased.

'00 PROCEDURE: AOI 027 o

CONTROL ROOM INACCESSIBILITY REU This instruction was revised to This revision was done to reflect t

OS reflect the change of pressure the 'as-constructed

status of the t

setpoints and time delays for auto plant and has no affect on safety.

swap-over from CST to ERCW.per WP l

119E3, and to correct typographical errors.

(

00 PROCEDURE: AOI - 03S I

o LOSS OF OFFSITE POWER REU This instruction was revised to add This revision cautions the operator OS a caution concerning the loss of that in the event of loss of offsite offsite power and update steps for power, coincident with a LOCA, the

. manually operating the steam train

'B' CCS water to the spent generator PORUS.

fuel cooling heat exchangers may have to be manually aligned. The technical specification requirements are still met and the margin of safety is not decreased. The revision to the steps to manually operate the PORUS does not decrease the margin of safety of the technical specification. t

1 P;;gJ. No..

2-102/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEOURE CHANGES DESCRIPTION

. SAFETY SunnARY REU.

This revision to AOI-3S was,in This change will allow the diesel 06 response tolINPO SER BS-2S to add a generators to run during a blackout caution to reset a diesel generator when it may_not have before. This after a non-emergency trip prior to decreases the probability of an an emergency start.

occurrence and the consequences.of an accident. The margin of safety as defined in the basis of the technical specification.is not decreased.-

co PROCEDURE: FR

- FR-O o --STATUS TREES REV This revision. changed the cold This change was to make the COPS O2 overpressure protection curve for consistant with the design units 1 and 2.

It also changed the setpoints. It does not increase the arming. temperature for unit 2. This probability of an occurrence or the made the procedure consistent with consequences of an accident or revised design setpoints.

malfunction as previously evaluated in the FSAR. This procedure change does not affect the basis of any technical specification.

00 PROCEDURE: FR

- FR-S.1 o

RESPONSE TO NUCLEAR POWER GENERATION /ATWS REU

-This revision to close the BIT The probability of an accident is 02 recirculation valves before the BIT not increased by changing the inlet and. outlet valves are opened sequence of the BIT valve alignment ~.

prevents overpressurizing the BIT The margin of safety as defined in recirculation lines and prevents the basis of the technical diversion of the BIT contents to the specification is increased because BAT until-recirculation is closed the BIT recirculation-line will not and pravents the dilution of the be overpressurized when this valve BIT.

alignment sequence is followed. ~

(PhiNo._

~3 102/22/G7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE' CHANGES LDESCRIPTION SAFETY 1

SUMMARY

05 PROCEDURE: SI

- 001 o l SURVEILLANCE PROGRAM

'REU.

This instruction was revised to This change affects only_the 13_

resolve. inadequate guidance and administrative requirements of the inadequate assignment of instruction. The addition of

-responsibilities in current' plant appendix

'F' actually increases'the procedures which address the attention given to insuring that Technical Specification Compliance technical specification requirements Instrumentation Program. This are met through administrative revision is~in response to CAR review requirements.

85-10-017.

REU.

This revision to SI-1 clarified the This change clarifies but does not.

15

.use of

'NA*

in the SI data sheets change the requirements related to

.and deleted _the requirement to the use of 'N/A' on SI data sheets.

maintain a six month SI schedule.

The probability or the consequences This revision is in response to NRC of an accident is not increased. The r

IE Inspection Report 50-327, margin of safety is not. decreased

-328/85-35.

because the plant physical configuration is not affected nor are actual test procedures.

REU This revision to SI-1 implemented The breaker / fuse program is an

~16

.the new breaker / fuse program increase in the level of inspection-description, incorporated NQAM and controls on scheduling, changes, implemented corrective tracking, and maintaining historical action for LER 327/86029 and records for the surveillance performed a two year review, instructions involved. This change does not affect physical plant configuration or change testing methods or procedures. It provides a more accurate and accountable scheduling and tracking technique..

REU This revision to SI-1 added appendix This change provides guidance and 18 G and made changes to appendices B limitations on the lining through of and C.

It provides guidance and data or the retaking of data and limitations as to when and to what does not increase the probability or extent data can be lined through and the consequences of an accident. The when explanations are required.

content of specific maintenance and surveillance instructions is not affected by this change. The margin of safety as defined in the basis of the technical specification is not decreased.

JF

]

.P;giNo.--

4

?O2/22/07 SEQUOYAH' NUCLEAR PLANT' 1986.NRC ANNUAL OPERATING REPORT

' PROCEDURE.. CHANGES DESCRIPTION SAFETY

SUMMARY

Eo* PROCEDURE: SI: - 002 0: SHIFT LOG

?REU.

Thisl instruction was revised: to The majority of the changes-were

39 place.the data sheets in two administrative and in no way. affect appendeces.for better' performance of the safety of.the plant or 4

the SI; to delete the reactor pit previously evaluated safety sump verification requirement for analysis.-The safety summary for ALARA considerations (the using'PR2 level indicators indicated-requirement was placed in SI-3); to that during made-S operation the comply with the recommendations of cold calibrated pressurizer level QA inplant survey checklist instrumentation provides a more

21-8S-P-011; to incorporate a conservative _ indication of actual technical' specification revision; pressurizer level than does the-hot and in accordance with ICF-BS-ISBB calibrated' instrument. The margin of and BE-0176 added a note to use.

safety as defined in the basis of either of the four. pressurizer level any technical specification is not-indicators Chat or cold calibrated) reduced by any of the changes for data readings in this.

incorporated by this revision.

instruction and to circle on the

' data sheet the11evel indicator number used for recording data.

REU This revision ta SI-2 corrected a The correction of the footnote and 40.

footnote which incorrectly stated a the SR number does not increase the j

diesel generator requirement and probability or the consequences of corrected the SR number in the an accident. The margin of safety as instruction.

defined in the basis of the technical specification is not decreased by this change.

l 00 PROCEDURE: SI

- 003 o-DAILY, WEEKLY, AND MONTHLY LOGS REU This instruction was revised to The change to the board voltages 47 correct battery boards and represents a change in the

. instrument power boards voltage.

acceptance criteria to reflect the Incorporated the reactor pit sump correct values. This revision will verification from SI-2 for ALARA not reduce the margin of safety of considerations. Deleted redundant any technical specification under

{

shift engineer signoffs and reviews the scope of SI-3.

per the surveillance instruction review checklist.

i i

I 1

n.

i 5 PagJ No.

02/22/07 SEQUOYAH. NUCLEAR PLANT 1985 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES

' DESCRIPTION

. SAFETY SunnARY REU This revision to'SI-3 clarified the 'This change affects:anly the 48 operability of seismic instrument interpretation on the effect of the 0-PX-SE-BS.

event trip function.on operability of the recorder. The monitor is capable of_ recording even with.the trip function for. seismic event in the white light.-The possid111ty for an accident or malfunction of a different, type than that evaluated.

in the FSAR does not exist. The.

' capability to compare the measured response to that used in the design basis is not affected.

.REU.

This revision to SI-3 changed the A technical specification revision

.49 made requirements for step changed the requirement for performance and deleted the overcurrent protective device overcurrent protective device verification and the devices are now verification. Also, corrected the verified in SI-270. The other monthly' log per PRO-1-86-067, changes were administrative. The corrected a. surveillance requirement probability of an occurrence or the number, and deleted an incorrect consequences of an accident are not 1 Footnote.

increased and the margin of safety is not decreased.

00-PROCEDURE: SI

- 006.01 I

O CONTAINMENT BUILDING UENTILATION ISOLATION C100 HRS / 7 DAYS) i-REV This instruction was revised to The probability of an accident is 03 include testing containment vent not increased by CUI testing with isolation CCUI) by making up these radiation monitors or by

[

RM-90-130A, RM-90-1308, RM-90-131A, including items from SI-14.1 and j

and RM-90-131B, and add items from 14.2. This additional testing does

'SI-19.1 and 19.2. It was revised in not affect the margin of safety.

response to findings of the technical specification review committee, PROS86-083 and 86-186, and LER 327/86017.

l l,

l 4

l l t

_ Pcg3 No.

E

~

02/22/87 SEQUOYAH NUCLEAR. PLANT

1985 NRC ANNUAL OPERATING REPORT PROCEDURE. CHANGES

~ DESCRIPTION

. SAFETY

SUMMARY

C*LPROCEDURE: SI

- 007 0J ELECTRICAL POWER SYSTEM: DIESEL GENERATORS REU. 'This instruction was revised to Appendix.E~1s performed quarterly to 33

. clarify the requirements for check the vibration and the fuel oil appendix E during increased transfer pump flowrate. Testing can frequency testing of the fuel all be placed on increased frequency if transfer pumps.

warranted by section XI.

. Increasing-the testing frequency does not affect the margin of safety as defined in the basis of any technical specification.

REU-This revison to.SI-7 reduced the

.The technical specification exempts 34 <

loading requirement of the diesel the 4000kW requirement if both units' generator while both units are in are in made 5 or B.

The margin of modes 5 or 6 to 2000kW. This will safety is not affected due to,the

conserve fuel and reduce wear on the decreased loads-which would be diesels..This revision clairfied the placed on the diesel generators voltage requirements per Technical during a made S or 6 accident.

Specification Interpretation No. 88. Verifying operability at 2000kW proves that sufficient load capability exists.

-REU This revision to SI-7 clarified the Performing more manual starts and 35 requirements on start methods and fewer auto starts will decrease the add space to record the diesel probability of an occurrence or the generators' run time.' Added space to consequences of an accident. The record verification of the start and instruction continues to meet the run data in'the SI-7.2 start log.

surveillance requirements and the

-margin of safety is not decreased.

REV This revison to SI-7 placed the The probability or the consequences 36 procedure in a format to help of an accident are not increased eliminate personnel errors and because the new format is an corrected some fuse identification administrative change, and the numbers.

correction of the fuse ids shows the

'as constructed' status of the plant. The margin of safety as defined in the basis of the technical specifications is not decreased.

N PJga-No.

7 02/22/87 SEQUOYAH NUCLEAR PLANT

-198S-NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY SunnARY oo' PROCEDURE: SI

.007.01 0.. DIESEL GENERATOR.AC ELECTRICAL POWER SOURCE _ OPERABILITY UERIFICATION REV This instruction was revised to Reading voltage indications has no 06-

' include a data sheet.to record start effect on safety. The. addition of bus and shutdown board voltages per surveillance requirements.will SR 4.8.1.1.1.a.

and add made increase the margin of safety.

applicability and requirements in the instruction.

REU

.This revision to SI-7.1 deleted The deletion of the reference to 4

- 07 reference to SI-3 and added a SI-3 and the addition of the signoff signcff to insure the diesel does not increase the probability of generator start was logged in the the occurrence or the consecuences l

diesel generator start log, of an accident. The margin of safety as defined in the basis of any technical specification is not decreased.

