W3P87-1751, Rept of Facility Changes,Tests & Experiments for Mid-Yr 1987 Per 10CFR50.59

From kanterella
Jump to navigation Jump to search
Rept of Facility Changes,Tests & Experiments for Mid-Yr 1987 Per 10CFR50.59
ML20236F733
Person / Time
Site: Waterford Entergy icon.png
Issue date: 06/18/1987
From: Cook K
LOUISIANA POWER & LIGHT CO.
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
W3P87-1751, NUDOCS 8711020277
Download: ML20236F733 (52)
v • d • e


Text

,. .. _ _ , _

e T I 3..

l 1

Louisiana Power and Light Company Waterford 3 SES

. y. Docket No. 50-382 License No. NPF-38 t l REPORT OF FACILITY CHANGES, TESTS AND EXPERIMENTS

FOR MID-YEAR 1987 PER 10CFR50.59  !

I I

hDR P R

1EY7 g

,=- 4 -1 Louisiana Power and Light Company

'Waterford 3'SES

10CFR50.59 ANNUAL REPORT FOR MID-YEAR 1987 TABLE OF CONTENTS FACILITY CHANGES A. STATION MODIFICATIONS (SMPs)

Report No. Title

1. SMP-76 Boron Management / Liquid Waste Management
2. SMP-80 Gaseous Waste Discharge Rate and Pressure Control
3. SMP-195 Change Reactor Containment Building (RCB)

Sump Pumps to Submersible Sliding Rail Pumps

4. SMP-226 Broad Range Toxic Gas Detectors
5. SMP-232 Qualified Safety Parameters Display System (QSPDS)
6. SFT-316 Recirculation Line for Turbo Charger Lubrication Oil Filter
7. SMP-351 Addition of Sight-Glasses to Acid and Caustic Tanks
8. SMP-383 Emergency Diesel Generator Pressure Switches Test Connections
9. SMP-461 Boric Acid / Condensate Cross-tie 10._SMP-570 Oil Separator Improvements
11. SMP-578 4" Detergent Waste Line Relocation
12. SMP-721 Auxiliary Boiler Sample Piping
13. SMP-860 Radiation Shielding for Letdown Line
  1. 2CH2-60A/B
14. SMP-1058 Basemat Crack Width Monitoring
15. SMP-1165 Oil / Water Separator Improvements l

l i

_ --_- - _ _ _ --- _ a

7 . , - .i i

l Louisiana Power and Light Company Waterford 3 SES 10CFR50.59 ANNUAL REPORT FOR MID-YEAR 1987 TABLE OF CONTENTS (Continued)

A'. STATION MODIFICATIONS (SMPs)'

Report No. Title

16. SMP-1218 Turbine Generator Oil Pump Modification
17. SMP-1262 Feedwater' Pump Turbine Gland Steam Supply Drains
18. SMP-1332 Chemical Volume Control (CVC) Letdown Flow Oscillation
19. SMP-1353 RCP Motor; 011 Addition Problems
20. SMP-1359 Replacement of Waste Gas Decay Tanks Isolation Valves
21. SMP-1458 Second Pen to Pressurizer Level Recorder
22. SMP-1469 Control Board Controller / Indicator Scales
23. SMP-1506 Valve Extension Stem Assemblies for Moisture Separator Reheaters Vent Valves
24. SMP-1544 Reactor Power Cutback Loss of Load j
25. SMP-1688 Boric Acid Requirement for Technical Specification Compliance
26. SMP-1740 CIWA 28553 Remove Valve CD-MVAAA1701 1
27. SMP-1746 CIWA-28046, Documentation Correction for '

Recorders

28. SMP-1752 CIWA-28758 Moisture Separator Reheater Steam Temperatures j
29. SMP-1803 CIWA-030412, SP-102A and SP-102B Misdrawn on l Flow Diagram
30. SMP-1821 Emergency Dier.el Governor Cooling '.)

Modification (CIWA-30815)

, 31. SMP-1856 Component Cooling Water Monitoring and

Cleanup (Temporary Alteration Request.

l TAR-86-019) l l

I i )

~i -i.

Louisiana Power and Light Company I..'

Waterford 3 SES 10CFR50.59 ANNUAL REPORT FOR MID-YEAR 1987 Table of Contents (Continued)

B. PROCEDURE CHANGES  :

l

32. Plant Procedures,'CE-3-900 & CE-3-905
33. Plant' Procedures, MI-3-201 & OP-903-107
34. Emergency Operating Procedures Update C. SPECIAL EVALUATIONS
35. CPC/CEA Software Modifications l
36. Temporary Alteration Request, TAR 87-22
37. Temporary Alteration Request, TAR 87-23
38. Temporary Alteration Request, TAR 87-24
39. Temporary Alteration Request, TAR 87-31
40. Temporary Alteration Request, TAR 87-33

.41. Temporary Alteration Request, TAR 87-44

42. Temporary Alteration Request, TAR 87-57
43. License Document Change Request, LDCR 87-549
44. License Document Change Request, LDCR 87-567
45. License Document Change Request, LDCR 87-689 1

i l'

-111-l i

s -*

o- j L i l

i I

k Waterford 3 SES .j Mid-Year 1987 Report of Facility Changes, Tests and Experiments

.\

I i

SUMMARY

.i This report provides the Waterford 3 Facility Changes made pursuant to 10CFR50.59(a)(1) . The report covers the period from January 1, through June 18, 1987.

l No experiments or tests not described in the FSAR were conducted at Waterford 3 during the report period. None of-the items in this report represent an unreviewed safety question or change to the Technical Specifications.

The report identifies 45 Facility Changes (31 changes under the Station Modification program, 3 procedure changes and 11 special safety evaluations).

p.

it - s-e L

l. FACILITY' CHANGES A. . STATION MODIFICATIONS (SMPs)  !

f

1. Station Modification, SMP SHP-76, Boron Management / Liquid Waste Management i

i, Description of Change f Revise present piping for lon Exchanger Drain Header from Equipment Drain Tank to the Spent Resin Tank.

Reason for Change To ensure that the Ion Exchanger Drain Header and the Waste - a' Condensate Ion Exchanger Drain will-not contaminate the Boron Management System either chemically or with resin fines.

Safety Evaluation This change affects a non-safety,.non-seismic system. The change does not alter any previous accident or equipment malfunction analyses. This change does not create an unreviewed safety question, c

y l

T ',

' 2. Station Modification, SMP-80 SMP-80, Gaseous Waste Discharge Rate and Pressure Control Description of Change i

This modification replaced a flow indicating transmitter with a larger range flow indicating transmitter; added self-contained, direct ,

operated, in-line gas pressure regulator downstream of system isolation valve; modified scale on flow. indicator; and relocated manually operated needle valve.

