Text

Forwards Revision to Inservice insp-pump & Valve Testing Program Representing Present Program Status
	ML19259A594
Person / Time
Site:	Brunswick
Issue date:	12/21/1978
From:	Utley E; CAROLINA POWER & LIGHT CO.
To:	Ippolito T; Office of Nuclear Reactor Regulation
References
	GD-78-4354, NUDOCS 7901080165
	Download: ML19259A594 (62)
	v • d • e

.

U 3

Carolina Power & Light Company December 21, 1978 FILE: NG-3514 (B)

SERIAL: GD-78-4354 Mr. T. A. Ippolito, Chief Operating Reactors Bracch No. 3 Office of Nuclear Reactor Regulation Division of Operating Reactors United States Nuclear Regulatory Commission Washington, DC 20555 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 & 2 DOChTT NOS. 50-325 & 50-324 LICENSE NOS. DPR-71 & DPR-62 IN-SERVICE INSPECTION - PUMP & VALVE TESTING PROGRAM

Dear Mr. Ippolito:

On September 5,1978, Carolina Power & Light Company submitted a revised pump and valve testing program. As a result of continuing analysis, review, and implementation, CP&L has found it necessary to revise that program. The current revision is attached.

Attachment A to this letter summarizes the pump and valve testing program and details the information contained in the attached tables.

The pump and valve testing program is being conducted in accordance with Subsections IWP and IWV of Section XI of the '74 edition of the ASME Boiler and Pressure Vessel Code through the U mr,1975 Addenda, except for specific relief requested in acsordance with 10CFR50.55a(g)(5)(iii) which is identified in Attachment B.

The attached program represents the status of the pump and valve testing program at this time. As required additions or changes are identified, we will present the necessary information to you.

Yours very truly,

- - /

/

'E/E.Etleyug Senior Vice President RPR/j nh*

Power Supply Attachments d

790108 o Ko f o-411 Fayettevme Street

P. O Box 1551 + Raleigh, N. C. 27602 M2%%%u w A *b"iW2 w.aZ w"d.TIL M

Attachment A ASME SECTION XI PUt!P & VALVE TEST PROGRAt!

BRUNSWICK STEA?! ELECTRIC PLANT The pump and valve testing program shall be conducted in accordance with Subsection IWP and IWV of Section XI of the 1974 Edition of the ASME Boiler and Pressure Vessel Code through the Summor, 1975 Addenda, except for specific relief requested in accordance with 10CFR50.55a(g)(5)(iii) which is identified in Attachment B.

The period for which the pump and valve testing program is applicable commenced on March 1, 1978 and expires on November 1, 1979.

The pump and valve testing program was developed employing the classification guidelines contained in 10CFR50.2(V) for Quality Group A and Regulatory Guide 1.26, Revision 2 for Quality Groups B and C.

Quality Groups A, B, and C are the same as ASME Class 1, 2, and 3, respectively.

Figure 1 identifies the drawings used to develop the pump and valve testing program.

Figure 2 lists the codes and symbols used throughout the program.

Table 1 lists all safety related? Class 1, 2, and 3 pumps included in the testing program.

The test parameters measured and the testing frequency are also 1isted.

Table 2 lists al1 safety related* Class 1, 2, and 3 valves included in the program, Specifically excluded per IWV-1300 are valves used for operating convenience only, such as manual vent, drains, instrument and test valves, main-tenance valves, pressure regulating, thermal reliefs, and valves used for system control. Test methods and frequencies are also listed.

Valve stroke times are 1isted for the valves that have had their initial baseline values established.

At the present time, all valves in the program have not been full stroke timed.

The times will be supplied at the next revised submittal.

Valves which cannot be tested during normal o;)eration have the next acceptable frequency listed as allowed by IWV-3410 and IWV-3520.

Cold shutdown testing has been defined in the following manner:

0 hours0 days 0 hours 0 weeks 0 months Scram event or scheduled shutdown 0-12 hours Time necessary to determine the anticipated length of the shutdown 12-36 hours Time required to cool down, make arrangements for maintenance, and mobilize crews to actually begin ISI testing.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Testing will commence and continue until complete or plant is ready to return to power.

Completion of all testing will not be a prerequisite to return to power.

Any testing not completed at one shutdown will be performed during subsequent shutdowns within the required frequencies.

Safety-related - Necessary to safely shutdown the plant and mitigate the consequences of an accidrat.

ATTACHl!ENT B BRUNSWICK STEAtl ELECTRIC PLANr SPECIFIC REQUESTS FOR RELIEF _

Pump Testing Program 1.

Specific Relief Requested:

Deviation of Alert Range and Required Action Range for dif ferential pressure values as speci fied in IWP-3100-2.

Applicable To:

RHR pumps (4 per unit)

In Lieu of Test:

Upper value for dif ferential pressure in alert range of 1.08 AP.