. REU.

This revision to SI-7.1 added The actual SI format / scope was'not

03 operator signature and date on data changed. The probability or the sheet 7.1A and added double person consequences of an accident is not verification for the return to increased. The margin of safety is normal steps after the diesai not affected by this revision.

generator is stopped. This was to i

comply with all items of the technical review.

l 00 PROCEDURE: SI

- 007.02 l

o<

DIESEL GENERATOR SURUEILLANCE FREQUENCY REV O This is a new instruction. The This SI satisfies surveillance purpose for this SI is to provide a requirements 4.8.1.1.4 and portions j

history of the diesel generator of 4.8.1.2.

The margin of safety as system to allow identification and defined in the basis of any corrective action for problem areas technical specification is not that could reduce the reliability of reduced.

the diesel generators.

l l

4 i

I

PagJ No.

8 02/22/C7 SEQUOYAH NUCLEAR PLANT ISBS'NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

00 PROCEDURE: SI

- 011 O

REACTIVITY CONTROL SYSTEMS MOVEABLE CONTROL ASSEMBLIES REV This instruction was revised to add The clarification of information on 07 a statement to the data sheet to the data sheet does not increase.the reflect the use of group demand probability of an accident nor does indicators.

it decrease the margin of safety as defined in the technical specification.

C*

PROCEDURE: SI

- 012 O

ECCS VALUE ALIGNMENT UERIFICATION REV This instruction was revised to The changes made to the instruction 15 comply with the SI-1 review have no affect on the way-the SI is checklist, correct grammatical performed. The probability of an errors, and add a statement accident is not increased nor is the concerning what should be done if margin of safety affected.

the acceptance criteria is not met.

REU This revision of SI-12 deleted Deletion of this valve from the

'B' 16

.FCV-63-4 C'A' train) from the

'B' train checx11st will not increase train checklist per SD-DR-86-1SSR.

the probability or the consequences of an accident since it is verified in the train

'A' checklist of the same SI. The margin of safety as defined in the basis of the technical specification is not decreased.

C0 PROCEDURE: SI

- 017 f

C EGTS FLOW REV This instruction was revised to The controlling value remained the 16 change the diffierential pressure same. This revision changed the controller setpoint fr:1m 8.33 setting on the instrument scale to percent to 10 percent to comply with correspond with the 0-5 inches water workplan 11S31.

DP controller installed. The margin of safety as defined in the basis of any technical specification is not decreased.

.~

~

' Pig 6 NJ.

S --

.02/22/87' SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION ~

SAFETY'

SUMMARY

I o.

CONTAINMENT SHIELD BUILDING EMERGENCY GAS TREATMENT SYSTEM FLOW REV This~ revision to SI-17 corrected the These changes are administrative and 18 format and added valves.for-the valve documentation for EQ does

. environmental qualification (EQ) not directly affect any plant

' documentation. This revison also systems. The probability of the changed the name of the SI.

occurrence or the consequences of an accident are not increased. The

. margin of. safety as defined in the basis of the technical specification is not reduced.

'00 PROCEDURE: SI- - 021 0 PUXILIARY BUILDING GAS TREATMENT SYSTEM REV This instruction was revised to This revision is to provide

' 1'S include documentation of additional documentation of'the FCO-30-146A, -1968, -157A, and -1578 valve operating parameters for having been full stroked and environmental qualification. The operating limits verified, for margin of safety as defined in the i

environmental qualification.

basis of any technical specification has not been decreased.

l j

co PROCEDURE: SI

- 033 l;

o ERCW AND AERCW UALUES SERVICING SAFETY RELATED EQUIPMENT REV This instruction was revised to This revision corrected an error in l

-20' change the required position of the valve position. It in no way affects

.ERCW outlet valves on the auxiliary the margin of safety of any i

mir compressor from open to technical specification.

throttled.

l co-PROCEDURE: SI

- 038

'8 SHUTDOWN MARGIN REV This instruction was revised to add This revision will maintain this 19 clarity and provide a new method of procedure in compliance with the calculating X(eff) to reflect technical specification. The availability of ARI critical baron probability or ths consequences of

data, an accident is not increased. The margin of safety is not decreasbd.._

~

Paga No.

10-

^~

>O2/22/87 SEQUOYAH NUCLEAR: PLANT

- 1986 NRC ANNUAL OPENA' RING REPORT PROCEDURE CHANGES

+

DESCRIPTION SAFETY

SUMMARY

x.

k' s

I,J

^

.REV This revision to SI-38 corrected an

.The' data which will be usedras a 120 errorfin the. previous revision which resultiofc this change has'been.

resulted in the indication of an previously analyzed and,was found to incorrect. source of data.

be acceptable. Since the. data willh be :obtained from a previous'ly -

evaluated source, the margin of safdty remains unchanged."#

s

~' #

00 PROCEDURE: SI

- 040 C

CENTRIFUGAL CHARGING PUMP l

REU-This one time temporary change The more, accurate test gauges installed' temporary test gauges to improved data readings and enhance non-CSSC instrumentation for testing the-evaluatton of the pumps. This the centrifugal charging pumps, did not increase the probability of an occurrence or the consequences of>'

an accident or malfunction of l

equipment. This revision did not-changq thu acceptance criteria for the pumps.

The margin of safety was. ;

not reduced.

~

cau l

s REU This one time temporary change to This test insured that the technt. cal' 51-90 added a part

'D'-to obtain specification requirements were i t

additional data needed to evaluate being met. An operable centrifugals the centrifugal charging pump tharging pump was verified' i

degradation.

in-service prior to isolating tha'

\\L l

pump being tested.

The margin of 4

safety was not decraased.. '

f.

i 00 PROCEDURE: SI

- 095.01 i

o ESSENTIAL RAW COOLING WATER PUMPS REU This one time temporary change The instrumentattor, added had a allowed the installation and removal higher accuracy than plant gauges of test instruments and allowed two and double verification was provided opposite train pumps to be operated for the installation and removal of at the same time. It also gave the instruments. Running anu two instruction to close 1-FCV-67-929 opposite train pumps will provies instead of 1-FCU-67-223 and adequate cociing water to the 2-FCV-67-223.

opposite train.

The margin of safety was not reduced. The margin of safety is increased by returning valves 1-FCV-67-929, 1-FCV-67-223, and 2-FCU-67-223 to their normal positions per TVA drawing'97W895-2.

i -

-.:r

5:y -

m;

~ ^ " - -

1;s

'PugkNo.4 11' c

50E/CE/87-n

.SEQUOYAH NUCLE 5R PLANT.

gr 4

p 2

1986 NRC ANNUAL OPERATING REPORT s

PROCEDURE CHANGES

~

DESCRIPTION SAFETY

SUMMARY

~ % ;

..........u.

a f,. -

r 3

REUi <Th.ts revision tc SI-4S.1 changed a This changa was to correct an 15' Lva'1ve number.in steis 1.1.2. Valve appacant' typographical. error'and

' 'E7-744A was incorrectly identified

_does?not. change the intent =or? scope

ss 67-743B., This was ein apparent of-the instruction. The probability _

' typographical error, of an. occurrence or the consequences of an accident is not' increased.-

This change.does not affect the-

//

instructions ability to fulfill the.

technical specificartion requirements. The margin of safety is not reduced.

,u 4 co PROCEDURE: SI 060 p-ho 72-HOUR CHEMISTRY REQUIREMENT 3 t'

REV Th19 instruction was revised to Only non-technical specification 24 include only technical sde,cification sample parameters were removed from i

reqQ1'ruments.

The non-technical

.this SI.

The_ probability of an (jl specification.requiremw:1ts Shich occurrence or the consequences of an r

were deleted are new'part of TI-37.

accident-or malfunction is not increased.

The margin of safety as defined in the basis of the technical specification is not decreased.

REV This revision to SI-50 revised the These changes were made to keep 25 ecope section and added the SI-SO in compliance with SI-1 and reference section.to comply with the the technical specification. The-

,(

requirements of SI-1. Also clarified' probability cr the consequences of-eg,,

the D.E.'I-131 requirements-for the an accident is not increened and the' 7 ',

technical specification.

margin of safety is not decreased.

p C*

PROCEDURE: SI L - 051 f

WEEXLY CHEMISTRY REQUIREMEN S REV This instruction was revised to make The changes that were made do not.

22 the SI more concisec clear, and to affect the safety of any plant eliminate redundancy.

equipment. These changes eliminate redundancy and insure that technical

-p specification requirements are satisfied. The margin of safety is j.

not decreased.

3 1

1 i-

[

/

y 4

k 4

. t..

4 LPcg1 No.-

l25 l-

'02/22/C7

.SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES

' DESCRIPTION SAFETY

SUMMARY

- PROCEDURE: SI. - OSS

'n 0 fREACTOR COOLANT DE I-131 ACTIVITY CONCENTRATION DETERMINATION

~ REU This revision cancelled the The dose equivalent I-131 09 instruction. The.SI requirements concentration is to be f.etermined were placed in SI-SO.

-once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. This is an 6

increase in frequency of performance. The margin of. safety as defined in the basis of any technical specification is not decreased.

-oo PROCEDURE: SI

- 057 "O ' ' SECONDARY COOLANT DE I-131 ACTIVITY CONCENTRATION DETERMINATION lREU

'This revision cancelled the The surveillance requirements of 27 OS instruction.-The requirements for SI-57 are satisfied by SI-50. The SI-57 were transferrad to SI-SO.

cancellation'of this instruction has no effect on plant: safety.

't

.** PROCEDURE: SI

- 075-

-*- REMOTE SHUTDOWN MONITORING INSTRUMENTATION STEAM GENERATOR LEVEL r.

REU This instruction was revised to add The intent of this instruction has 10-sign-offs (with instructions), added not changed but the order in which a reference section, separated the the steps are performed has,been L

transmitter calibration from the changed. No changes were made to the

"'. loop, and added the turbine driven acceptance criteria.

The margin of' L

auxiliary feedwater level loops.

safety as defined in the basis of any technical specification is not reduced.

l l

\\

L

\\.

f -

~

Paga No.

13L 02/22/B7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

Co. PROCEDURE: SI

- 080 C

POWER RANGE NEUTRON FLUX CHANNEL CALIBRATION AND FUNCTIONAL TEST COUARTERLY)

REU This-instruction was revised to add These changes were made to comply

' 110 a reference section. Also revised with the requirements of SI-1, and the scope to state that the to insure that all requirements,

' procedure can be performed in any including technical specification made. The acceptance criteria was requirements, are met. The margin of changed to include a statement to safety as defined in the basis of evaluate out of tolerance compliance the technical specification is not instruments per TI-S4.

decreased.