Reason for Change To increase the maximum discharge flow rate to 50 SCFM and add an in-line gas pressure regulator'shich will eliminate the need of two ,

pressure controllers.

Safety Evaluation The modified portion of the system (with the exception of relocating existing manual operated needle valve) is non-safety related. The change does not alter any previous accident or equipment malfunction analyses. This change does not create an unreviewed safety question.

The radiological controls of the system are not affected and there is no impact on the 10CFR50, Appendix I analysis.

l

i

.I l

3. Station Modification, SMP-195 SMP-195, Change Reactor Containment Building-(RCB) Sump Pumps to Submersible Sliding Rail Pumps l

Description of Change Replaced the existing Containment Sump Pumps with submersible stainless steel pumps and a sliding rail system.

Reason for Change The Containment Sump Pumps must be reliable'and easily maintained. ,

The old' pumps were suspect to corrosion and could not be easily  !

maintained or replaced.

i Safety Evaluation This change affects a non-safety, non-seismic system. The change does not alter any previous accident or equipment malfunction analyses. i This change does not create an unreviewed safety question.

l l

l i

I

c . ., . - .

.: ,~

l' i

l:

I 4.. Station Modification,'SMP-226 SMP-226, Broad Range Toxic Gas Detectors Description of Change Installation of a new Broad Range Gas Detection System.

' Reason for Change The previous Broad Range Gas Detection System could not be made to operate properly.

Safety Evaluation This modification will inform operations in the event of a toxic gas entering the air shaft and isolate the control room from this hazard.

No new accident or malfunction is created nor is the consequence or 1 probabil!.ty of any previously evaluated equipment malfunction I increased. Therefore, no unreviewed safety questions exists.

i l

s; 'a.

f I

l-i

5. Station Modification, SMP-232 l l- SMP-232, Qualified Safety Parameters Display System (QSPDS)

'l.

l 1- )

i l

-l Description of Change Combustion Engineering revised QSPDS programming.

Reason for Change To update the QSPDS data base for providing more information to operators, to correct display ranges in QSPDS, and to improve the efficiency of the Plant Monitoring Computer in communicating with QSPDS microprocessors.

l.

Safety Evaluation 1

This change is to QSPDS software only. The change does not alter any l previous accident or equipment malfunction analyses. This change does not create an unreviewed safety question.

1 l

i

l 6.. Station Modification, SMP-316 SMP-316, Recirculation Line for Turbo Charger Lubrication 011 Filter I

J Description of Change A recirculation line with an orifice was installed between the turbo charger lube oil filter outlet and the engine cump. '

leason for Change To provide adequate recirculation of oil through the lube oil filter to allow preheating of the oil going to the turbo charger upon engine startup, thus decreasing bearing wear.

Safety Evaluation The Emergency Diesel Generators are required for the safe shutdown of the plant in case of loss of offsite power. This modification however, does not adversely affect the availability of the units.

Furthermore, the modification does not adversely affect the original design, it does not represent a new accident and has no impact on the accidents previously evaluated. There is therefore no unreviewed safety question for this modification.

i

, l

i'

7. Station Modification, SMP-351 1 SMP-351, Addition of Sight Glasses to Acid and Caustic Tanks i

i Description of Change Replaced the Make-up Demineralized Acid and Caustic Storage Tank level-meters with sight glasses and replaced the level switch for each tank ,

with a capacitance type level switch. The high level alarms were j deleted. l l

Reason for Change The tanks are manually filled so the sight glasses were added to provide better accuracy to prevent spills when filling and therefore there would be no need for the high level alarm. The level switch will be used to control the motor / pumps in case of a tank low level.

Safety Evaluation The modified tanks are components of the non-safety, non-seismic Demineralized Water System. The modification does not increase the possibility of an accident or create any new accident scenarios not previously considered. There is no unreviewed safety question.

l-

.g i

1

8. Station M5dification, SMP-383 6 SMP-383, Emergency Diesel Generator Pressure Switches Test Connections l

I Description of Change Added test connections and instrument shutoff valves to various Emergency. Diesel Generator (EDG) pressure switches and Amot instrument valves.

Reason for Change The installation of the test connections and instrument shutoff valves-was to facilitate instrument calibration and routine testing of the instruments.

Safety Evaluation The equipment affected by this SMP is considered quality related-safety related. By design, the trip function of the pressure switches is overriden when the EDG is in the emergency operating mode. Thus, failure of the new test connections or associated tubing and fittings will not prevent the EDG from responding to an emergency start signal.

Neither would failure to leave one or more of the isolation valves in the open position. Safe plant shutdown is therefore not affected by this SMP.

^T he change does not increase the probability or possibility of any accident scenarios or equipment malfunctions previously evaluated.

This change does not create a different type of accident or equipment malfunction from those previously evaluated and does not create an unreviewed safety question.  !

1

)

i l

__,--_---:-_--__-.._- . . _ _ - - )

i i l

t

9. Station Modification, SMP-461 SMP-461, Boric Acid / Condensate Cross-tie Description of Change l a) Relocated six pressure transmitters approximately four feet higher than the present location.

b) Removed springs from two check valves.  !

c) Provided an alternate vent path from the existing Boric Acid i Concentrator Distillate Cooler vent line to the Vent Gas Collection Header with a manually operated globe valve. i Reason for Change a) To ensure that no condensation / flashing will occur in the sensing lines of the pressure transmitters.

b) To reduce line losses to aid gas transfer flow from the Gas Surge Header to the Gas Surge Tank.

c) To provide an alternate vent path for the Boric Acid Concentrator Distillate Cooler.

Safety Evaluation The Boric Acid, Boric Acid / Waste and Waste Concentrators are not required for safe shutdown of the plant. The modification has no impact on the accidents previously evaluated in the FSAR. Providing an alternate vent path from the Boric Acid concentrator to the Vent Gas Collection Header (VGCH) has baen analyzed and although the  ;

radioactive inventory of the VCCH increases, it does not affect compliance with 10CFR20 limits. This modification does not constitute an unreviewed safety question. j l

l l

l l

i I

10. - Station Modification, SMP-570 i t

SMP-570,.011 Separator Improvements Description of Change .

s

.Made the following changes to the 011 Separator System:

1. Added Sight Flow Indicator to the 011 Separator, Oil Recovery Line. )
2. Added a Level Indicator Device to the Waste Oil Collection Tank with a high level shutoff interlock to the pump.

4 1

3. Added sampling connections at inlet and outlet of 011 Separator, q
4. Added permanent ladder and catwalk on Waste Oil Tank.
5. Added separate tank for Waste' Sludge Oil holding.

6.. Added concrete slab and curbing around both tanks and oil separator. j l

Reason for Change To minimize operational problems as well as to minimize the amount of 4 waste oil / sludge which must be removed by an outside vendor and to reduce the possibility of environmental permit violations.