Upper value for dif ferential pressure in required action rangb of 1.10 AP r

Justification:

The relief as requested will allow CP&L to perform ISI testing using installed instrumentation.

Presently, to achieve the accuracies required by the code test, instrumentation must be calibrated, installed, and removed for each test. Approximately 20 man-hours per pump is required to perform the test in this fashion.

The average exposure to the test personnel is approximately 100 mrem per pump.

For the RHR System, this constitutes 1920 man-hours and 9.6 rem per year to the plant staff.

The installed discharge pressure gauge has a requi red accuracy, per the GE Instrument Data Sheet, of + 12 psig. The required action range of the suction gauge is 13 psig. Thus, the total maximum error in measuring pump differential pressure can be as large as + 15 psig or 6% at the project reference test pressure, even though the gan;;c would still be accurate to 12% of their respective ranges.

Replacing the installed instrumentation with instruments capable of greater accuracy would constitute an undue hardship with no compensating increase in sa fety.

New inst ruments would cost approximately $10,000 and would require about 300 man-hours of engineering and administrative time.

Additionally, 300 man-hours would be required for installation with a total radiation exposure to plant personnel of 6 rem.

The relief request is made in the conservative direction.

Degradation of the pump would be detected in a lowering of differential pressure.

The ISI Test is not the only monitor of RHR pump performance.

There are other rotential backup methods fo r ensuring pump operability.

1.

Pump performance can be ev,luated by observing the running current of the motor at its feeder breaker.

2.

There are local and remote flow indictors or alternate flow paths which can be used if questions arise about RilR pump performance.

3.

In addition to the monthly ISI testing, CP&I. is verifying design pressure and flow of alI RilR pumps once per quarter as re<piired by Technical Specifications.

2.

Specific Relief Isequested:

Deviation of Alert Range and Required Action Range for low rate values as speci fied in IWP-3100-2.

Applicable To:

Ri!R Service Water Pumps (4 per unit)

In Lieu of Test:

Upper value for flow rate in alert range of 1.08 Q.

Upper value for flow rate in retpiired action range of 1.10 Q r

Jus ti fi ca t ion:

The relief as requested will allow CP&L to perform ISI testing using installed instrumentation.

Presently, to achieve the accuracies required by the code test instrumentation must he calibrated, installed, and removed for each test. Approximately 20 man-hours per pump are required to perform the test in this fashion.

The average exposure to the test personnel is approximately 40 mrem per pump.

For the RilR Service Water System, this constitutes 1920 man-hours and 3.84 man-rem per year.

The rated accuracies of the installed flow t ransmi tter and indicator are i 1/2% and i 2% respectively, of their overall range of 0-12,000 gpm.

This corresponds to an error of + 300

~

gpm. At the projected test point of 4,000 gpm, the error is !

7.5.

_a_

Replacing the installed instrumentation with instruments capable of greater accuracy would constitute an undue hardship with no compensating increase in safety. The cost would be between five and ten thousand dollars with a resultant radiati m dose to installation personnel of about 3 man-rem.

The relief request is made in the conservative direction.

Degradation of the pump would be detected in a lessening of flow.

The ISI test is not the only monitor.f RHR pump performance.

There are other potential backup methods for ensuring pump operability.

1.

Pump performance can be evaluated by observing the running current of the drive motor.

2.

Suction pressure is monitored at all times by an annunciator in the Control Room.

3.

Discharge pressure is monitored by both local and remote (Control Room) indicators.

4.

In addition to the monthly ISI testing, CP&L is verifying design pressure and flow of all RllR service water pumps once per quarter as required by Technical Specifications.

3.

Specific Relief Requested:

Deviation of Aler_ Range and Required Action Range for di f ferential pressure valves as specified in IWP-3100-2.

Applicable To:

Core spray pumps (2 per unit)

In Lieu of Test:

Upper value for dif ferential pressure in alert range of 1.08 AP r

Upper range for differential pressure in required act. ion range of 1. lp APr Justification:

The relief as requested will allow CP&L to perform ISI testing using installed instrumentation.

Presently, to achieve the accuracies required by the Code Test, instrumentation must be calibrated, installed, and removed for each test. Approximately 20 man-hours per pump is required to perform the test in this fashion.

The average exposure to the test personnel is approximately 40 mrem per pump. For the core spray system, this constitutes 960 man-hours and 1.92 man-rem per year.

The installed pressure transmitter has a nominal accuracy of 1%

of scale (+ 5 psig) and its indicator has a nominal accuracy of 2% (+ 10 psig) for a nominal total possible error of + 15 psig, or about 4.6% of the pump's total developed head at-the test p o i r.t.

Replacing the installed instrumentation with instruments capable of greater accuracies would constitute an undue hardship with no compensating increase in safety. New materials would cost about

$5,000 and would require about 300 man-hours for engineering and administrative time. Additionally 200 man-hours of installation time would constitute 1000 mrem of exposure The relief request is made in the conservative direction.