CO PROCEDURE: SI

- 082 o

FUNCTIONAL TESTS FOR THE RADIATION MONITORING SYSTEM. CUNITS 1 AND 0)

REU

.This revision added the reference These changes do not affect the high

-12

section and changed the approval to radiation setpoints or the intent of perform the test from unit operator the instruction. The probabliity or to senior reactor operator. It also the consequences of an accident are changed the alarm verification on not increased. The margin of safety the block test switch HS-90-136Al was not affected by this change.

and A2 and other minor changes required to conform with the procedure review checklist. Also added R-90-12S and R-90-126 to this instruction because they have ESF and use block switch HS-90-136Al and A2.

00 PROCEDURE: SI

- 082.02 o

FUNCTIONAL TESTS FOR THE RADIATION MONITORING SYSTEM (UNIT 2)

REV This revision added a reference This revision does not change the 03 section and changed the approval to high radiation setpoints or the perform the test from unit operator intent of the instruction. The to senior reactor operator. It also probability or the consequences of changed the alarm verification on an accident are not increased. The block test switch HS-90-136A1 and A2 margin of safety as defined in the and made other minor changes to basis of the technical specification conform to the procedure review is not decreased.

checklist. ~

PagJ No.

14

'02/22/G7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES' DESCRIPTION SAFETY

SUMMARY

- PROCEDURE: SI

- 083 20 CHANNEL CALIBRATION FOR RADIATION MONITORING SYSTEM REV This instruction was revised to The function of the ABI test

.13 delete the verification of ABI performed by SI-83 will.not be relays UKAR-S and UKBR-6. These altered by this change. All

. relays were removed by ECN-LS446.

technical specification requirements remain unchanged.

c* PROCEDURE: SI

- 093 0

REACTOR TRIP INSTRUMENTATION FUNCTIONAL TEST CPRIOR TO STARTUP)

REV This instruction incorporated the The steps added to this procedure-08 signoffs with the instructions and will insure proper operation of the added steps to test the auto shunt auto shunt trip features and will trip features to the reactor trip not increase the probability of an switchgear. This was added by occurrence or consequences of an ECN-6293 for NRC generic latter accident or malfunction. The 83-28.

functional testing of the auto shunt features should increase the confidence placed in the existing margin of safety by insuring a reactor trip can be achieved when demanded.

Rx TRIP INSTR FUNCTIONAL TESTS CONDITIONAL 7 DAYS (PRIOR TO STANTUP)

REV This revision to SI-S3 added steps This change will insure the HOS to test the bypass breakers as operability of the bypass breakers outlined in NRC generic letter BS-OS in the event of an undervoltage trip and added details to insure in the solid state protection compliance with the common mode system. The method of testing will failure criteria.

not increase the probability of an occurrence or the consequences at an accident or malfunction.

No technical specification setpoints or limits are affected by this change, therefore, the margin of safety will not be affected.

e u..

~

-Pcg7 No.1 151

O2/22/87,

^

SEQUOYAH' NUCLEAR PLANT' 1986 NRC ANNUAL' OPERATING REPORT PROCEDURE' CHANGES bDESCRIPTION SAFETY

SUMMARY

- ' PROCEDURE: SI

- 098.09 1V CHANNEL CALIBRATION FOR'ESF: INSTRUMENTATION, CONTAINMENT: SUMP _-

!REV O.This is a new instruction to cover This instruction satisfies-a11' containment _ sump loops in one surveillance requirements

' instruction.

9.3.1.1.b.9.a and 4.3.3.7.b.15.

00 PROCEDURE: SI

- 102 E/A

'O' ~ DIESEL GENERATOR ANNUAL ELECTRICAL INSPECTION

REU O This ista new instruction which

'This instruction partially satisfies contains the vendor recommended surveillance requirement

.' annual: electrical inspection

.4.8.1.1.2.d.1.

requirements for the diesel generators.

co PROCEDURE: SI

- 102 E/M-0 ' DIESEL GENERATOR MONTHLY ELECTRICAL INSPECTION

'REU O This is a'new-instruction which This instruction partially satisfies contains-the vendor recommended surveillance requirement monthly electrical inspection 9.8.1.1.2.d.l.

requirements for the diesel generators.

00 PROCEDURE: SI

- 102 E/SA l

o DIESEL GENERATOR SEMI-ANNUAL ELECTRICAL INSPECTION REU O This is a new instruction which This instruction partially satisfies contains the vendor recommended surveillance requirement semi-annual electrical inspection 9.8.1.1.2.d.1.

j requirements for the diesel generators.

REV This revision to SI-102 E/SA The channes will not affect the 01:

rearranges-steps to provide proper diesel generator operability and l

verification of alarm circuits while will not reduce any technical minimizing diesel generator starts, specification limit.

It changed the upper limit for the

~

hydraulic' governor to prevent interference with the electric governor.

t 4..a

Paga No.

.16 02/22/87 SEQUOYAH NUCLEAR PLANT 1586 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

REU This revision to.SI-102 E/SA deleted The-steps deleted are verified in 102 steps 6.S.2 and S.S.3.3 which are another step of the11nstruction and repetitions of step 6.4.S, no technical specification Verification of ' fail to run requirements are reduced.

annunication'.

co~ PROCEDURE: SI

- 102 M/M o

DIESEL GENERATOR MONTHLY MECHANICAL INSPECTIONS

.REV O This is a new instruction which This diesel generator surveillance contains the vendor recommended instruction is for the inspection of monthly mechanical inspection the mechanical equipment required to requirements for the diesel maintain operability of the diesel generators, generator and does not increase the probability or the consequences of an accident. These insnections will not affect the margin nf safety of any technical specification.

REV This revision to SI-102 M/M allowed The procedure was revised to meet 01 inspections to be-performed as the requirements of the technical required by the technical specification and will not increase specification to meet the SI the probability of an accident, The checklist requirements, margin of saf uty as defined in the basis of the Technical Specification SR 4.8.1.1.2.d.1 is not decreased.

'00 PROCEDURE: SI

--104 0

AUXILIARY BUILDING CRANE INTERLOCKS REU.

This revision added common mode This change only makes additions as 10 failure reference, surveillance required by the SI-1 review requirement number, and clarified cheak.ist. The margin of safety will the scope of the procedure.

not change due to the addition of this reference information to the instruction. (Tochnical Specification; SR 4.9.7) i i

1 -..

-Pagd'No.

' 17.

x.

"OE/22/G7-SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING-REPORT.

PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

1*0~ PROCEDURE: SI

-.114

~

c>. PRESERVICE BASELINE INSPECTION FOR TUA SEQUOYAH NUCLEAR PLANT lREU

.This~ revision-to.SI-114 cancelled This instruction was.used to. perform 14 the entire instruction. This the initial baseline inspection

- instruction was used during the required by section XI of the-ASME preservice period only..It has been. Boiler and Pressure Uessel Code and

replaced by SI-114.1 for unit 1.and was to have stayed in effect until SI-114.2.for unit:2, which are to be commercial operation of units 1 and i:

'used during inservice inspection

2. Since the startuo of units.1 and.

intervals.

2, the inservice inspection program-has-been performed per SI-114.1 and SI-114.2.which resulted from 4

Surve111ence' Requirement 4.0.S.

Cancelling this procedure will not-increase _the probability of an occurrence or the consequences of an

. accident. The margin of safety has not decreased.

c' PROCEDURE: SI

- 114.02 0

INSERVICE INSFECTION PROGRAM FOR TVA SEQUOYAH NUCLEAR PLANT REV This instruction was revised to' This revision complies with the 07 reflect. organizational changes and.

interpretations made by NRC plant configuration changes. The reviewers and incorporates plant revision also complies with configuration changes. This will not discrepancy report SQ-DR-OS-OS-11SR, increase the probability or the and NRC commitments (CCTS1 control ccnsequences of an accident. This numbers: NCO-86-0284-OO4, revision reflects NRC inter 7retation NCO-85-0119-OO4, NCO-OS-0119-OO3, of the ASME Section XI Boiler and NCO-86-0119-OO2, and Pressure Uessel Code and will not NCO-86-0119-OO1.

reduce the margin of safety definad in the basis of the technical specification....

PagJ No..

18 02/22/97' SEQUOYAH NUCLEAR PLANT IS86.NRC ANNUAL OPERATING REPORT

-PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

C*

PROCEDURE: SI

- 117 o

ERCW SYSTEM OPERATING REV This revision to SI-117 added the Addition of the applicable modes 01

. applicable modes for the SI. This does not increase the probability or was the result of a technical the consequences of an accident. The review.

margin of safety is not decreased.

REU

'This instruction was revised to meet Ccmbining the instructions and data 02 the format and content of SI-1 sheets, adding SRO signoff, and criteria. Also added the requirement making SI-117 comply with the that an SRO must grant permission requirements of SI-1 does not prior to testing.

increase the probability or the consequences of an accident. The addition of the SRO signoff will insure that all technical specification requirements are met.

The margin of safety is not affected.

c* PROCEDURE: SI

- 118 o

MOTOR-DRIVEN AUXILIARY FEEDWATER PUMP AND UALUE AUTOMATIC ACTUATION REU This instruction was revised to add Adding the notification of the SRO 13 steps that require permission from decreases the probability or the SRO to perform the test and that consequences of an accident because the SRO must be notified when the the SRO is knowledgable of the test test is completed.

in progress and the possible implications. The margin of safety is not decreased.

C0 PROCEDURE: SI

- 11S o

ERCW AUTO ACTUATION FROM AN SI SIGNAL REV This instruction was revised for This revision will insure that both 07 technical review and to prevent trains of the ERCW are in service removal from service of a complete during performance of the test. This train during performance of the does not increase the probability of test. Steps were included that an accident. The margin of safety as prevent a cooplete train from being defined in the basis of the removed from service during the technical specification is actually performance of the test.

increased.

i n-

f PhgelNo.

19' lO2/22/;7 SEQUOYAH NUCLEAR PLANT

.1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION-

' SAFETY

SUMMARY

(

-Go PROCEDURE: SI

- 130.02

'o NOTOR DRIVEN AUXILIARY FEEDWATER PUMPS

REV

_This' instruction was revised to add The installation and use of the

~1S sumps to install an ultrasonic-ultrasonic flowmeter will not create' 4

Flowmater on the inlet or the possibility of an accident or recirculation piping of the motor equipment malfunction. The: ability driven auxiliary feedwater pumps.

of the auxiliary feedwater system-to l-This was done to obtain baseline perform.its intended function will data and to. measure the flow rate not be affected.-

during periodic performance testing.