Safety Evaluation  !

This system is non-seismic, non-safety and non-quality related. The system does not serve any safety function.

Failure of the system or its components would not jeopardize safe plant shutdown or any safety-related equipment. This change does not involve an.unreviewed safety question.

l i

I l

1' i ,,- ,

! :11. Station Modification,'SMP-578 SMP-578,.4" Detergent Waste Line Relocation Description of Change The 4" waste line connecting the floor drains in the decontamination room and hot machine shop to the laundry tanks was rerouted.

Reason for Change The line had been routed through the HVAC equipment room and the Health Physics count room (both non-radiation controlled area) which posed a radiological risk to personnel working in these rooms.

Safety Evaluation This modification involved non safety-related and non-seismic piping only, and does not affect the ability to safely shut the plant down.- A portion of routed piping passing over safety-related equipment is seismically supported. No new radiological release pathways were introduced. This change does not create an unreviewed safety question.

i I

?

-a_

t i

i 1

12. Station Modification, SMP-721 )

SMP-721, Auxiliary Boiler. Sample Piping i

l Description of Change l

Added two valves and rerouted a short segmentlof piping for provision of a new chemistry sample point in the auxiliary boiler mud drum.

l l

i

-l i

Reason for Change j l

To improve operation of the Auxiliary Boiler by. allowing for sampling the mud drum.

l 1

i l

Safety Evaluation This change affects a non-safety, non-seismic system. The change does q not alter any previous accident or equipment malfunction analyses.

This change does not create an unreviewed safety question.

i I

g :-

l l

l l

i

']! .

13. Station Modification, SMP-860 SMP-860, Radiation Shielding for Letdown Line #2 Cue-60A/B l

i 1

. Description of Change Added shielding around letdown line #2CH2-60A/B which is located in the letdevn pipe chase beneath the +21' RAB wing area. j l

i Reason for Change I Shielding added to reduce dose rate in the area.

l l

Safety Evaluation The addition of shielding over the letdown line improves the existing )

I design and does not create any new accident scenarios, nor does it increase the probability of any accidents previously evaluated. This change does not create an unreviewed safety question.

]

l l

)

1

14. Station Modification, SMP-1058 i SMP-1058, Basemat Crack Width Monitoring j i

I Description of Change Installed crack width monitoring devices on fifteen cracks in the basemat. Installed six basemat settlement monitoring points in the east and west cooling tower areas. Also reset the brass inserts and contact seats for all points installed so that the top of the brass

' insert is flush with the basemat.

i Reason for Change j To provide additional monitoring of basemat cracks and settlement.

The inserts were made flush to prevent accidental hits from invalidating the measurements.

Safety Evaluation l The changes made to the basemat monitoring devices do not alter any previous accident or equipment malfunction analyses. This change does not create an unreviewed safety question.

i 1

l l

1

p 3 :. .

15. Station Modification, SMP-1165 SMP-1165, Oil / Water Separator Improvements Description of Change This modification made the following changes to the 011/ Water Separator:
1. Changed the Separator Pack material to polypropylene.
2. Increased the angle of the Separator Pack plates.
3. Installed air lances in the Separator Pack.
4. ' Added a water / air injector to the Sludge Hopper discharge.

Reason for Chnnge Improve opert. tion of the 011/ Water separator.

l l

Safety Evaluation l This change affects a non-safety, non-seismic system. The change does not alter any previous accident or equipment malfunction analyses.

This change does not create an unreviewed safety question.

l l

l l

l l

l l

l l

s. -e 9.

s Jr

16. ,tation r

Modification, SMP-1218 SMP-1218, Turbine Generator 011 Pump Modification I 1

i t

I, Description of Change 1

Added a backup pressure switch to start the DC Pump.

4 .

j i

Reason for Change To ensure automatic pump start on low lube oil pressure. This modification of the system constitutes system enhancement.

Safety Evaluation This change affects a non-safety system. The change does not alter .

i any previous accident or equipment malfunction analyses. This change does not create an unreviewed safety question.

i

17. Station Modification, SMP-1262 l SMP-1262, Feedwater Pump Turbine Gland Steam Supply Drains i

i I

Description of Change Installed four continuous drain stations with plug resistant orifices in'the gland steam seal supply piping to Steam Generator Feedwater Pump Turbines.  ;

i

}

I l

~!

Reason for Change i

Provides for continuous drainage of the condensate formed in the i steamlines thereby preventing carryover into the turbine glands.

Safety Evaluation i This change affects a non-safety, non-seismic system. .This change i does not alter any previous accident or equipment malfunction  !

analyses. This. change does not create an unreviewed safety question.

.)

j I

l l

l 1

r.

.e. p .

I

18. Station Modification, SMP-1332 SMP-1332, Chemical Volume Control (CVC) Letdown Flow Oscillation 1

Description of Change Changed the trim of the CVC Letdown Flow Control Valves.

Increased the intermediate Letdown Pressure Relief Valve setpoint from 600 to 650 psig.

Reason for Change To improve letdown flow arceteristics.

Safety Evaluation Changing the trim of the CVC Letdown Flow Control Valves changes the stroke characteristics of the valves but not the actual minimum and maximum letdown flow. The changes to these valves do not affect . their seismic qualification nor their previously analyzed responses during an accident condition. The increase in the pressure relief setpoint does not exceed the system design pressure and in addition affected system components were reevaluated to demonstrate the components' suitability to perform safely under the raised set pressure conditions. These changes do not alter any previous accident or malfunction analysis, nor are any unreviewed safety questions created.

4

'.1 -

4, w

19. Station Modification, SMP-1353 SMP-1353, RCP Motor; Oil Addition Problems-Description of Change-This modification provided remote oil addition capabilities'for the upper oil reservoirs on the Reactor Coolant Pump motors. In addition, this modification replaced the existing instrumentation that provides level indication of the oil reservoirs to the plant computer. This modification consisted of routing tubing between the motor oil reservoirs and the two feedwater line penetrations in the secondary shield wall. Oil will be added by gravity feed and a hand pump, utilizing a portable oil can.

Reason for Change To provide the capability for remotely adding oil, when needed, to the ,

upper oil reservoir on the Reactor Coolant Pump motors during power '

operation, and replace existing motor oil level indication instrumentation with more reliable units.

Safety Evaluation Oil will be added to the reservoirs via non-safety-related, seismically supported stainless steel tubing that is to be routed from the feedwater line penetrations in the secondary shield wall to the oil reservoir fill points. Portable 5 gallon, FM approved safety cans with spring loaded valves will be temporarily placed on the platform

+46' elevation for quick connection to the tubing and filling of the l RCP reservoirs via hand pump. This operation would be repeated i for the other RCP if necessary. The cans will be removed from containment once filling activities have been completed.