Degradation of the pumps would be detected in a lowering of di f ferential pressure.

The ISI test is not the only monitor of core spray pump performance There are other potential backup methods for assuring pump operability.

1.

Pump performance can be evaluated by -observing the running current of the motor at its feeder breaker.

2.

There a re local gauges monitoring suction and discharge pressure which r,ive further indication of pump performance.

3.

In the (very unlikely) event of the pump producing a much higher (140%) than normal pressure, there is a pressure switch E21-PS-N007 which will alarm in the Control Room.

4.

There are local and remote flow indicators on an alternate flow path which can be used if there are any questions about core spray pump performance.

5.

In aihlition to ISI testing, CP&L is committed by Technical Specifications to test the core spray pumps every <piarter by operating them at design conditions.

4.

Specific Relief Re<piested.

?!onthly Flow Rate Test as required by IWP-3400 Applicable To:

SBLC Pump In Lieu of Test:

t!casure flow rate at refueling outage Justification:

Current design does not permit measuring flow rate without actuating the explosive squib valver.. Pump suction is taken f rom the SilLC test tank and discharged back to the tank for the monthly operability testing. During refueling, the squib valves are actuated and the pump discharges into the vessel, allowing flow rate to be measured. Adequate assurance of pump operability is demonstrated by the monthly test and the full flow test at refueling.

5.

Specific Relief Requested:

flonthly flow rate test as required by IWP-3400 Applicable To:

SW lube water pumps In Lieu of Test:

flonthly start pump and assure discharge pressure is greater than service water pressure.

Quarterly tests to measure inlet pressure, dif ferential pressure, and vibration amplitude.

Justification:

Currently instrumentation is not installed to measure flow rate from the pumps. Plant modifications have been developed and 'he required instrumentation will be installed at the next refueling outage.

The in-lieu-of testing as described is adequate to assure pump operability until the modifications are made.

J

VALVE TESTING PROGRAM I.

Specific Relief Requested:

Seat Leak Testing on Category A Valves as required by IWV-3420 Applicable To:

All Category A valves listed in Table 2 In-lieu -of Test:

Leak testing per the requirements of 10CFR50, Appendix J.

Justification:

The Icak rate testing required by Appendix J imposes detailed and restrictive requiretants to assure containment integrity.

The local Type C testing, as well as t.

Integrated Leak Rate Testing required by Appendix J are currently being performed under Tech-nical Sp.ecifications.

No additional level of quality would be gained by duplicating the tests.

II.

Specific Relief Requested:

Quarterly exercise testing required by INV-3410 and IWV-3520 Applicable To:

Valves C11/C12 - 115, CV126, CV127, SV120, SV121, SV122, SV123 for all 137 CRD liydraulic Units In-lieu-of Test:

Operatlan of each valve verified during normal operation every seven days and pariodic tests performed every 16 weeks for 10% of the control rods selected on a rotating basis and all rods tested at each refueling outage.

Justification:

The valves for each control rod are contained within the hydraulic unit for that rod.

Satisfactory performance of the unit demonstrates oper-ability of the valves. Each rod is moved one notch every seven days that the reactor is operating at greater than 20% power.

In addition 10% of the control rods are fully inserted on a rotating basis every 120 days of operation.

At refueling all control rods are tested.

This test-ing is felt to exceed the requirements of IRV-3410 and IWV-3520, therefore a higher icvel of confidence is demonstrated for each valve.

III. Specific Relief Requested:

Quarterly exercise testing required by IWV-3410 and IWV-3520 Applicable To:

RilR valves Ell-F075, Ell-F078, and Ell-F073.

In-lieu-of Test:

None Justification:

These valves are in the cross connect line between RilR and Service Water Systems.

The function of the valves is to open as a very last resort and inject Service Water into the R]IR system.

No credit was taken in the plar. safety analysis for this action, therefore they are not considered as essential valves.

Testing of these valves would inject the untreated service water (brackish) into the primary loop.

No level of confidence is gained by testing these valves.

IV.

Specific Relief Requested:

Action required for inoperabic valves per IVW-3410(g) and IWV-3520(c).

\\pplicable To:

Valves listed on Table 2.

In-lieu-of Test:

Unit startup with an inoperable valve shall be governed by the technical specifications.

Justification:

The AS!!E Code's authoritative on when an individual valve is inoperable, but whether a unit startup can be perforned with an inoperabic valve depends on many factors.

These limiting conditions for operation have been analyzed and are currently included in the technical specification and should not be superseded by the ASME Code.