- PROCEDURE: SI

- 130.03 o

AFW FULL FLOW-TEST i

REV O This is a new instruction for full The AFW system will not be operated flow testing of the motor driven outside the limits stated in the auxiliary feedwater CAFW) pumps by basis of surveillance requirement ramping the level control valves for 3.7.1.2 and only one AFW-pump will

_the pump being tested.

be tested at a time. The margin of.

safety is not reduced nor-the probability of an occurrence or the consequences of'an accident 1_

increased.

REV

.This revision to SI-130.03 cancelled This SI does not fulfil 1~a technical

~

'01_

the instruction.

specification surveillance requirement. The technical specification surveillance requirment for AFW full flow testing is being implemented by a new instruction, SI-727.

l-i l'

1

! )

Page No.-

'20

'02/22/G7-

.SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

c*' PROCEDURE: SI

- 13S s

JO ESTS CLEANUP' SUBSYSTEM AUTOMATIC START

'REV JThis revision added two dampers The probability of an accident is 08 which should have been included not-increased by the addition of the.

Originally.

two dampers to a checklist on which they should have been originally.

The margin of safety is increased by the identification of the dampers.

c' PROCEDURE: SI

-1137.04 O

REACTOR COOLANT PUMP SEAL INJECTION RESISTANCE REV This revision cencelled the entire This surveillance instruction was 02

. instruction'. This instruction was written to verify assumptions made r

originally written to verify in a Westinghouse ECCS accident i

outdated Westinghouse analysis. All analysis. The assumptions are no-test requirements will be satisfied longer valid and testing by SI-137.3.

requirements are satisfied by SI-137.3. The probability of the.

occurrence or the consequences of an accident is not increased, and the margin of safety is not reduced by cancelling this instruction.

00 PROCEDURE ~: SI

- 149

-0 AUXILIARY BUILDING GAS 7dEATMENT SYSTEM UACUUM TEST REV This revision clarified the This~ change does not increase the 13 procedure, corrected several probability or the consequences of door / damper ID numbers, corrected an accident or malfunction. The typograahical errors, and added a margin of safety as defined in the calculation' sheet for ' allowable basis of the technical specification leakage tolerance *. The change was is not decreased.

performed as a result of an SI-1 checklist review.,

~ PUgJ No.

21 02/22/G7 SEQUOYAH NUCLEAR PLANT 1985 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

co. PROCEDURE: SI

- 1S1 0

SIX MONTH TEST REQUIREMENT ON ELECTRIC' HYDROGEN RECOMBINER SYSTEM REV This revision insures the hydrogen This revision is to insure that the 10 recombiner hac operated for a hydrogen racombiner has operated for

-sufficient time prior to determining a sufficient time to allow an that a thermocouple is bad. It also adequate evaluation of the subdivides the SI-1S3 reference.

thermocouples and prevent unnecessary issuance of work requests.

00 PROCEDURE: SI

- 1S8.01 0

CONTAINMENT ISOLATION VALUE LEAX RATE TEST REU.

This revision specified that 'as The changes are due to typographical 24 found' and 'as left' path leakage is errors and a change in reporting and based on worst case boundary (valve) documentation methods of containment leakage for each leakage path. This leak rates. The probability of an also corrected typographical errors. accurrence or the consequences of an accident or malfunction is not-increased. The margin of safety as defined in the basis of any technical specification is in no way reduced.

oo PKJCEDURE: SI

- 166.03 0

FULL STROXING OF CATAGORY

'A' AND

'B' VALUES DURING COLD SHUTUOWN REV This revision deleted the The deletion of the power operated 22 requirements for testing the relief valves test requirement pressurizer power operated relief instructions from SI-166.3 will not valves (PORUS). SI-166.40 will affect the margin of safety. They fulfill this SR.

are now tested under SI-166.40.

(SI-166.40 revision is in progress) l i

l

, [

PcC; No.

22

~02/22/C7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

D PROCEDURE: SI

- 165.29

'o CONTROL AIR. CHECK UALUE TEST DURING COLD SHUTDOWN REU This revision provided steps and This documentation to insure that 007 signoffs to document the removal and the caps removed from the test reinstallation of pipe caps from valves are replaced. insures the test valves used for this test. This margin of safety as previously is to provide documentation as analyzed is maintained.

required by AI-37 and AI-9.

c' PROCEDURE: SI

- 167 o

FIRE HEADER UALUE LINEUP INSPECTION REU This revision added fire hydrant Neither inspection of the new valves ~

17 isolation valves for the nor the additional clarification construction warehouse hut area per provided will increase the Work Plan 11942 and made probability or consequences of an typographical corrections. It was accident. The margin of safety as also revised to isolate air to test defined in the basis of the the operability of PCU-26-109 and technical specification is not 110 and to include new valves, reduced.

REU This instruction was revised to The probability of occurrence or the 18 comply with SI-1. This instruction consequences of an accident is not contained a valve that was never increased by this change which installed in the plant. The valve updates the procedure to the 'as was deleted from the instruction to constructed' state of the olant. The bring it up to date with the 'as margin of safety as defined in the constructed' configuration of the basis of the technical specification plant. Additional administrative is not decreased. The valve was changes were made to comply with never installed in the plant and the SI-1.

other changes were administrative.

C*

PROCEDURE: SI

- 172 O

FIRE SYSTEM TESTABLE VALUE CYCLING REU This revision added sectionalizing The addition of the sectionalizing 09 valves that are in the turbine valves to this instruction does not building ring header.

decrease the margin of safety as defined in the basis of any technical specification.

. 1

'Page No.-

23 02/E2/97 SEQUOYAH NUCLEAR PLANT.

ISBS NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

c' PROCEDURE:'SI

- 177.01 0 ~ SPRAY AND/OR SPRINKLER SYSTEMS FUNCTIONAL

REU This revision changed the data Neither the revision of the data 02 package cover sheet and deleted a package cover sheet nor the deletion manual valve on data sheet-177.1A of the manual valve increase the which was on the data sheet by probability or the consequences of mistake.

an accident. The margin of safety as defined in the basis of the technical specification has not been reduced.

CO PROCEDURE: SI

- 181 o

FIRE HOSE HYDROSTATIC TEST REV O.This revision cancelled the Technical specification fire hoses

-instruction. SI-181 will be will be hydrostatically tested in replaced by SI 181.1 and -181.2.

SI-181.1 and -181.2. The margin of safety as defined in the banis of any technical specification has not been decreased.

C*

PROCEDURE: SI

- 181.02 0

FIRE HOSE HYDROSTATIC TEST-TRIENNIAL REV O This is a new instruction and it The acceptance criteria was assumes the test responsibilities transferred from SI-181. The for technical specification fire probability of occurrence or the hoses from SI-181.

consequences of an accident are not.

increased. This SI satisfies the surveillance requirements. The margin of safety is not decreased.

REV This revision is in compliance with Portions of this SI are covered by 01 SI-1 and changed the range of the surveillance requirement test gauge from 0 to 500 psig. Also 9.7.11.4.c.2. This revision made other minor changes.

incorporates made performance and SRO approval to test. It does not reduce the margin of safety as defined in the basis of the technical specification. _,. _ _ _,. - - _ - _, _ _ _ _, - _,, _

,._____.._.c__

-Paga No.-

24 102/22/87 SEQUOYAH NUCLEAR PLANT 1586 NRC-ANNUAL OPERATING REPORT PROCEDURE CHANGES

' DESCRIPTION SAFETY

SUMMARY

t

-00 PROCEOUREi SI

,181.03 lb.HIGH PRESSURE FIRE PROTECTION STRAINER' INSPECTION (12 MONTHS)

REV O This is a new instruction written in.The strainer inspection /cisaning-response to' CATS BS-428. This performed by this instruction-will instruction established a 12-month ~

reduce the probability of the frequency.of-inspection of-the unit occurrence of'an accident. The

'1 and unit 2 high pressure fire strainers will be cleaned and known protection strainers.

to be in proper condition before returning to service.' Performance of this SI will provide the margin of safety defined in the basis of the

. technical specification.

00 PROCEDURE: SI

- 181.04

'o-HIGH PRESSURE FIRE PROTECTION STRAINER INSPECTION (18-MONTHS)

REV O This is a new instruction to provide The strainer inspection / cleaning inspection of unit 1 high pressure performed by this instruction will fire protection strainers once per decrease the probability of an 18 months.

accident since the strainers will be known to be in the proper condition prior to returning to service. The performance of this instruction will provide.the margin of safety defined in the basis of the technical specification, 00 PROCEDURE: SI

- 181.OG o

HIGH PRESSURE FIRE PROTECTION STRAINER INSPECTION (18-MONTHS)

REV O This is a new instruction to provide The otrainer inspection / cleaning inspection of the unit 2 high performed on the frequency of this pressure fire protection strainers SI will decrease the probability'of once per 18 months, an accident since the strainers will be known to be in the proper condition prior to returning to service. The performance of this instruction will provide the margin of safety defined in the basis of the technical specification.

- - - - - - - - - - _ = - - - - - - - - - - - - - - -

! ' Pag J No.

L25 02/C2/D7 SEQUOYAH' NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE ~ CHANGES' DESCRIPTION SAFETY

SUMMARY

-C0 PROCEDURE: SI

- 184 16 ' PERIODIC CALIBRATION OF UPPER HEAD INJECTION SYSTEM

REV This revision cancelled this' The technical specification 02 instruction. These requirements'have requirements are being. met'in SI-1SG been incorporated into SI-196.

and no margin of safety is reduced.

All calibrations will be performed on their required intervais, c' PROCEDURE: SI

- 195 0

PERIODIC CALIBRATION OF FLUID COMPONENTS INC. FLOW SWITCHES (SEMI-ANNUAL)

REV This instruction was revised in The qualification maintenance data Oli accordance with ICF NOS. 85-1715, sheets (QMUS) are satisfied and the 86-0454, and 86-DOB1 which added setpoints are clearly listed on the steps for setting the switch data sheets. The probability or the setpoint and added documentation for consequences of an accident are not environmental qualification (EG) increased. This change will insure requirements.

an accurate calibration is performed and will.not reduce the margin of safety as defined in the basis of SR 3.6.1.8.

REV This revision to SI-1SS incorporated This revision does not alter the

'02 new vendor information on flowswitch original function or operation of calibration and corrected the instruments. The change is only deficiencies found by the SI-1 to implement new calibration checklist. General revisions were instructions and insure the made to clarify the instruction.

actuation points are set correctly.

The instruments in this procedure are not technical specification instruments. No margin of safety is decreased.

'Page No.

23

.02/22/07.

=SEQUOYAH NUCLEAR PLANT L1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION.