The tubing will not represent an oil leakage hazard since it will only contain oil during the brief fill period, and since overfill provisions are present in the reservoirs below the fill point. The i presence of combustible lube oil in the RCP reservoirs is already considered in the Fire Hazards analysis. Oil will be present at platform +46' elevation by the opening of the feedwater line penetration in the secondary shield wall only for the duration of the fill activity. The hand pumps permanently mounted on the wall are reversible, therefore any remaining oil can be totally drained before removing the oil cans. Thus, no additional provisions are included for collection of leaking oil.

)

I i

.The probe and transmitter will be replaced with more reliable units i which will not alter the function of the system. The cable type will ]

L be changed to three conductor shielded, however, there will be no net 1 increase in cable footage and thus no net change in the combustible l

loading assumed in the Fire Hazards Analysis.

l The implementation of this modification does not affect safe shutdown l equipment nor create an unreviewed safety question.

l 1

1

20. Station Modification, S $ 3 9 -

SMP-1359, 'Ren} Acement ' of Waste Gas Decay Tanks Isolation Valves s

.gi I, g .

t  !

< 'l ~

i *

\ s a
3. S 3 :,

.c . j q )

it

.\..

Qsdl.pt'ionof' Change t, s

! \s . , .

. . Replaced eighteen Waste Gas Management System valves with tighter ,

.i ., shutoff design valves. Related changes to piping, support o and valve j N ' extension were made as needed.  ;

a '.)

s S

.q s Reason for Change The previously installed metal diaph'ragm stem sealed globe valves i leaked badly due to corrosion in uhe system and resultant seal damage. -

\ ause the valves are in lines w l O are cross-connected among the i 4

Tp'rN rfn Ancay tanks, equalization A pressure reaulted in the tanks.

bfdebt, le(

ancI .ft,f ase;}gressure

}n each tank equalization indivi!qally.prevented batch collection, decay

,,et ,y , ,

g a (g , * (

I '

Ii g

s;j/ps

,3 o

, \.

v f

4

%.o

s. - '

,.I' Sg(uty Evnjuation + <

{'l (i TQb inheren6 :yystem operation Co unchanged by this modification and s i will not comployse the capabili.3 to s'af ely shut down the plant. No l adverse effects ha quality oi safety result from this change. {

A i 1 i s

\r I i,s*  ;

h l

)I-

, ) s i  :

( j t) s

)y 1

\'

N ) , i f

_l . .

m 3 p} '[

(, YL t e

, 1 t- fj he i 1

k e

21. -Station Modification, SMP-1458

- SMP-1458, Second Pen to Pressurizer Level Recorder Description of Change Added channei "Y" signal of pressurizer. level signal to the control panel recorder.

Reason for Change Ensure trend capability for both "A" and "Y" channels of pressurizer level. This satisfied Human Engineering Deficiency HED-0234. .

l 1

Safety Evaluation j 1

The: addition of the second pen will place two safety channels on one f recorder. This is not in accordance with normal separation criteria. I J

However, a failure analysis was performed and it was determined that no adverse affects on the plant would occur from implementation of this modification. No unreviewed safety c,uestion is created by the modification.

i 1

1 ta 1

I i

I I

i I

________-_-_-_____ _ _ _ _ _ U

l

22. Station Modification, SMP-1469 SMP-1469, Control Board Controller / Indicator Scales 1

Description of Change Modified the following Reactor Turbine Generator (RTG) Board and Remote Shutdown Panel (LCP-43) indicators:

1. Pressurizer Pressure Controller Manual / Automatic Station changed from 0-100% to 1500-2500 psia on RTGB and LCP-43.
2. Master Steam Dump and Bypass Controller Manual / Automatic Station

. changed from 0-100% to 850-1050 psia on RTGB. l

3. Intermediate Letdown Pressure Controller Manual / Automatic Station changed from 0-100% to 0-600 psig on LCP-43. j
4. Condensate Flow Recirculation Controller Manual / Automatic Station  !

changed from 11,000 gpm to 10,000 gpm major increments on RTGB.

5. PI~CA-6702 SMA, SMB, SMC, and SMD Containment Pressure Indicators  !

changed from 0-40 psia to 0-30 psia on RTCB.

Reason for Change To provide consistent PAC manual / automatic station indication between the process indication and setpoint indication, and to provide quick channel comparisons.between the parallel indicators for the  :

Containment Pressure Indicators. I Safety Evaluation l This modification changes meter scales and recalibrates the meters.

The change does not alter any previous accident or equipment malfunction analyses. This change does not create an unreviewed safety question.

l l

l l

1 1

m______ _ .-

I p

j

23. Station Modification, SMP-1506 l SMP-1506, Valve Extension Stem Assemblies for Moisture Separator  !

Reheaters Vent Valves

. Description of Change Installed " Roto-hammer" valve stem extension assemblies on four Extraction Steam System' valves.

l

~l Reason for Change To minimize the potential of industrial safety hazard to the operating personnel because the valves had to be operated by someone standing on a pipe. ,

j Safety Evaluation l This change affects a non-safety, non-seismic system. The change does not alter any previous accident or equipment malfunction analyses, j This change does not create an unreviewed safety question.  !

i 1

i l

I i

.~

'24. ' Station Modification, SMP-1544 SMP-1544, Reactor Power Cutback Loss of Load Description of Change j

i Added capability to select either. reactor power cutback or reactor 1 trip on loss of load.

)

l i

l 1

Reason for Change i

)

i A previously reported change by Station Modification SMP-987 removed I the loss of load reactor power cutback and installed a loss of load l trip into the reactor trip on turbine trip circuitry. SMP-1544 j restored the reactor power cutback capability and retained the j capability for a loss of load trip.

{

i l

Safety Evaluation No credit is taken for loss of load turbine trip or reactor power cutback in FSAR Chapter 15 Accident Analyses. This change does not alter any previous accident or equipment malfunction analyses. This change does not create an unreviewed safety question.

1 4

o  !

f.

I l l l

J

1

1. .

1 i

25. Station Modification, SMP-1688
SMP-1688, Boric Acid Requirement for Technical Specification l- Compliance j Description of Change  !

Provided additional level indicator on each Boric Acid Makeup Tank.

l Reason for Change To provide backup level indication if the existing system fails.

Safety Evaluation This modification supports a previously approved Technical Specification change for the Boric Acid Makeup Tanks. A Bellows type Differential Pressure unit instrument was used. The process tubing tapped into the existing valved and capped taps on the outlet line of ;

each Boric Acid Make-Up Tank. .ASME III tubing was run in tube track j and supported by Seismic Class 1 supports and-was routed inside the ,

tank cubicle to the instrument which was attached to a seismic rack I mounted on the cubicle wall. A safety class break (Safety Class 3 to Non-Safety Class) was made at the new instrument valve installed just before the instrument. However, all instrument installation was in accordance with ASME III requirements. The change does not alter any previous accident or equipment malfunction analyses. This change does not create an unreviewed safety question.