Revised December 22, 1978

FIGURE 1 BRUNSWICK STEAM ELECTRIC PLANT DRAWING LIST System P&ID Number Service Water 9527-D-20041, Rev. 5 Diesel Generator Service Water and Demineralized Water 9527-D-2274, Rev. 5 Containment Atmosphere Control 9527-D-25015, Rev. 6 Control Rod Drive Hydraulic 9527-D-25016, Rev. 7 Control Rod Drive llydraulic 9527-D-25017, Rev.5 Reactor Coolant Recirculation 9527-D-25018, Rev. 10 Nuclear Steam Supply 9527-D-25021, Rev. 4 Nuclear Steam Supply 9527-D-25022, Rev. 9 liigh Pressure Coolant Injection 9527-D-25023, Rev. 14 Core Spray 9527-D-25024, Rev. 12 Residual llent Removal 9527-D-25025, Rev. 12 Reridual lleat Removal 9527-D-25026, Rev. 9 Reactor Water Cleanup 9527-D-25027, Rev. 10 Reactor Core Isolation Cooling 9527-D-25029, Rev. 17 Service Water 9527-D-25037, Rev. 9 Closed Cooling Water 9527-D-25038, Rev. 9 Service Air 9527-D-25042, Rev. 6 Drywell Drains 9527-D-25045, Rev. 10 Scandby Liquid Control 9527-D-25047, Rev. 10 Reactor Coolant 'cfrr '_ation 9527-D-25048, Rev.~ 9 Fuel Pool Cooling and Filtering 9527-D-25049 Rev. 7 Containment Atmosphere Control 9527-D-2560, Rev. 4 Torus Drain and Keep Fill Charging 9527-D-26098, Rev. 2 Instrument Air Supply 9527-D-70007, Rev. 5 Instrument Air Supply 9527-D-70029, Rev. 8 Instrument Air Suppl. System Reactor Building 9527-D-70077, Rev. 4 Containment Atmosphere Monitoring 9527-D-72018, Rev. 7

FIGlTE 2 BRUNSWICK STEAM ELECTRIC PLANT CODES AND SYM130LS USED Valve Types Actuator Types BF.

Butterfly A0.

. Air CK.

Check M

. Manual DA.

Diaphragm

!!O.

. Motor GA.

Cate SA.

Self Actuated GL.

Globe SO Solenoid ND.

Needle REG Regulator Valve Position RV.

Relief / Safety C

Closed 3W.

3-Way 0

Open LC.

Locked Closed LO Locked Open V.alve Test Methods FS.

. Full Stroke FL.

Observe Failure Mode MT.

Measure Time LT.

Leak Test VI.

Verify Remote Indication PV.

Passive Valve (No Test hequired)

RV.

Relief Valve (Test per IWV-3510)

ET.

Category E Valve (Verify locked or scaled)

Test Intervals Misc. Symbols M.

Monthly NA.

. Not Applicable Q........ Quarterly NR.

. Not Required C.

Cold Shutdown R.

Refueling A.

Annual

TABLE 1 BRUNSWICK STEAM FLECTRIC PLANT PUMP TEST PROGRAM No. Per Safety Rotative Inlet Diff.

Flow Vibration Bearing Pump Unit Class Speed Press.

Press.

Rate Amplitude Tenn.

(1)

RHR*

4 2

NR M

M NR M

A RHR SW Booster 4

3 NR M

M M(2)

M A

HPCI*

1 2

M M

M NR M

A RCIC*

1 3

M M

M NR M

A (3)

Core Spray

2 2

NR M

M NR M

A (4)

SBLC 2

2 NR M

M R

M A

Service Water 5

3 NR M

M M

M A

SW Lube (5)

Water 2

3 NR M

M M

M A.

Considered to be fixed resistance system since tested in mini-flow mode () indicates numbers of specific relie f re quested.

Revised September 1, 1978

TABLE 2 VALVE TL50 PisGGRMI Diesel Generator Service BRLl;SWICK STEFlt ELECTRIC Pl>2'T sySTF:t ::A:C Water and Dedineralized Water System PLID ::0, 9527-D-2274 FACE 1 of 2 6}

P, g

n 6

o u

H r

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e a

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M N

S VALVE of VALVE c

m cr p

R =g y

M yg m

g NUMBER

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y Rp y

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S h~d H

H y

as m

a a

o m

A o

m 0

O u

A B

C D

E y

4" 1-SW-V210 3

E2 X

6 BF M0 C

N FS-Q MT-Q 2-SU-V210 3

E2 X

6 BF MO C

N FS-Q MT-Q 1 SW-V211 3

E5 X

6 BF M0 C

N FS-Q MT-Q 2-SW-V211 3

E5 X

6 BF MO C

N FS-Q MT-Q 1-SU-V212 3

E7 X

6 BF MO C

N FS-Q MT-Q 2-SW-V212 3

E7 X

6 BF MO C

N FS-Q MT-Q 1-SW-V213 3

E10 X

6 BF

?!O C

N FS-Q MT-Q 2-SW-V213 3

E10 X

6 BF M0 C

N FS-Q tr-Q t

i l

l

TABLE 2 VALVE TEST FROGRAM Diesel Generator Water ERC;5 WICK SIEAM ELFCTRIC PLAST SYSTE!! :g's!'E Service & Demineralized Water System FLID I;0 9527-D-2274 PAGE 2 of 2