SAFETY

SUMMARY

.co PROCEDURE: SI

- 196~

,o LS CALIB AND ULU CLOSURE RESPONSE TIME TEST OF UHI SYS HYDRAULIC ISO ULUS

REV-This instruction was revised because Changing the scheduling document for oOS the Barten UNI Level. Switches were the level transmitters and pressure replaced with SOR brand switches,.on indicating switches will not affect-

=ECN S3SS, which require a different the 18 month calibration frequency..

calibration method. Also, The purpose of ths ECN was to incorporated the calibration of the install a more reliable switch which UHI~ surge tank level transmitters will reduce the number of PRus which and the pressure' indicating have been written due to the Barton switches.

switch being found out opf tolerance. The probability of an-occurrence or the. consequences of an accident is not increased. The margin of safety is not reduced.

00 PROCEDURE: SI

- 196.02-0 LS CALIB AND-ULU CLOSURE RESPONSE TIME TEST OF UHI SYS HYDRALLIC ISO ULUS

-REV This revision cancelled this The technical specification o09 instruction. This instruction has requirements are being met in SI-196

'bmen incorporated into SI-196.

and no margin of safety is reduced.

All calibrations will be performed on their required intervals.

00 PROCEDURE: SI

- 204 o

FUNCTIONAL TEST FOR RADIATION MONITORING SYSTEM CMONTHLY)

REV This instruction was revised for The calibration and instrument 16 general update and review against scaling values were not changed by the SI review checklist. It was also this revision. The probabilitu or revised to move the functional test the consequences of an accident is of'RM-90-12S and RM-90-125 to SI-82 not increased since the surveillance since these monitors use the block requirements are met in SI-82. The switch while performing the margin of safety is not decreased, functional test.

L l

Page No.

)

27 02/E2/C7 SEQUOYAH NUCLEAR PLANT 1985 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

co PROCEDURE: SI

- 204.02 O

FUNCTIONAL TEST FOR RADIATION MONITORING SYSTEM CMONTHLY)

REV

'This revision added a list of The surveillance requirements of the 06 technical specification monitors to FSAR and technical specification are the scope of the procedure and not affected by this revision. No clarified the acceptance criteria.

margin of safety is decreased.

(

co PROCEDURE: SI

- 209 o

PERIODIC CALIBRATION OF COMPLIANCE INSTRUMENTS IN ASSOCIATED ELECTRICAL SYS REU This revision cancelled.this The surveillance requirements of 02-instruction. The technical this instruction has been specification surveillance transferred to SI-209.1 ANO -209.2.

requirements will be covered by The margin of safety as defined in SI-209.1 and 209.2.

the basis of the technical specification is not decreased.

00 PROCEDURE: SI

- 209.01 0

PERIODIC CALIBRATION OF UOLTMETERS IN ASSOCIATERD ELECTRICAL SYS REU 0 This is a new instruction that meets The added details will insure that the technical specification the probability of occurrence or the surveillance requirements of SI-209, consequences of an accident is not for unit 1.

In addition to these increased. The margin of safety is requirements, details on instrument increased due to the increased calibration including lifting and requirements in the procedure, replacing wires and the use of calibration stickers were added.

oo PROCEDURE: SI

- 209.02 0

PERIODIC CALIBRATION OF VOLTMETERS IN ASSOCIATED ELECTRICAL SYS REU 0 This is a new instruction that meets The added details will insure that the technical specificaticn the probability of occurronce or the surveillance requirements of SI-209 consequences of an accident is not for unit 2.

In addition to assuming increased. The margin of safety is the requirements, details on increased due to the increased instrument calibration (including requirements in the procedure.

lifting and replacing wires) and use of calibration stickers were added.

i Page No..

23

02/E2/C7

.SEQUDYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY SunnARY co. PROCEDURE: SI

- 212

-o ECCS THROTTLE VALUE MECHANICAL STOP POSITION REU This instruction was revised to Revising the throttle valve 013 comply with required positions of positions insures that the assumed unit 1 ECCS throttle valves per flow ECCS injection flows will'be balancing performed during the provided during an accident and performance of SI-2SO. The new maintains the margin of safety as positions provide the required flows defined in the basis of the and balance per SR-9.S.2.h.1 and

.2.

technical specification.

REV This revision to SI-212 added a note The format change and the note added 15 to the data sheets to use a template are administrative. The acceptance and revised the format to comply criteria was already in the uith SI-1. It also added acceptance instruction and was added to criteria to attachment 1.

attachment 1. The probability of an occurrence or the consequences of an accident are not increased. The margin of safety as cefined in the basis of the technical specification is not decreased.

co PROCEDURE: SI

- 218 o

PERIODIC FUNCTIONAL TEST OF RCP UNDERFREQUENCY RELAYS REU This revision cancelled this SI-218 is replaced by SI-218.1 for 04 instruction. This instruction is unit 1 and SI-218.2 for unit 2. The replaced with SI-218.1 and SI-218.2. new procedures accomplishes the same function as SI-218. The margin of safety is not reduced because the new procedures verify the relays are calibrated to meet technical specification requirements and the calibration is performed in a made when the relays are not required to be inservice.

LPage No..

ES

,'02/22/C7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT

. PROCEDURE CHANGES-CESCRIPTION SAFETY

SUMMARY

CO PROCEDURE: SI

- 218.01 0

PERIODIC CALIBRATION OF RCP.UNDERFREQUENCY RELAYS

-REV O This instruction was written to Verifying the relays are calibrated replace SI-218.for unit 1. This-to. meet technical specification instruction verifies that the relays requirements and performing the are calibrated to meet technical calibration in a mode when the-specification requirements, relays are not required to be-instruments used in calibrating ~the inservice insures the margin of relays have the necessary accuracy, safety as defined in the basis of and common made failure criteria is the technical specification is not-addressed.

reduced.

00 PROCEDURE: SI

- 218.02 0 - PERIODIC CALIBRATION OF RCP UNDERFREQUENCY RELAYS REU O SI-218.2 was written to replace SI-218.2 will accomplish the same SI-218 for unit 2. SI-218.2 includes function as SI-218 and the steps not in-SI-218 that verify the additional steps in SI-218.2 will relays are calibrated to meet improve the calibration test. The technical specification probability of an occurrence or the requirements, instruments used in consequences of an accident is not.

calibrating the relays have the increased. The surveillance necessary accuracy, and common made requirements are being assumed by failure criteria is addressed.

another instruction. The' margin of safety is not decreased.

00 PROCEDURE: SI

- 228 o

PERIODIC FUNCTIONAL TEST OF RCP UNDERVOLTAGE RELAYS REU This' revision cancelled this SI-228 was replaced by SI-228.1 for OS instruction. The requirements were unit 1 and SI-228.2 for unit 2.

The incorporated in SI-228.1 and new procedures will accomplish the SI-228.2.

same function as SI-228. The margin of safety is not reduced because the new procedures verify the technical specification requirements are met and the required number of undervaltape relays remain in service at all times.

SI-d28.1 and

.2 are in the review / approval cycle..

Page No.

30

-02/22/87 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORf PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

00 PROCEDURE: 'SI

- 230 0

PERIODIC FUNCTION TEST OF RCP UNDERFREQUENCY RELAYS REU This revision cancelled the The surveillance requirements are-07 instruction.

The surveillance still being met. They are being requirements for SI-230 are being transferred to SI-230.1 and incorporporated.7to SI-230.1 and SI-230.2. The margin of safety as SI-230.2.

defined in the basis of any technical specification is not decreased.

CO PROCEDURE: SI

- 230.01 l

0 PERIODIC FUNCTIONAL TEST OF RCP UNDERFREQUENCY RELAYS CUNIT 1)

REU 0 This instruction is a new SI-230.1 will perform the same

(

instruction written to replace function as SI-230, for unit 1, and

~

SI-230, revision S, for unit 1.

the additional steps will improve r

(

SI-230.1 has steps that are not in the functional test. The probability SI-230. These steps will verify: the of an occurrence or the consequences underfrequency relays actuate of an accident is not increased.

approximately at their setpoints, Since the surveillance requirements orange stickers are placed on the were transfered from SI-230 to annunciator windows, and common made SI-230.1 and are still being met, failure criteria is addressed, the margin of safety is not reduced.

co PROCEDURE: SI

- 230.02 O

PERIODIC FUNCTIONAL TEST OF RCP UNDERFREQUENCY RELAYS CUNIT 2)

REV O This is a new instruction written to SI-230.02 will perform the same replace SI-230 for unit 2. SI-230.02 function for unit 2 as SI-230. The has steps that are not in SI-230 additional steps will improve the which verify the underfrequency functional test. The probability of relays actuate approximately at an occurrence or the consequences of their sat points. Orange stickers an accident is not increased. Since are placed on the annunciator the surveillance requirements were windows and common made failure transferred from SI-230 to criteria is addressed.

SI-230.02, all the requirements are still being met. The margin of safety is not reduced.

PagJ No.

31.

02/22/ 7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE' CHANGES DESCRIPTION SAFETY

SUMMARY

co PROCEDURE: SI

- 233.01 O

VISUAL INSPECTION OF PENETRATION FINE BARRIERS'- MECHANICAL REU This revision reflects the current These changes do not' increase the C1

' physical plant conditions, current probability of occurrence or the plant procedures, and clarifies the consequences of an accident or scope..It also incorporated ICF malfunction. Surveillance

(

86-0829 which allowed the 3/4-inch requirement 3.7.12 states that all conduit penetration for door AS1A on fire barrier penetrations shall be the thru wall linkage hookup to functional. The acen cenetration is remain unsealed at all times.

acceptable per NFPA 80 and it has been evaluated by DNE. The margin of safety is not decreased.

co PROCEDURE: SI

- 233.04 o VISUAL INSPECTION OF THERMAL FIRE BARRIERS REV This revision clarified the Clarifying the instruction and 01 instruction and defined the method defining the methods for identifying for identifying and repairing and repairing breaches does not breaches to Xaowool or Thermo-lag reduce the margin cf safety as thermal fire barriers.

defined in the cases of the technical specification.

C*

PROCEDURE: SI

- 233.OS o

VISUAL INSPECTION OF MISCELLANEOUS FIRE BARRIERS REV This revision updated the procedure This instruction revision did not 01 with the change from maintenance change the procedure's ability to request to work request, added controi fires or breaches. The Technical Specification probability of an occurrence or the Interpretation Log No. 86 to the consequences of an accident will not reference section, and added a fire be increased. The additional fire wall to comply with appendix

'R' wall added to the procedure was requirements.

installed to provide proper separation of trains. The margin of safety as defined in the basis of the technical specifications is not reduced.

PagJ No.

32

02/22/E7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING HEPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

00 PROCEDURE: SI

- 234.06 O

TECHNICAL SPECIFICATION FIRE DETECTORS UNIT 1, 2,

AND 0 REV This revision deleted step 7.2.2 on The intent and actual performance of 09 data sheets that are not cross the instruction remains the same, zones. Also corrected typographical Tho uteos were changed for clarity errors.

at the reauest of craft personnel.