1 l

1 1

A 3.

~l

26. Station Modification, SMP-1740 ShP-1740, CIWA 28553 Remove Valve CD-MVAAA1701 i Description of Change The Condensate Short Cycle Recirculation Line Drain Valve was removed and a cap was welded on the nipple, i

Reason for Change Vibration on the line was causing weld on'11ne to crack. Since this valve was not used for the intended purpose and generally not needed, the valve was removed to help eliminate vibration and weld repairs.

Safety Evaluation l

This change affects a non-safety, non-seismic system. This change does not alter any previous accident or equipment malfunction analyses. This change does not create an unreviewed safety question. I l

l

'27. Station Modification, SMP-1746 SMP-1746, CIWA-28046, Documentation Correction for Recorders Description of Change Corrected labels and indicator scales on Control Wiring Diagrams and Control Room Panel CP-7.

.[

1 i

Reason for Change l

To correct labels and scales of recorders on CP-7 which receive output from Qualified Safety Parameter Display System. -f

'i i

1 4

l 1

Safety Evaluation j l

This. change is to show correct description of the recorded signal and j does not affect the probability of an accident. No unreviewed safety l question is created by the modification.

l l

! 1 l

f L _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

28. Station Modification, SMP-1752

.SMP-1752, CIWA-28758 Moisture Separator Reheater Steam Temperatures f

Description of Change Changed the flow diagram, computer point descriptions, and the I&C i work packages to show the correct location of the steam temperature thermocouple on each Moisture Separator Reheater.

I l

Reason for Change Some of the documentation did not reflect the field locations of the thermocouple.

i I

Safety Evaluation l i

This change affects a non-safety, non-seismic system. The change does l not alter any previous accident or equipment malfunction analyses.

This change does not create an unreviewed safety question.

A i

a 1

i i

i l

29. Station-Modific.ation, SMP-1803  ;

SMP-1803, CIWA-030412, SP-102A and SP- Q2,B Misdrawn on Flow Diagram-l 1

Description of Change Revised flow diagram to indicate correct solenoid return valve number i for each containment sump pump.

Reason for Change i

Flow diagram'vas incorrect.

l i

l Safety Evaluation This is a drawing change only. It will not increase the probability or consequences of any accident to the plant. The drawing change does not create an unreviewed safety question.-

r

[c p.

~

(- - .

-30. Station Modification, SMP-1821

'SMP-1821,-Emergency Diesel Governor Cooling Modification (CIWA-30815)- i l-l I

l Description of Change-i Changed both Emergency Diesel Generators cooling water to the governor oil heat exchanger from the Component Cooling Water System to each ,

L Diesel Jacket Water System. I Reason for Change Per vendor request because the cooler Component Cooling Water made governor adjustment difficult as a result of a wide variation in governor oil viscosity.

Safety Evaluation This modification was installed at the recommendation of the Diesel Generator vendor and the change was installed in accordance with the original equipment specifications. No new accident or malfunc',fon is created nor is any previously evaluated equipment malfunction increased. Therefore, no unreviewed safety question axists.

l

]

l

'31. Station Modification, SMP-1856-SMP-1856, Component Ccoling Wata.r Monitoring and Cleanup (Temporary A1teration Request, TAR-86-019)

+

f 1

l Description of Change Installed a corrosion monitoring test loop between valves CC-550 and CC-559 in the Component Cooling Water System in the secondary lab and installed a cleanup loop between CC-513 and CC-529 and updated flow  !

diagrams. l l

I 1

Reason for Change To allow for clear.up and monitoring of corrosion rates in the ]

Component Cooling Water System. 1 1

l l

I Safety Evaluation This additional equipment tied into pre-existing valves in the i non-safety /non-seismic portion of the Component Cooling Water System. j The change does not alter any previous accident or equipment i malfunction analyses. This change does not create an unreviewed l safety question.

\

l l

1 l-

B '. PROCEDURE CHANGES

32. Plant Procedures, CE-3-900 & CE-3-995 '

CE-3-900 (Rev.3), Operation of the Post Accident Sampling System CE-3-905 (Rev.2), Testing and Maintenance of the Post Accident Sampling System Description of Change Complete re-write of both procedures to provide proper direction for operation, testing and maintenance of the Post Accident Sampling System-(PASS) to accommodate major modification made to the system and controls.

Reason for Change The system as installed could not be effectively tested until commercial operation. Testing conducted during the first cycle of operation. identified that quantification of dissolved gas content in the continuous sample was difficult to achieve due to inherent system design.

Safety Evaluation Implementation of these' procedure changes along with the associated hardware changes retains in-line instrumentation to sample and analyze the process stream constituents for pH, dissolved oxygen and hydrogen.

The modified system provides sampling capability and radiological and chemical analysis to meet the original design basis described in FSAR section 9.3.8. 3 i

Grab sampling remains available to permit diluted and undiluted  !

samples to be taken for laboratory analysis of chlorides, boron and  ;

various radionuclides. With the exception of the individual grab {

samples, all controls for the operation of the sampling system j originate from the Process Control Panel which contains all the readout devices for the analyzers and instruments,

)j l

Discharge of the liquid sample flow is directed to either the radwasto f tanks or the containment sump. Gaseous samples / residues are routed l either to the Gas Surge Tank or returned to the containment at- I mosphere. Therefore, no new unmonitored release paths are introduced. l The revised system operation meets the requirements of Technical

, Specification 6.8.4(d), therefore, no changes are required to the Technical Specifications.

The changes made to the PASS system are consistent with the requirements of NUREG-0660, NUREG-0737 and the guidelines of Regulatory Guide 1.97 Revision 3. These changes do not alter any accidents or equipment malfunctions from those previously analyzed.

The changes do not decrease any margin of safety and thus does not create an unreviewed safety question.

L________

1 I

i

33. Plant " meedures, MI-3-201 and OP-903-107 i

h! " 201 (Rev.4, Change A), Plant Protection System Calibration l

OP-903-107 (Rev 4, Change B), Plant Protection System Channel )

Functional Test Description of Change  ;

Change the Hi Log Power Pretrip setpoint from -4.699 Vdc to -6.398 Vdc.

Reason for Change This change was implemented to accommodate low power physics testing for Cycle 2 fuel. The purpose was to clear pretrip indication during low power physics testing. The change was only in effect until the completion of testing.