.6

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El X

6 CK I

SA N

FS-Q t

2-SW-V272 3

El X

6 CK SA N

FS-Q 1-SW-V273 3

E4 X

6 CK SA N

FS-Q 2-SW-V273 3

E4 X

6 CK SA N-FS-Q 1-SU-V274 3

E7 X

6 CK SA N

FS-Q 2-SW-V274 3

E7 X

6 CK SA N

FS-Q 1-SW-V275 3

E10 X

6 CK SA N

FS-Q l

2-SW-V275 3

E10 X

6 CK SA N

FS-Q i

i Revised June l 'e, 1978

L.G M 2

' A! ' - i'>.

1-CGI" '

ERC;sUICK STEllt ELECTRIC PLA::T c..b1[. I..b. e containtuent Atmosphere Control 9527-D-2560

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ES X

0.5 RV SA C

N RV PSV7

')

E6 X

0.75 RV SA C

N RV l'S V 3 2

C5 X

1.5 RV SA C

N RV PSV4 2

DS x

0.S RV SA C

N RV PSV5 2

DS x

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N RV 2 - t ! !'- V

C6 L

GI.

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ET-31 2-NP-V1 2

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ki Revised December 22, 1978

TAhlE. 2 VALVE TEST PRGGRAll ERUNStJICK STEAJ1 ELECTRIC PLANT SYSTE!! n:'d serufer i h r..,

P&ID !;0.

9527-D-20041 PACE 1 of 3 B

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9 2

p g

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A B

C D

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~

N RV4 3

B6 X

0.75 RV SA N

RV RV5 3

B8 X

0.75 RV SA N

RV RV6 3

BLO X

0.75 RV SA N

RV RV7 3

B2 X

0.75 RV SA N

RV RV8 3

B4 X

0.75 RV SA N

RV RV9 3

C6 X

0.75 RV SA N

RV RV10 3

C8 X

0.75 RV SA N

RV RVll 3

C10 X

1.75 RV SA N

RV RV12 3

C2 X

'). 7 5 RV SA N

RV RV13 3

C4 X

). 75 RV SA N

RV V 13 3

E6 X

20 BF MO O

N FS-Q drr-Q V4 3

F.7 X

20 BF M0 C

N FS-Q 1

MT-Q V15 3

E8 X

20 BF 110 0

N FS-Q MT-Q i

~

Revised September 1,1978

TABLE 2 VALVE TEST PROGRAM BRL7;SUICK STEAM ELECTRIC PLA'iT SYSTEM !!A:S. Service Water P&ID :;0 9527-D-20041 PAGE 2 of 3

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m O

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L V16 3

E9 X

20 BF MO C

N FS-Q MT-Q V17 3

E10 X

20 liF MO O

N FS-Q MT-Q l

V18 3

Ell X

20 BF M0 C

N FS-Q MT-Q Vl9 3

E3 X

20 CF MO O

N FS-Q MT-Q V2O 3

ES X

20 BF MO O

N FS-Q MT-Q V201 3

E2 X

4 CK SA N

FS-Q V202 3

A9 X

4 CK SA N

FS-Q V203 3

A8 X

4 CK SA N

FS-Q V204 3

A9 X

4 CK SA N

FS-Q V205 3

A8 X

4 CK SA N

FS-Q V255 3

E2 18 BF MO O

N PV l

I, Revised September 1,1978 Revised Decerber 22, 1978

TABLE 2 VALVE TEST PRCCRMI BRUttSUICK STEA:1 ELECTRIC PLAl'T SYSTE:! I'A:E se r, t r,.

U n o,-

PLID NO. 9527-D-20041 Pact 3 of 3 6

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ao s

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p m

2 o

m o

o g

N 9

a o

A B

C D

E Z

V21 3

D7 X

20 CK SA N

FS-Q V21 & V276 tested only if "A" Conven-tional pump is operable.

V276 3

C6 X

1.5 CK SA N

FS-Q V22 3

D9 X

20 CK SA N

FS-Q V22 & V277 tested ;nly if "B" Conven-tional pump is o arable V277 3

C8 X

1.5 CK SA N

FS-Q V23 3

D11 X

20 CK SA N

FS-Q V23 & V273 tested only if "C" Conven-tional pump is operable V278 3

C10 X

1.5 CK SA N

FS-Q 4

V24 3

D3 X

20 CK SA N

FS-Q V24 & 279 tested only if "A" Nuclear pump is operable V279

'l C2 X

1.5 CK SA N

FS-Q V25 3

D5 X

20 CK SA N

FS-Q V25 & V280 tested only if "B" Nuclear pump is operable.

V280 3

C4 X

1.5 CK SA N

FS-Q I

TABLE 2 VALVE TEST PROGRA!!