The margin of safety as defined in the basis of any technical specification is not reduced.

Co PROCEDURE: SI

- 234.07 o

TECHNICAL SPECIFICATION FIRE DETECTORS REACTOR BUILUING UNIT 2 REU This revision added six fire The. addition of detectors ulii 00S detectors to the annulus fire increase the fire protection in the protection zone, annulus and.no margin of safety is reduced.

00 PROCEDURE: SI

- 256' O

PERIODIC CALIBRATION OC & GF RELAYS ON 6.SkV RCP DN 6.SkV UNIT BOARUS REV This revision incorporated detailed The changes to this instruction OS acceptance criteria, double signcff, enhance the testing program recuired and to remove the distance relay.

to insure the evercurrent protection This change is associated with a referenced in the basis of the commitment made in response to I 8 E technical specification. Because of Report 590-327. 328/85-46-04.

this, the margin of safety associated with the penetration protection is maintained, co PROCEDURE: SI

- 258.02 o

INSPECTION OF MOLDED CASE AND LOWER UCLTAGE CIRCUIT BREAKERS REV This revision added data sheets for Inclusion of additional breakers and 008-additional Westinghouse EB and updating torque values to latest General Electric TFK and TEB specifications improves the margin breakers and updated the torque of safety, values on table 1. _

Pag _; No.

33 02/L2/L7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

- PROCEDURE: SI

- 260.02.1 0

BIT CL INJECTION FLOW BALANCE, PMP PERFORMANCE, AND CHECX VLU TEST (MODE 5)

REV O This instruction has been written to Performing this test with the allcw full flow testing cf the reactor head installed does not centrifugal charging pumps with the decrease the margin of safety. The reactor head installed. It also cold overpressurization protection allows the measuring of the is always provided.

centrifugal charging pump miniflow flow rate using an ultrasonic flowmeter.

o BIT CL INJECTION FLOW BALANCE. PMP PERFORMANCE AND CHECX VLV TEST REV This revision to SI-260.02.1 added a This change will insure that 01 note to enter LCO 3.7.12, as technical specification valves are required, when power is restored to tested properly and insure that the the miniflow valves. Changed the technical specification is compiled instruction so that the throttle with during the performance of this valves are put in their initial SI. The margin of safety as defined positions when taning 'as found' in the basis of the technical data. Corrected the elevation specification is not decreased.

difference equation and typographical errces.

CO PROCEDURE: SI

- 261 o

VISUAL INSPECTION OF TECHNICAL SPECIFICATION FIRE DOORS ON A PERIODIC BASIS REV This revision complied with appendix These changes, which corrected the 08 R commitment, CATS 85137 and 86067.

instruction to actual locations and Also revised in accordance with ICF added or deleted doors to comply Nos. 86-0170, -0188, -0315

-0678, with the drawings, do not affect the and -0735. The changes made to intent of the SI. The probability of satisfy these requirments were:

an occurrence or the consequences of correctly indsntified the elevation an accident or malfunction is not of the lube oil purification room, increased. These changes do not deleted doors AIO3 and A117 which affect the procedure's compliance are no longer fire dcors per the with the technical specification drawings, corrected the elevation of requirements and no margin of safety door TSa, corrected door ID from C46 is decreased.

to C46a, added control building doors C14 and C15, and changed the title to ' VISUAL INSPECTION OF TECHNICAL SPECIFICATION FIRE DOORS ON A PERIODIC BASIS'. -

Pag ~ No.

34 02/22/C7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

C3 PROCEDURE: SI

- 267.62.5 0

INSERVICE PRESSURE TEST OF CVCS BORIC ACID BLENDER AND COMPONENTS REV This revision cancelled this The boric acid blender and 01 instruction. The baric acid blender components are not in the secpe of and components are not included in ASME Section XI and the test is not the scope of ASME Section XI Cno required by surveillance requirement safety function) and are not 4.0.S.

The margin of safety as required to be pressure tested defined in the basis of any in-service.

technical specification is not reduced.

co PROCEDURE: SI

- 275.02 O

INSPECTION AND TESTING OF NON CLASS 1E LOAD CB'S FEU FROM CLASS 1E BUSES REV This instruction uns revised to This revision insures that eacn type 07 comply uith the technical of circuit breaker u111 be specification requirements to functional uhen required, thus perform an individual polo reducing the probability of an overcurrent trip test, if accident. No safety-related applicable, on molded case and equipment covered by the technical instantaneous (secondary current specification u111 be degraced and injection) for rack out (DS) circuit no margin of safety is reduced.

breakers, o

INSPECTION AND TESTING OF NON CLASS IE LOAD FED CB'S FEU FROM CLASS IE BUSES REU Inis revision to SI-275.02 added These changes enhance the 08 additional information on common performance and provide greater made failure clarification, deleted control over the curformance of this a DC hold point in section 7.2, and SI. The probability or the deleted page 64 of the data sheet, consequences of an accident is not The response trip time values uere increased. The margin of safety as also corrected and the use of the defined in the basis of the configuration control data sheet uns technical specification is not required.

reduced.

h Page No.

3S O2/22/C7 SEOUOYAH NUCLEAR PLANT I

1S86 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

O INSPECTION AND TESTING OF NON CLASS 1E LOAD CB'S FED FROM CLASS 1E BUSES REV This revision to SI-275.02 This change requires additional 10 incorporated instantaneous testing testing of molded case circuit of all breakers. This revision breakers that will insure their satisfies the biennial review and is ability to function as designed.

revised in accordance with SI-1 This is required for compliance with Appendix

'F'.

S.H. 9.8.3.3.a.

Testing is done with the breaker out of service and no accident probabliity or margin of safety is changed.

INSPECTION AND TESTING OF NON CLASS 1E LOAD CB'S FROM CLASS IE BUSES REV This revision to SI-275.02 was in These fans do not perform any 10 accordance with ICF 85-1278 which safety-related function. The added breakers for the icwer probability or the consequences of compartment cooler fans to the list an accident are not increased. The to be inspected and tested. Data margin of safety is not reduced sheets for these breakers were because the icwer compartment added.

coolers are not addressed in the technical specification.

C'

PROCEDURE: SI

- 276 o

AUXILIARY FEEDWATER AUTOMATIC CONTROL VALUES OPERABILITY REV This instruction was revised to Addition of tnu cavitating venturi 13 update the instructions for testing does not increase the probability of the auxiliary feedwater CAFW) motor occurrence or the consequences of an driven pump LCUs due to the accident or malfunction. The margin installation of the cavitating of safety as defined in the bases of venturi on the motor driven AFW the technical specifications is not pumps. This reflects the change in reduced.

the crossover point from the bypass valves to the main regulating valves. The original value of S00 psia was changed to 400 psia due to the installation of the venturi. I

)

Page No.

35 02/22/C7 SEQUOYAH NUCLEAR PLANT 1985 NRC ANNUAL OPERATING REPORT PROCEDURE CHANGES DESCRIPTION SAFETY

SUMMARY

C3 PROCEDURE: SI

- 278 0

FUNCTIONAL TEST OF SOURCE RANGE NEUTHON FLUX CHANNELS DURING MODES 2 THHU S REU This revison cancelled this SI-93.2 was revised in iSBS to 04 instruction. The entire scope of handle the shutdown and startuo SI-278 has been included in SI-93.2. requirements previously orovidec by SI-278. The probability of the occurrence or the consequences of an accident are not increased, and the margin of safety as defined in the basis of any technical specification is not reduced.

CO PROCEDURE: SI

- 279 O

REACTOR TRIP INSTRUMENTATION FUNCTIONAL TESTS REU This revision cancelled this SI-93.2 was revised in ISBS to 05 instruction. The entire scoce of handle the startup requirments SI-27S has been included in SI-93.2 previously provided by SI-279. The and SI-93.

margin of safety as defined in the basis of any tecnnical specification is not decreased.

c3 PROCEDURE: SI

- 289 o

ULTRASONIC INSPECTION OF PRESSUR12ER RELIEF LINE REPAIR REU This revision cancelled this The surveillance requirements of 03 instruction. The requirements of this instruction have been this SI have been incorporated into transferred to SI-114.1. The margin SI-119.1.

of safety is not decreased.

co PROCEDURE: SI

- 400.01 O

LIOUID WASTE EFFLUENT BATCH RELEASE REU This instruction was revised to The changes made to this SI affect 14 provide instructions to allow the only minor changes in release shift engineer to declare the documentation and will not have any release radiation monitor inoperable consequence on plant safety. The when it is contaminated so a liquid dociaration of the release monitor release can be made. It was also as inoperable is provided fcr in the revised for clarification and minor technical specification and the corrections.

other changes are administrative.

The margin of safety as defined in the basis of the technical specification is not decreased.

t Page No.

37 02/22/87 SEQUOYAH NUCLEAR PLANT 1985 NRC ANNUAL OPERATING REPORT PROCEDURE' CHANGES DESCRIPTION SAFETY

SUMMARY

Go PROCEDURE: SI

- 410.04' O

WASTE GAS DECAY TANK RELEASE REV This instruction was revised to The only equipment involved is the 04

_ provide a more accurate method for utilization of the chemistry determining curies released and section's gamma-analysis system. The release rates, theory or method of pre-analysis and determining setpoints is not changed; only the method for determining what was actually released was changed. The margin of safety as defined in the bases of the technical specification is not decreased.

C0 PROCEDURE: SI

- 470.05 o

F.UXILIARY BUILDING IODINE SAMPLER FLOW ESTIMATION REV This revision cancelled this The margin of safety is not 01 instruction. The technical decreased because the technical specification requirements are being specification requirements have been covered by SI-407.2.

transferred to SI-407.2 (907.2~is in the review / approval cycle).

co PROCEDURE: SI

- 654 0

FIRE HEADER VALVE SEALS INSPECTION REU This instruction was revised to This change does not increase the 09 delete the SRO approval for the probability or the consequences of performance of this SI and to remove an accident or malfunction. The the revision numbers en the drawing requirements of the Administrativo references due to frequent revisions Controls Section, 6.8.1.f. of the of 'as-constructed' prints.

technical specification are still being met. The margin of safety is not reduced.

l i

i 9

h I

l s

4 4

a SUXWARY OF SPECIAL TESTS J

6 5

4 1

p

~

y' l g' l '

y

,, j

~ Page AOL

.02/22/57-

?v SEQUOYAM ESLEAR PLANT N$ 'r f*

1SS6,NRC ANNUAL. JPERATING REPORT SPECIAL TEST

<n, NESCRIPTION SAFETY SUMMANY N

co STI

- 01 s

o xSPECIAL TEST INSTRUCTIONS r

Thic revision Ancorporated changes This is administrative in nature and' I

resulting from the, biennial re>imw ar$ provides strict requirements for various changes due to recent.ruvlsions-preparation and conducting of special cf the NOAM ptit !!,csections 4.6.and tests. These requirements insure that

.4l9. This describea;the special test the probability of or the consequences l

-ptogram and its impiame9tation at of prebiously evaluated events are not

'Soquoyah Nuclear PLANT.