Safety Evaluation l'

During normal operation, the pretrip setpoint is more than 2 decades below the trip value to provide the operator with advance notice of j approach to the trip value. Some low power physics testing is  !

performed in a power range slightly above the normal pretrip setpoint. i Adjusting the pretrip to a higher value closer to the trip value i during low power physics testing will remove the unwarranted actuation of a pretrip during testing but will still provide the operator with notice of approach to the trip value should there be an inadvertent increase in power. In addition, administrative controls in procedure j NE-02-003 (Post-Refueling Startup Testing Controlling Document) are in j place to keep reactor power below the revised pretrip value.

]

The safety function provided by the Hi Log Power Trip is unaffected by the pretrip setpoint change. Therefore, the probability of occurrence 1 and/or consequences of an accident evaluated in the FSAR or equipment malfunction will not be increased by the change. The changes do not-create an unreviewed safety question.

l l

r L

l a *

34. Emergency Operating Procedures Update Description of Change j

.Several changes were made to the Emergency' Operating procedures which include OP-902-000 through OP-902-008. The changes made incorporate j the run two-trip two Reactor Coolant Pump philosophy, Reactor Vessel '

Level Monitoring System, the option of using the Auxiliary Feadwater 1 Pump in place of Main Feedwater or Condensate Pumps, restoration of l Dry Cooling Tower Sump Pumps following a loss of offsite power;, steps for Steam Generator U-Tube voiding and operations of CCW valves on SIAS, CIAS, and CSAS and MSIV Hydraulic Pump power supply operations due to station modifications.

Reason for Change The reason for the changes are'to:

1) incorporate changes identified in Revision 2 to the Combustion Engineering Emergency Procedure Guidelines (CEN-152), and l
2) incorporate changes to operating steps to account for station modifications.

Safety Evaluation In accordance with Supplement I to NUREG-0737 the Combustion Engineering Emergency Procedure Guidelines were submitted to the-NRC

]

in two submittals dated May 8, 1984 and November 26, 1984 from the J Combustion Engineering Owners Group. A Safety Evaluation Report was ) '

issued by the NRC dated April 16, 1985 entitled " Supplement I to the SER for CEN-152, Combustion Engineering Emergency Procedure Guidelines". Because the guidelines have received prior NRC approval a specific safety evaluation was not performed for individual

- procedures. Rather, a validation process was implemented to ensure that the plant procedure as developed, utilizing the Procedures Generation Package, reflected the NRC approved guidelines. This validation process is documented in LP&L memorandum W3087-0004 dated January 12, 1987 from L.W. Myers to the Plant Operations Review Committee (PORC).

l The original Emergency Procedures were written in anticipation that changes would be made in a future revision to CEN-152. Therefore, j consideration was given at the time, to writing steps and sequencing steps to allow for relatively simple incorporation of the Revision 2 l changes of CEN-152.

I l

l l

l L__-_-___-__

~e;  :.

C.- SPECIAL EVALUATIONS  :!

35. CPC/CEAC Software Modifications i

Description of the Change

, A Variable Overpower Trip (V0PT) algorithm has been added to the i UPDATE program to improve the CPC response to transients with rapid power increases. The V0PT alogrithm uses an auctioneered power to generate a trip setpoint that is larger than the auctioneered power by 1 a constant offset at steady state. I Modifications were made to the Asymmetric Steam Generator Transients l (ASGT) algorithm to improve its response to asymmetric temperature transients. The ASGT trip setpoint has been made power dependent and the new algorithm adjusts the measured cold leg temperature difference for RTD response time and.for RTD errors. In addition, the ASGT trip was modified such that it was separated from the DNBR calculation and l made an auxiliary trip.

Modifications were made to several of the programs to initiate the CEA withdrawal prohibit (CRP) prior to exceeding the deadband for CPC l response to any misoperations such as a single CEA deviation, out-of-sequence group insertion, excessive part-length CEA insertion or significant deviation between subgroups within the same groups.

i The selection of the set of spline functions for the synthesis of core l average axial power distribution was modified. The selection process ,

was tailored to reflect the range of typical shapes encountered during i a fuel cycle. This modification permits the synthesis to follow the  !

actual power shape in the plant more closely through the use of l additional spline function sets. ]

I l

The algorithm used to calculate reactor coolant mass flow rate was simplified to use only the reactor coolant pump speeds, primary coolant specific volume and the hot leg temperature. Simplifying the j calculation and eliminating the flow projection reduces the time l required to calculate flow and thus reduces the loading on the CPC j central processing unit. l The data base constants previously used in the CEAC program provided unique penalty factors for both DNBR and LPD for many combinations of l deviation direction, deviated CEA and general CEA configurations. A l reduced set of penalty factor data vill be used in the future to l simplify the analysis that generates the CEAC data base.

The POWER program was modified to calculate a hot pin ASI based on actual excore signals at powers below the substitution point. This low power ASI is for operator information only and is not used elsewhere in the CPC. By monitoring this value, the operator can assure that ASI is within the acceptable range prior to increasing power above the switchpoint.

L.

c. - - - . - - -
35. (Continued) - CPC/CEAC Software Modifications Reason for Change The CPC programs were modified to support use of reload data which ,

consists of constants that are typically fuel management, analysis i methodology or hardware dependent. They are not expected to change on J a cycle-to-cycle basis. The reload data block constants were l extracted form the CPC/CEAC software and were made disk resident to

_ ]

simplify modifying the constants should it be necessary in the future. l This will eliminate the need for software changes should any of the  !

reload data block constants require change.

Safety Evaluation The changes identified above were part of the CPC Improvement Program as identified in Combustion Engineering documents (CE submittals to )

NRC by letters dated August 30, 1985 and October 18, 1985)

CEN-308-P-A, "CPC/CEAC Software Modifications for the CPC Improvement Program", April, 1986 and CEN-310-P-A, "CPC and Methodology Changes for the CPC Improvement Program", April 1986. These reports were submitted to the NRC and a Safety Evaluation was issued by the NRC.

The Safety Evaluation was included in a letter from Herbert N. Berkow of the NRC to A.E. Scherer of Combustion Engineering dated March 12, 1986, titled " Acceptance for Referencing of Licensing Topical Report CEN-308-P and CEN-310-P, "CPC/CEAC Software Modifications for  ;

the CPC Improvement Program" and "CPC and Methodology' Changes for the 1 CPC Improvement Program".

A safety review of the WSES-3 Cycle 2 CPC/CEAC software changes package was performed. The determination was that the package was I complete and had been developed in accordance with NRC approved procedures. Futhermore, it was determined that:

1) these modifications do not change the design, functions and/or operation of the system as described in the WSES Cycle 2 Reload Analysis Report (RAR);
2) these modifications do not change any procedures as i described in the RAR;
3) these modifications do not result in the conduct of test or experiments not described in the RAR; and
4) these modifications do not require a change to the Technical Specifications.