BRtmSWICK STEA'l ELECTRIC PLANT SYSTF!! !Ll!S Containment Atmospheric Control P&ID 1:0.

9527-D-25015 PACC 1 of 3

-.6 9

m Li M

H LO o

a H

p E

N N

N m

cr VALVE VALVE J

g g

gg og a

g laIMLER m 4=

CATECORY m

RER W'S v

o o-W

$.2 H

<4

3. s a

a ss L

o b$

d d

N' s=g a

M p

u c

U N

O A

o m

o o

g "g

o 4

o A

B C

D E

V4 2

C5 X

8 BF A0 O

Y FS-Q FL-Q LT-R X

APP.J V5 2

C6 x

20 BF A0 C

Y FS-Q FL-Q LT-R X App. J V6 2

D7 X

18 BF A0 C

Y FS-Q FL-Q LT-R X

App J V7 2

C11 X

20 BF A0 C

Y FS-Q F1-Q V8 2

C11 X

20 BF A0 C

Y FS-Q FL-Q V9 2

F10 X

18 BF A0 C

Y FS-Q FL-Q VI-R l

I Revised Decerber 22, 1978

TABLE 2 VALVE TEST PRCCRM1 BRtalSUICK STEMt ELECTRIC PLA:IT SYSTE1IL1:C Conrainment Atmospheric Control P&ID I:0.

9527-D-25015 PAGE 2 of 1 8

q H

^

E U

U L) 8 t

2 h

G VALVE oe VALVE c

o z

=

[4 e

c-.

=o a

d s

m

e. <

a ea laIMBER m

uu CATECORY v

o o-(q

<m REN\\RKS 3s H

a sa m

m ea b MS O

f N

d d

a "8

G i

d d

Q o

A B

C D

E L-VIO 2

F10 X

18 BF A0 C

Y FS-Q FL-Q VI-R V15 2

E6 X

24 BF A0 C

N FS-Q FL-Q LT-R X

APP.J V22 2

C12 X

2 CA M0 C

Y FS--Q MT-Q V23 2

F10 X

2 GA M0 C

Y FS-Q MT-Q V47 2

D6 X

1 CA A0 0

Y FS-Q FL-Q LT-R X App. J V48 2

08 X

1 CA A0 0

N FS-Q FL-Q LT-R X App. J V49 2

C9 X

4 BF A0 C

Y FS-Q FL-Q l

I L

Revised December 22, 1978

TABLE 2 VALVE TEST PROGRAM BRU::sWICK STEAM ELECTRIC PLMIT SYSIU1ID.:S cnntainment Armspheric control P&ID 1:0 9527-n-?s01s PACE 3 of 3 O

g 9

^

U Y

R 1 ID:EER y

g-g CATEGORY p

_g W

i M

N G

8 VALVE o e, VAINE c

o p

g gg v

o op g

$m RE.MPJ3 d dS d

{

f Od *d d

a f

"8 a

m o

N N

o A

B C

D E

V50 2

C9 X

4 BF A0 C

Y FS-Q FL-Q VI-R V55 2

D6 X

1 CA A0 C

Y FS-Q FL-Q LT-R X

APP.J V56 2

D6 X-I c^

^0 C

Y FS-Q FL-Q LT-R X

APP.J V59 2

DS X

0.75 RV SA Y

RV V74 2

D5 0.75 GL M

C Y

PV l

V91 2

ES X

1 GL M

C N

ET-N X20A 2

B6 X

X 20 CK SA N

FS-Q LT-R X

App. J X20B 2

B7 X

X 20 CK SA Y

FS-Q LT-R X

App, j Revised December 22, 1978

TABLE 2 VALVE TEST PROGRAM BRUNSUICK STEAM ELECTRIC PLANT SYSTE:1!!A E Control Rod Drive Hydraulic P&ID NO.

9527-D-25016 PAGE i nr 9 s'

m S

d

[

d B"

=

c e

n 8

e VALVE os VALVE c

o z

=:

c_3 m

IRDSER

$ d5 CATEGORY U

[$

50 D$

REMARKS U

E "a N $"

U Ud 5M d

H H

U u

o ao H

a H

Id N

c a

m a

H c

m o

o y

N-2 a

o A

B C

D E

Z 8-F083 1

G2 X

X 3

CK SA N

FS-R FR83, F086: SYSTEM IS IN CONTINUOUS LT-R X App.

.) OPERATION.

TEST AT REFUELING.

F086 1

G1 X

X 3

CK SA Y

FS-R LT-R X

App.J F087 1

G1 3

CA M

0 Y

PV I

l l

Revised Sep tember 1,1978 Revised December 22, 1978

TABLE 2 VALVE TEST PRCORMt BRU'ISUICK STEA?! ELECTRIC PLA'IT SYSTE!! MA:E Control Rod Drive Ilydraulic P&lD NO.