1.

incesased. The requirements of STI-1 insure that each special test is l

evaluated by qualified individuals k

prior to approval of the tests. These reviews and evaluations prevents f

's approval of a special test that could create a new unreviewed condition leading to an accident or malfunction.

i ST1-1 requires substantial control over i

special tests and their impact upon the

~

technical specifications. This contro1 insures that the margin of safety asl defined in the basis of any technicaI[

t specification is not reduced.

'/

g n

)

00 STI

- 02 o

ICE CONDENSER LOWER INLET DOOR LEAXAGE i

l Th10 instruction describes the method The lower inlet doces are not required for determining the ice concenser lower to be operational during mode 5 and S.

1 inict doces out inakage. It was The test configuration and performance performed while the unit was in made 5 did not increase the probability or er E.

consequences of a previously evalustaa i

accident nor caused a malfunction of equipment important to safety whils in modo 5 cr 6. The ice condenser icw'er inlet doors will be operational per technical scocification requirements prior tc entering made 4.

00 STI

- 05 o

DEGRADED VOLTAGE TESI FOR MFIU'S BRAKE SOLENDIDS Th3 purpose of this instruction was to The test was performed in a made where provide a detailed procedern for feedwater isolation is not required for 4

i tasting the motor brake rails for the any FSAR unalyzed accident. There is no m31n feedwater isolation' valves, requirement for feedwater inciation in mode 5-'The test only effected the l

brake r.cil and the parameters were monitored during all phases. Had damage to the coil been experinneed, necessary repairs would have been made prior to entrylinto mode 3.

3

.H

<t r

Page No.

2-

~02/22/97 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL-OPERATING REPORT SPECIAL TEST DESCRIPTION SAFETY

SUMMARY

00 STI

- 06 0

FIELD ~ TESTING OF 410 SS ULU STEMS.TO SCREEN FOR IMPROPER HEAT TREATMENT Th3 purpose of this instruction was to The hardness testing resulted in a ccccen.a selected number of 910

.small shallow indentation on the and or Ctoinless steel valve stems for near the and of each valve stem. The icproper heat treatment using field indentation does not affect the hnedness testing methods. This strength of the stem or the packing information will be evaluated to seal area. The operability of the

+

d3ttrmine whether wide-spread heat valves was unaffected by the testing.

trCatment problems exist at Sequoyah.

The testing was done without tagging l

Thic is in response to operating the valve or affecting the system Cxp3rience review, IE notice 85-59.

alignment. If any disassembly was required, the valve was removed from service under MI-11.9 for CSSC valve maintenance. The margin of safety was improved by identifying valve stems' that are susceptible to the stress corrosion cracking problems identified by IE notice 85-59.

t 00 STI

- 07 O'

WESTINGHOUSE DEMONSTRATION OF ICE CONDENSER SERVICING TOOLS Thio instruction peccided guidance for The ice ccndenser equipment integrity tha preparation and perec-mance of the was unchanged and the equipmant was Cxp2rimental demonstration of the inspected after the demonstration. The W;ntinghouss ice condenser basket margin of safety remains the same as CIrvicing tools in the Sequoyah unit 1 before the tool demonstration started.

ica condenser.

The ice condenser equipment was returned to the same condition it was in prior to the demonstration.

Lo*

STI

- OB o

GENERAL HARDNESS TEST FOR CSSC & NON-CSSC PRESS 8 NON-PRESS RETAINING PARTS i

l Th3-purpose of this instruction was to The hardness test made only superficial Ccrgen parts for improper heat indentations. The indentations do not trOstment using field hardness testing affect the integrity of the parts.

mIthods.

Technical specification requirements were not affected by this test.

l

. -..,.. -.- _. -.-,., -- -. - - - - -.:...-..-. i -, -

Page No..

1 02/22/L7 SEQUOYAH NUCLEAR PLANT 1986 NRC ANNUAL OPERATING REPORT SPECIAL TEST l

DESCRIPTION SAFETY

SUMMARY

l l-j c*

STI 09 I

'O PROOF LOAD TESTING OF ANCHORS IN HIGH-DENSITY CONCRETE I

Thio instruction was written to aid in The testing was performed to provide DNE's evaluation of proof Icad testing actual field test data for use by DNE

-cf cnchors in high-density concrete, in evaluating anchorages in high-density concrete. The testing of anchorages by this STI did not affect the seismic integrity to the extent of causing permanent degradation.

Therefore, the probability of an occurrence or the consequences of an accident or malfunction was not increased. The possibliity of an accident not already evaluated was not increased.

00 STI

- 10 0

COMPONENT COOLING SYSTEM INLEAXAGE SPECIAL TEST Thio component cooling water system This test did not contribute to CCCS) inleakage special test involved increasing the rate of equipment tCcting specific trains of safeguard failure since no alignment used was cquipment that use CCS cooling water, abnormal to the system design. The Thic was done to locate and document margin of safety was not adversely Cny in-leakage of radioactive water affected since the test did not degrade into the CCS.

system perforcance, c'

STI

- 11 o

PLANT COMPUTER ROOM UENTILATION TEST Thic instruction was written in order This test collected data required to to resolve safety parameter display make modifications to the plant cyctem CSPDS) availability problems as computer room ventilation system which rccommended in SONS' response to will increase SPDS availability.

Op; rating Experience Review - IE notice Increasing SPDS availability does not 86-10.

create any additional accidents or malfunctions. No margin of safety was reduced.._-

Faga - NJ..

2

.02/22/G7 SEQUOYAH NUCLEAR PLANT 1988 NRC ANNUAL OPERATING REPORT j

SPECIAL TEST SAFETY

SUMMARY

'. DESCRIPTION co STI

- 12 o

MAIN. STEAM ISOLATION VALUE SPRINGS

PROOF TEST This new special test instruction is to Performing this test did not impair the~

perform a compression-test on the main function'of the MSIU springs. It

'CtCcm isolation valve CMSIU) springs to insured continued realibility of the in;ure continued reliability of the MSIU springs for at least 950 MSIU springs for at least 960 additional. cycles. This test was

~cdditional cycles.

performed during cold shutdown made or refueling mode. This test did not decrease the capacity of the MSIVs*

function or degrade the margin of safety.

co STI

- 14 0

NDT OF IN PLACE CONCRETE PER ASTM STANDARDS C803 AND C80S - UNITS O, 1,

AND 2 Thic special test was to perform The test methods did not degrade the nondestructive testing.cf in place integrity of the structures and the concrete for category'l structures.

procedure insured no embedded conduit, component, or piping was jeopardized by this test. The possibility of occurrence or the consequences of an accident or malfunction of. equipment was not increased and the possibility for an accident or malfunction of a different type than any previously evaluated was not created.

00 STEAR 02 I

O SPECIAL TEST OF PREACTION SPRINKLER SYSTEM This revision cancelled this special The test has been conducted and is no tc2t.

longer needed.

co STEAR 03 0

DIAL INDICATOR METHOD ICE WEIGHING This revision cancelled this special This instruction is no longer needed.

tsat.

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.1 WJM8ER OF PERSDwwEL AND Pt& pen BY W0tK ANO JOS FJNCTIO4 2

PLANT! 51QUtts M;;LitR M.A;T 1996 1012 T9 ESSAY, F!BRGARY 5,1997 hurfEI.1 JF PEES 0*WEL (3 OR s 3 M-RE1)

T0 Tat MA4-EEN

................- P O=W A S T E PRCC E S$1ws -+-------.---------.-- -

- ~ ~ ~ ~. -

EneUP STsTION LTILITT CD)T2fCT

.T3TAL STATIJ4 UTILITY CONTkACT-TJTAL EMPLLY2E5 E M GYFC5 WJ OTHIRi Pfa5345 EMPLCfEES EMPLOYEES AMO OTHERS n-REMS 1AldTE 44hC* *E450hEL n2 1

0 18?

5.872 0.000 0 003 5.7!2 3PEAATING PE.150*ld.

23 1

5 25 5.177 0.3 3 1.(37 4.622 41*LTD PHYSICS PF51J44;L 43 0

2 43 1.571 0.300 0.000 1.515 SUPERWIS02f 2ER$0&tEL 1G 0

0 15 2 640 0.300 0.003 7 640 iN61N32RI56 PER50n1EL 12 0

4 15 0 020 0.100 0 002 0 022 no 27 ti 1

9 293 15 132 0.303 1.489 14 549 hC:1Z*UfL-----------------~~--~~~~~~----------------~---

SkOUP STATION LTILITY Co*TE!CT T3fAL STATI3N UTILITY CONTRACT TOTat irPLufEES I1PLOYEE5 Eko OfrtTRO PIR$145

!MFLCfEES EMPL1 FEES AND OTHERS n-EEF5 1AINTE46t40C Pt954*f L 12 0 0

I 125 18.189

0. 300 3.032 18.271 3?EteTING PER50tNi. i 20 0

C 23 0.L90 0.300 3.040 0 190 1EALTh Phf 3ICS Pies)1'fEL 22 0

C 2?

0.735 0.300 0.000 0.785 5UPERbISCRY.3EM 061IL 5

7 C

1?

0.724 0.150 3.00G

0. 914 26Ih2mEIa;5 pef'30p tCL 15 5

4 21 0.597 0.180 3.520 1.291 40 it.*

10 1

?C) 20.495 0.$30 3.632 21.411

' 00

= ras azz

=Js sust s=sytes esszes amazza osasses 7

M61 417 332 6113 455.435 15.562 72.673 544.8~5 Persons may be counted in more than one category.

4 prw k '

p t

i.

RJMER 37 PEE'ON<Et AM9 P51-kgM py uggc Agt JOB FJNCTIe4 3

PL A.IT SEQU(YnH WhCLEN PLagt 1936.

10:12 TUEstaV, FEmuaRf 3,1987 Nunei.1 bF 7!R50a:sEL D JE = 0 M4!1) idTAL Mai-REM G9007 5TATICN UTILITY CO*TPECT T0TAL STATI)4 U TILITY CONTR8CT TJTAL ErPLOYEES E.1PLGYE CS 30 CT;9ED5 Pv'15 ns EM7LofEES EMPL3YEES 4% OTHEAS M-Rett 5 MAIhif 42h*E Peps 0SiEL 20u4

'. 5 90 5023 355.751 0.364 P.070 363.90$

'JPE2 ATING P2 250 ME.