Based on these considerations, installation of the CPC/CEAC software modifications as described above does not result in an unreviewed safety question.

i

'l i

36. .. Temporary Alteration Request, TAR 87-22 TAR 87-22, Use GWM-116 Sensing Line to Control Valve GWM-114 to Maintain-Gas Surge Tank Pressure Description of Change-Utilize the controller from valve GWM-116 to control valve GWM-114.

The sensing line to GWM-114 was removed and capped. A constant pressure of 15 psig was applied to GWM-116 to keep this valve open.

GWM-114 is used to control pressure and flow to the Gas Surge Tank.

GWM-112 is used to control Volume Control Tank pressure.

Reason for Change Valve GWM-116 fails to close. It is not functional for controlling pressure in the Gas Surge Tank.

Safety Evaluation GWM-116'and GWM-114 are not required for safe shutdown or to maintain safe shutdown and are not used to minimize the probability of an accident. The safety function of these valves is to maintain 1 integrity. FSAR section 15.7.3 describes the limiting faults as they affect this system. This temporary alteration does not alter the methodology or the consequences of this safety evaluation. As a result.this temporary alteration does not increase the risk to the health and safety of the public.

)

)

)

i i

l I

i 1

j

_ _ _ - _ - _ _ - . - - l

l i-j- 3 7. . Temporary Alteration Request, TAR 87-23 TAR 87-23, Provide Alternate Discharge Path For out of Specification Component Cooling Water Description of Change Provide a. temporary tank, pump and connections to the Component  !

Cooling Water system to allow for sampling prior to discharge to the Regenerative Waste Sump. I Reason for Change This change was necessary to' assist'in reestablishing proper water chemistry in the Component Cooling Water system after the first refueling outage. Because the system was laid up, proper chemistry I

required for operation was not maintained. This change was neceasary only until proper water chemistry was restored.

Safety Evaluation Processing of the Component Cooling Water was performed on a batch basis. At no time was the safety function of the system compromised or altered. Batch processing allowed the system to automatically compensate for the volume removed for processing. The safety function provided by the Component Cooling Water system was unaffected by this temporary change. Therefore, the probability of an occurrence and/or the consequences of an accident are not increased by this change. .

I i

i a

l l

l 1

l l

I

. .. i i

1

38. Temporary Alteration Request, TAR 87-24 j TAR 87-24, Reroute Secondary Sample Tank Discharge to Turbine Building Floor Drain to Allow For Monitored Discharge

)

i Description of Change Install a temporary connection to route the secondary sample tank discharge to the turbine building floor drain system instead of being i routed to the hotwell.

Reason for Change i i

To provide'for sampling of the tank discharge before releasing the contents to the environment.

Safety Evaluation The Process Sampling System, part of which is the Secondary Sampling System, is not essential'for plant shutdown as described in the FSAR. j Rerouting discharge of the Secondary Sampling Tank discharge to the j floor drainage system instead of the main condenser will ensure that .]

the discharge is monitored for radioactive contamination prior to release to the environment. This change does not alter any accidents or equipment malfunctions from those previously analyzed. The results of the-safety evaluation identify that this change reduces the potential for discharging contaminated effluents and that there is no ;

increase in individual or cumulative occupational radiation exposure. ]

The probability of an occurrence and/or consequences of an accident 1 are.not increased by this change. ]

j l

l l

1 l

c l

l l

l

)

t j

l 1

l i

39. Temporary Alteration' Request, TAR 87-31 j 1

' TAR 87-31, Install Temporary Flexible Hose To Route Leakage Past I CVC Valve to Equipment Drain Tank l

.)

Description of Change Install a temporary flexible hose downstream of CVC-MVAA-204 to divert leakage from the Equipment Drain Sump No. I to the Equipment Drain Tank.

Reason for Change This change was necessary to be able to more accurately quantify the leakage of valve CVC-MVAA-204 and to prevent noble gases and other gaseous nuclides from escaping to the Reactor Auxiliary Building atmosphere.

Safety Evaluation The portion of the line affected is downstream from the CVC valve and is considered a non-safety line. Since no modifications are being made to valve CVC-204, it retains its original safety function of maintaining integrity. Since no changes are made to safety related piping, this change does not alter any accidents or equipment malfunctions from those previously analyzed. This change does not decrease any margin of safety and thus does not constitute an unreviewed safety question.  !

l I

l l l

L. _ _ _ _ _ _ _ - _ _ - _ - _ _ . - .__ __ - _- _ _ -

0 e

40. Temporary Alteration Request, TAR 87-33 l

TAR 87-33, Operation of The Boric Acid Make-up System l

Without All Heat Tracing Operable Description of Change-This change removed heat tracing and insulation on the Boric Acid Make-Up System Tanks (BAM), disabled alarms and reprogrammed recorders to skip the points disconnected.

Reason for Change This change sas necessary to allow for repair of leaks and provide for cleaning of the BAM tank rooms.

Safety Evaluation Change to the WSES-3 Technical Specifications were requested'in'a letter dated August 20, 1986 and supplemented with two letters dated ,

October 6, 1986. The request was for removal of the requirement for a heat tracing circuit and reduction of the boron concentration requirements for the BAM system. License Amendment 10 was j subsequently issued by NRC on January 8, 1987 along with an accompanying Safety Evaluation Report. This license amendment preceded the implementation of the temporary alteration; however, system design and operating procedures had not yet been revised. The j safety evaluation for the Temporary Alteration Request references the i safety evaluation performed as part of the Reload Analysis Report .

(RAR) and the safety evaluation accompanying License Amendment 10 to {

the WSES-3 Technical Specifications. The results of these safety evaluations identify that this change involves no significant increase in the amounts of any effluents that may be released and that there is ,

no significant increase in individual or cumulative occupational radiation exposure. As previously isst.ed, the amendment involves no significant hazards consideration. The changes made as the result of this TAR are within the bounds of the USES-3 Technical Specification changes in License Amendment 10.

W

i

.. ^ .-

. 41. Temporary Alteration Request, TAR 87-44 TAR 87-44, Provide Mechanical And Electrical Interfaces For New Temporary Ecolochem' Plant Water Processing System l 1

L Description of Charige To provide mechanical and electrical connections for the' Temporary i Ecolochem Plant Water Processing System. All connections enable the j existing design to be utilized to provide flowpaths to the clearwell, i the clearwell transfer pumps, the degasifier, and the degas pumps. I i

Reason for Change The original system as installed was unable to provide adequate capacity for plant needs. The costs associated with maintaining the installed system were greater than the cost:of contracting the water ,

processing to an outside vendor. The temporary modification was made  !

on a trial basis only to provide time for an evaluation of the contracted services. The temporary design is such that if necessary, minimal effort is required to switch back to the permanent system.