9527-D-25017 PAGE 9 nf 9

..s e

Q to f4 H

M o

u s

u g

t M

h a

8 W

a vatze gg vAtvE c

g g _g g

g gg m

y UUNi2ER

)c g g-CATECORY op g

gm REMAPJ:S v

o e

H Ud d de M

W

'b R=d W

ao m

a u

o m

a o

m o

o

-g tg

.a o

A B

C D

E Z

4 115 2

E2 X

0.5 CK SA N

FS-Q X

FS-R CV126 2

E4 X

0.5 CA A0 C

N FS-Q X

FS -R F L-Q X

FL-R CV127 2

F4 X

0.75 CA A0 C

N FS-Q X

FS-R FL-Q X

FL-R SV120 2

E3 X

1 CA SO C

N FS-Q X

FS-R SV121 2

F3 X

0.75 CA S0 C

N FS-Q X

FS-R SV122 2

F4 X

0.75 CA SO C

N FS-Q X

FS-R SV123 2

F4 X

1.

CA SO C

N FS-Q X

FS-R I

i O

TABLE 2 VALVE TEST PRGGRA'l BRUNSWICK STEAM ELECTRIC PLANT Reactor Coolant Recirculation g7ggggg,c3 PLID 1;0.

9527-D-25018 PACE 1 of 1 6

e 9

m Y

a ta H

m o

u H

y E

'd S

m o

VALVE os VALVE 3

p y

M M

yg o

y, g

I;tDILER m

Oz CATECORY

RENS, v

o oH H

$., m

-~

s a

se o

m ta 4

%o t4 g/

?d d

EJ LH o

c2 d N

l q

b H

H co s

>J H

D A

m M

r o

m 0

9 M

M d

o A

B C

D E

N

~

F019 1

E7 X

0.75 GL AO O

Y FS-C F019, F020: Failure closed prevents FL-C sampling of reactor coolant VI-R F020 2

F3 X

0.75 GL A0 0

N FS-C FL-C VI-R E023A 1

n10 X

28 CA M0 O

Y FS--C F023A, F031A: Closure of either vr.1ve MT-C shuts off reactor coolant recircula-VI-R tion flow.

l F031A 1

C5 X

28 CA M0 O

Y FS-C MT-C VI-R F043A 1

C9 22 CA M0 C

Y PV F044A 1

G9 2

GA MO O

Y PV

.V22 2

F3 X

0.75 CA MO O

N FS-C V22, V24: Failure closed shuts off btT-C cooling water to recirculation pump.

I V24 2

F4 X

0.75 CK SA Y

PS-C FS-C F032A 1

B5 X

4 GA M0 C

Y MT-C F032A: Locked open by Admin. Procedure l

UT n durinc norm 1 operations.

Test it cold Revised September 1,1978 shut down. l Revised December 22, 1978

TABLE 2 VALVE h.ST PROOkM1 BRtR;SWIt-STE/J1 ELECTRIC PLA::T tiu c le. r Steam Supply SYSTE!! !!A:S P&ID I:0 PAGE 1 of 7

5 H

^

d U

h Pd m

e u

g s

o g

VALVE oN VALVE E

D

=

0 y"

s liU:GER I.

CATECORY O

58 D$

RER\\R13 D

d $U U

SH U

j

^

u g

o8 0

s I!

Ei d

M ti d

o m

o o

D-N-

q a

O A

B C

D E

c-F010A 1

D11 X

X 18 CK SA 0

Y FS-C F010A & B: Cycling would cause loss LT-R X

App.J of main feedwater flow.

F010B 1

B11 X

X 18 CK SA 0

Y FS-C LT-R X

App.J 313A 1

G7 X

6 RV SA Y

RV F0138 i

G8 X

6 RV SA Y

RV F013C l

E7 X

6 RV SA Y

RV F013D 1

E2 X

6 RV SA Y

RV F013E 1

E8 X

6 RV SA Y

RV F013F 1

D7 X

6 RV SA Y

RV Fol3G 1

D8 X

6 RV SA Y

RV F0131l 1

B7 X

6 RV SA Y

RV FOl L>

1 B8 X

6 RV SA Y

RV FOl3K 1

D8 X

6 RV SA Y

RV F013L 1

E9 X

6 RV SA Y

RV I

i i

Revised September 1, 1978

TABLE 2 VALVE TESF PROGRAM BRU:4SUICK STEA!! ELECTRIC PLA!1T SYSTE!! :U.:E Nuclear Stean Sunp1v P&ID I:0.