545 14 21 534 24.227 0.080 5.708 28.015 NEALTh PHf5ICS 3 Fidn FEL 251 5

2 265 31.317 0.145 3.C20 51 192 SLPLRbISCRf ?E253Fdit 357 159 J

54) 11.123 8.581 3.485 19.994 ENGIN1!EING 8Eh50*d!L 01%

212 575 1701 54.550 6.992 63.387 131.729 sia

=

s eu s

ssess aussas 3.=

===sess 4061 417 352 511]

453.433 15 552 72.570 544.815 Persons may be counted in more than one category.

I

'(

=

a

,i

-a----

NJMBER OF PERSONMCL anD P AN-REM BY I40u ANO JOB FRCTICM 4

%AWT: SE'JUCf AM KOLEeR % ANT 1985 10:12 TUES3AY, FE9tUA2Y 3,1987 TOTAL NUM3115 CF TNDIV110ALS l'

(> or = 0 m-Rem)

E;ouP S ta TIO1 UTILITY C01TRICT TOTAL PaINTEk11CE P!.150khfL 171 34 50 1055 C34R AT14G PEF 5 341EL 2 71 14 9

314 HI ALTH 8MY2IC 3 PTFS 'NNEL 54 4

1

$9 5'JPF;WI Cdy Fi25J'i> 2L 174 55 34 251 Et?GIM'E)IkG F:R5JN*IL 274 105 347 827 WTEJ 333 233 3333 1C54 211 441 2516 l

e e

l l

M19 R 3F P950NhE1 A'.0 P AN-PE% By l#0%E AND Joe FJWCTIO4 5

PLANT SEQUCYAH MICLEAR PLANT 1986 10!!2 TUE534Y, FEBRUART Iy 1987 kJd8ER OF PER30kNEL 0100 M-1EM)

TOTAL MAM-REM

-- ----- -------------- XJ a a f 1CT 02 G P S SU 2VE ! LL t wC E ----- -------- -

Group 571TIJ4 LTILITY CONTR8CT TOTAL STATI34 UTILITY CONTRACT T3TAL EnPLGfEEs SPL0yrES EPD OTHERS PER!345 EMPL0 FEE 5 EnPLOYEES ANO OTHERS It-RENS NAINTE4AhCE pea >0hcEL S45 1

15 552 27 722 0.303 1.502 31.307 JPE4ATING PEJ50 nae.

71

)

2 7%

11 713 0.300 3.066 11.044 miALTh Phf 5I:5 P2310*'8EL 41 C

C 47 1". 919 0 300 0.000 14.959 SUPEkWI5daf PER50h.EL OS P4 1

55 2 753 1 918 3.136 4.012 ENGIns[EItIG ?ER*JQ9 91L 72 17 CC 147 9.C33 2.436 17.617 29.051 1s 764 42 79 885 E3.255

4. 357 17.A31 91.993

.-.--- --- -.- -------- ------ M C = ? C U T I d i 1 tT 4 TE N 4 4 : ! -------------- ~~ ------- -

~ ~ ~ - - -

.EGJP STtTIO1 U TILITY 01%T2f:T TOTAL STATI34 UTILITY CONTRACT TOTAL EfdLLfff;

(*PLJftES mD OTw!PS PIP 5MS EMPLCfEES E=PL JYEES AND OT:tERS M-REN5 M&1mTEeAN;E pew 50httL 557

)

1C 575 159.091 0.300 6.807 151 39e DPE(ATIhG P21501ni.

73 0

5 75 4.512 0.000 1.727 6.239 diALTh PHYSICS PEED uEL 46 1

C 44 7.573 0.000 3.030 7.673 SUPERB!So tY PE410PtCL 25 24 1

53 2.225 0.436 3.032 2.663 EgGIN!!RIdb *Ea53Xt!L G4 9

62 115 0.515 1.104 16 591 23.910 4

10 7bi 33 C4 903 170 316 1 540 23.127 172.305 u

e

-- ----- -- --- -------- -- - - -- ~ - - -------- - --- -- #1 p I N-S E E VIC E I 15 P Y C T IO N - --- ------ ----- ---- --~ ~ ~----------

GROUP ST27101 LTILITY Cir.T?fCT TOTAL ST ATIJI4 UTILITY CONTRACT T3TAL EN 8LC YEE 3 E 9PL ;Yt '5 dhD OT1Ep; P2R5%5 En*LCrEE5 EMPL OYEIS AND OTHERS M-AEMS MAINTEeRNCE ped 516til 157 0

C 157 19.415 0 000 0.000 19.495 3PEGATING PEk5Dn.st.

15 0

0 15 3.019 0.330 0.000 0.019 HEA.Th PHf 5ICS PE8 5Ch.6TL IA 0

C 35 5.533 0.300 0.003 3.598 SUPiaWI501Y PER305 8EL 4

Li C

$2 0 055 5.044 0.003 5.082 EWGINEIRI:43 3:2SJA12L 27 11 2E 63 0.5t3 0.517 6.531 7.566 40 240 af 2E 33T 21.G58 5 561 6 511 35.750 jp

--- ----- ------- -- ~------ MC = 5 F E C 1 1L 1 A T w i E 14 N : s -- -------- --- ------~ ~ ~------------

.ROUP STATION L TIL T TY cueTH CT T)Til STATIJM UTILITY CONTRACT T JT AL 1

Ee'LCYiEs

?iPL ;YE i S 100 OT9EP'.

PE951N5 En/L0fEF5 EMPL3YEE5 AND OT9ERS.

M-REn$

i NAINTEsAhtE PEW 50m4?L

$49 1

11 531 124 907 0.000 2.251 127.158 JPH ATING PER50MNE.

G6 3

4 13 3.161 0.000 3.340 3.501 dE ALTh PHf 5ICS PEtile=EL 45 1

C 4?

2.519 0.005 3.000 2.524

$UPEwkI5Gif PE1 0> 4!L 13 12 1

41 0.593 0.527 3.000 0.920 EnGINiLPIM ?II:30>4EL E?

9 04 152 10.339 1 422 15.927 27.388 i

90 747 25 1CC 073 141 319 1 754 13.518 161.491 i

i I

pfM9ER 3F PER50N4EL 4;0 P AN-RFM BY WORK ANE JOS F34CTISE 6

PLRNT4 SEQUCYAH NUCLEAR

LAIT 1986 10?12 TUESHY, FEBRWARf 5,1987 hJimla 0F PERSONMEL (3100 M EN)

TOTAL MR1-REM

.... ~........... - ~........-.... -.~. ~. t o. W L S T E PROC E S S I M G ---~ --------------- ----- -~ ~-~~-------~

EkudP

$TATIO4 LTILITY COWTGA T TOTAL ST2TI)1 UTILITY ComIRACT total irPLufEE5 F1'LOYEES 44 QTdEP3 PIR53NS -

EM*LorEES EttPL3fE!5 ANO OTHERS M-REM 5 1AIaTEtatiCE PEkS4 tt 13!

3 0

131 5.7%

0 300 0.003 5.734 3PE44TimG PEi!501ME. i 15 0

3 17 3.135 0.300 1.532 4.437, MEALTP PHfSICS PZhilk..sL 65 3

0 45 1.350 0.300 0.000 1.369 50PikW1509f PER506tEL 10 0

0 13 2.G?3 0 000.

0.000

'2 623 ENGINE! KING PE2iC6 *EL 5

)

0 3

0.G10 0.300 0.003 0 010 m3 212 3

P15 12 840 0.300 1 332 14 172

-.......................................N=ggcu!L~--------------~-----.-------~---~~--~~-------

GRLUP ST2T104 L TILITY CJNTRACT T3TAL STATI3M UTILETY CONTRACT TOTAL dP#LOYEC1 E vtCYFd5 2:10 OTH P5 PERS315 EMpL0f EE S E4PLOYE!5 1NO OTHERS

' rt-RENS -

[

1AINTEdahCE P!kiakt:L 10 7 3

2 111 17 172 0.300 3 022 17.994 JPE2aTIhG /E450t,E.

17 0

C 17 J.190 0.130 3.030 0.190 dEALTD PHYSICS PCEi. lit r8EL 22 0.

C 22 0.T85 0.330 3 000 0.785 5UPExtI501Y ped %3WL 4

7 C

11 0.713 0 150 3.000 0.868 E=GIhEIRI/G PE25th4EL 1

2 2

16 0.567 0 175 3 503 1.242 4

ft3 1ct 9

4 174 20.232 0.325 3.522 21.379 m

=...

.... =..

8

!d93 145 29E 3334 436.120 13.637 65.411 516.868 Persons may be counted in more than one category.

l j

l i'

).

i PJH8ER OF PER50NME1 4ND PAM-4EM ffv WORK Awo J03 FJNCTIO4 7

L8ti: 5FQUCfAH NGCLF R *L84T 1986 10I12 TUESSAY, FEBRUARf 32 1987 huMRIR OF PER5'JhWEL Q100 M-UN)

TOTAL MA4-BEM GROUP ST;.TIDl4 UTILITY C0hT98CT T3Tal STATIM UTILITY CONTRACT TOTAL Ee#LOYEEi E".PL OYE IS AMD OT;4EPS PTR53MS EM*L0 FEES EMPL JYE E5 RNO OTHERS M-RENS MAINTE 4Ah0E ?!R50m4fL 2055 2

44 2102 345.921 0.303 F.652 353.596 JPE2ATINE P2A501ME.

255 0

15 271 22.I85 0.000 5.445 26.250 1EALTP PHYSICS PE5iMlEL 243 i

C 244 30.732 0.005 3.000 50 907

$UPEkk!$JRY PEJ50 heil B7 75 2

137 8.755

8. N5 3.138 16.968 Ih6IhIsrddG 7EpichtEL 245

'. 3 23E 513 28.657 5.554 55 156 89.177 as=,

=ss ans

==

s=

susess ausses

=

2390 145 215 5554 456 320 13 657 65.411 516 868 Persons may be counted in more than category.

1 1

M3MBER DF P,350N4% AhD P8E-REh RY WO48t est JOB FJIICTION 8

PLANT! SEQUCfAJ ECLten Pla1T 1986 10 12 TWESBav,FEsautef 42 1987.

TOT 3 NUMt"$ OF INDIVID'JSL5

{

(>100 alt 8 TIONRem)

G10D*

2 UTILITY C04 TRACT TOTAL 4

PtIhTENiNCE FG500FL 295 1~

16 615 C7524TI4G PEE 3GNdEL 71 0

5 76 h.ALTH aWy1IC3 p?Naa DEL 67 0

0 47 w

SJPERVIF.90f FI45JNNrL 19 29 1

47 F MIhEf 7IwG FIR $r' fart 53 7

101 175 333 m3 333 333 EJO 35 123 959 t

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ML20212J474

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