Safety Evaluation Implementation of this temporary change does not alter or. degrade any safety analysis or equipment required for operation or shutdown of the plant. The temporary process meets the system design as stated in FSAR section.9.2.3. This system serves no safety function and is not required to achieve safe shutdown or mitigate accidents.

i i

l

_ = - _

3 :-

. .o i

42; Temporary Alteration Requent, TAR 87-57 l

-TAR 87-57, Relocate Switchyard Fence To Eliminate i Gate In-Corner Of Switchyard Description of Change l l

Relocate existing switchyard fence in a corner of the switchyard bordering the isolation zone along the west side of the switchyard.

-Reason for Change I To provide enhanced security monitoring of the isolation zone and to eliminate an existing gate in the northwest corner of the j switchyard, j Safety Evaluation Implementation of this change _does not alter the protected area fence ,

or any of the equipment required for implementation of the Physical -)

Security Plan. The fence moved is a non-safety, non-quality related )

fence which protrudes into the isolation zone for the Protected Area Fence. This modification will reduce the possibility of a malfunction j I and will reduce the capability for a breach of the security system. l As such, this change does not alter any accidents or equipment malfunctions from those previously analyzed. This change does not decrease ~any margin of safety and thus does not constitute an )

unreviewed safety question. j 1

l i

-l l

l i

1 1

i l

1 i

- ___________-_________n

43. License Document Change Request, LDCR 87-549 LDCR'87-549, Clarification of Controlled Ventilation Area System (CVAS) Drawdown Time ,

Description of Change Revised the FSAR to change the CVAS drawdown time from "45 seconds following'an SIAS" to "60 seconds (including diesel start and sequencer' times) following an SIAS".

Reason for Change  !

To clarify an existing criterion.

Safety Evaluation FSAR Section 6.5.1.2.1.2 currently states that the design of the CVAS  !

is " based on the requirements to evacuate the controlled ventilation area to -0.25 inches wg (water gauge) within approximately 45 seconds following an SIAS". This requirement has been interpreted as not including the time required for the diesel generator to start and sequentially load the CVAS (as would be required during an SIAS coincident with a loss of offsite power). This is consistent with the SER which found the CVAS design acceptable based on its ability to achieve a -0.25 inches wg differential pressure within less than 60 seconds. ,

However, even taking a conservative approach, it has been determined that a time period of greater than 45 seconds in the amount of time it takes the CVAS to decrease the controlled ventilation areas to at least -0.25 inches wg differential pressure will not affect either the offsite doses associated with the LOCA or the habitability of the controlled ventilation areas. In fact, as long as the CVAS was able to reduce the controlled ventilation areas to the prescribed negative ,

pressure prior to recirculation actuation (approximately 30 minutes),

the dose analysis presented in FSAR Section 15.6.3.3. would remain valid. Therefore, the consequences of an accident previously evaluated in the FSAR will not be increased.

1 4

1 l

l I

l 1

. e l

j i

License Document Change Request, LDCR 87-567 44.

LDCR 87-567, Change Maximum Alarm Setpoint for Area Radiation Monitor Description of Change Revised FSAR to change Maximum Alarm Setroint for ARM-IR-5004 (RAB E1.-4ft. MSL, Column K-2A) from 5 to 7.5 mR/hr. i l

Reason'for Change  !

Due to unexpectedly high background radiation readings.

4 f

Safety Evaluation [

This change is on a non-safety related monitor, and the change does not affect system operation. The change is still more conservative

.. than equivalent safety related setpoints. The monitor is not a Technical Specification instrument and the setpoint does not affect i any other system. .

l 1

t

.i l

f i

i I

l 3

l t  ;

i  :

L---__-______________ l

44 .

  • i
45. License Document Change Request, LDCR 87-689 LDCR 87-689, Revise FSAR To Make Turbine Valve Inspection Frequencies Consistent With Technical Specifications Description of Change Revised Section 10.2.3.6 of the FSAR to be consistent with the Technical Specifications concerning the turbine valve inspection period. The FSAR indicated that all valves are inspected at least once every 36-39 months, however, the Technical Specifications section .

4.3.4.2(d) requires this inspection be conducted only once in every 40 }

months. l Reason for Change l

To make the FSAR consistent with the Technical Specifications.

Safety Evaluation The safety concern with turbine valve testing has to do with the potential generation of turbine missile which may affect safety systems. The only credible turbine accident which could affect safety ;

related equipment is the generation of missiles due to turbine overspeed. The probability sf turbine generated missiles is evaluated ]

j in FSAR Section 3.5. This analysis takes no credit for the turbine "

Overspeed Protection System (OPS) operating. Turbine valve inspections help assure the OPS will function properly. Since the l analysis takes no credit for OPS operation, the probability of missile I generation is not affected by this change to the FSAR. As such, this change does not alter any accident or equipment malfunctions from those previously analyzed. This change does not decrease any margin i of safety and thus does not constitute an unreviewed safety question. l l

- - ~ ~ - _ - _ _ _ _ - _ l

R2fer: 10CFR50.59 LOUISI POWER &AN A / 317 LIGHT NEWBARONNE STREET ORLEANS, LOUISIANA P. O. BOX 60340 70160 *

(504) 595 3100 UrfuNfysNM October 27, 1987 W3P87-1751 A4.05 QA U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 1987 Report of Facility Changes, Tests and Experiments i

References:

LP&L letter W3P87-0595 dated 3/31/87, subject: 10CFR50.59 Report for 1986.

Enclosed is the mid-year 1987 Report of Facility Changes, Tests and

'~

Experiments for Waterford 3 which is submitted pursuant to 10CFR50. 59 (a) (1) . This report covers the period from January 1 through June 18, 1987.

As mentioned'in the referenced letter, LP&L submits this mid-year report with a review cutoff date of June 18, 1987 which is identical to the date used for the annual FSAR update required by 10CFR50.71(e). As such, future annual reports per 10CFR50.59 will use a cutoff date of June 18 consistent with FSAR updates.

l If you have any questions regarding this report, please contact C.E. Wuller, Operational Licensing, at (504) 464-3499.

Very truly yours, Y

K.W. Cook Nuclear Safety and Regulatory Affairs Manager KUC:CEW:pmb Enclosure i

cc: R.D. Martin, NRC Region IV J.A. Calvo, NRC-NRR J.H. Wilson, NRC-NRR NRC Resident Inspectors Office j E.L. Blake fy i W.M. Stevenson "AN EQUAL OPPORTUNITY EMPLOYER"  !

- - - - -__ - - - _

Retrieved from "https://kanterella.com/w/index.php?title=W3P87-1751,_Rept_of_Facility_Changes,Tests_%26_Experiments_for_Mid-Yr_1987_Per_10CFR50.59&oldid=3572201"