9527-D-25021 PAGE 2 of 7 5

a m

S 2

h P

s O

m

.c m

-N S-w o

m m

o cr VALVE VALVE

,c p

g g

g gg 9g o

m I;1DSER u

Oa CATECORY v

o oH (1

<m REMAR13 as H

A HP gg m

~

dO N

S f~

k d

d a

H N

ao

~

A r-O m

A O

A B

C D

E FOl6 1

FS X

3 CA M0 C

Y FS-Q MT-Q VI-R LT-R x

App,J F019 1

F4 X

3 GA MO O

Y FS-Q MT-Q VI-R LT-R X

App. J F022A 1

C5 X

24 GL A0 0

Y FS-C F022A, B, C, D: Cycling would cause FL-C loss of primary steam flow LT-R X

App. J F022B 1

ES X

24 GL A0 0

Y FS-C FL-C LT-R X

App. J F022C 1

D5 24 CL A0 0

Y FS-C FL-C LT-R X

App. J F022D 1

B-5 X

24 GL A0 0

Y F', -C FL-C LT-R X

App. J Revised September 1, 1978'

TABLE 2 VALVE TEST PROGRAM BRUNSUICK STEAM ELECTRIC PLANT SYSTE:1 NA!S Nuclear Steam Supply PLID I;0 9527-D-25021 PAGE 3. of 7

O b

h u

=

i e

B E

s B

e VALVE VALVE c

o og p

g g

g gg m

g tad 2ER oj g3 CATEGORY op g

RERW3 v

o a

d se H

W i!

M<.= d U

e M

M ao a

o m

a o

m 0

53 g

y y

+3 A

B C

D E

~

N F028A 1

C4 X

24 CL A0 0

Y FS-C

F028A, B, C, D:

Cycling would cause FL-C loss of primary steam flow.

LT-R X

App. J F028B 1

E4 X

24 CL A0 0

Y FS-C FL-C LT-R X App. J FOS 8C 1

D4 X

24 GL A0 0

Y FS-C FL-C LT-R X App. J F028D 1

11 4 X

24 GL A0 0

Y FS-C FL-C LT-R X App. J F005 1

G10 2

GL M

0 Y

PV F0llA 1

Dll 18 GA M

0 Y

PV F0llB 1

Bil 18 CA M

0 Y

PV Revised September 1, 1978 Revised December 22, 1978

TABLE 2 VALVE TES1 PROGRC BRlR StlICK STEAM ELECTRIC PLA.T SYSTE!! I A:E Nuclear Steam Sunply P&TD !;0.

9527-n-25021 PACE 4 of 7

' ~.

..6 H

m d

h O

d m

e a

g g

VALVE o$

VAINE E

D 9

o w

(4 ce r-

=o 9

d m

z<

d HH

!;U:EER u)

~z CATECORY v

o os a

<m RE!" APES 7s H

A H H a

s-1-

4 a

u g

d

= D' u

o a:

N d

q H

s Qo H

Cu O

V1 A

o m

o o

y'~

p.

a i

o A

B C

D E

F024A 2

t:5 X

1 CK SA Y

FS-C F024 A, B, C, D & V28 A, B, J. D:

Cycling would cause loss of air and F0248 2

F6 X

1 CK SA Y

FS-C closure of main steam valve F024C 2

46 X

1 CK SA Y

FS-C F024D 2

6 X

1 CK SA Y

FS-C V28A 2

25 X

1 CK SA Y

FS-C V28B 2

F5 X

1 Ci' SA Y

FS-C V28C 2

05 X

1 CK SA Y

FS-C V28C 2

L:S X

1 CK SA Y

FS-C i

t O

TABLE 2 VALVE TESF PROGRAM BRU:ISUICK STEAM ELECTRIC PLANT SYSTE:1I:A S tinclear St oan Surm iv P&ID I:0 4527-n-?sn91 PACE _5of 7

..6 9

m m

u H

to o

a H

u g

t M

h 8

W o

=

~

cx VALVE o, a VitLVE c

'E4 c:

c-.

=o G

4 H

m O z<

CATECORY w

c-HH 1RDSER m

v o

oH u

<m RE.".N

~~H H

a HH m

n.

J u

'2 a

u

=.N' O

a N

H H

a5 H

a d

a m

a o

m 0

o u

a o

A B

C D

E Z

F029A 2

C4 X

1 CK SA Y

FS-C F029 A, B, C, D & V29 A, B, C, D:

Cycling would cause loss of air &

F029B 2

F4 X

1 CK SA Y

FS-C closure of main steam valve.

F029C 2

D4 X

1 CK SA Y

FS-C F029D 2

C4 X

1 CK SA Y

FS-C V29A 2

C4 X

1 CK SA Y

FS-C V29B 2

F4 X

1 CK SA Y

FS-C V29C 2

D4 X

l CK SA Y

FS-C 1

V29D 2

C4 X

1 CK SA Y

FS-C I

f F032A 1

D11 X

18 GL MO O

Y FS-C F032A & B:

Cycling would cause loss of MT-C main feedwater flow.

LT-R X

APP. J F032B 1

Bil X

18 GL MO O

Y FS-C MT-C LT-R X

App.

i L

TABLE 2 VALVE TESr PRCCRM1 BRU::SUICK STEM 1 ELECTRIC PLANT SYSTE!! !!A C finclear Steam c;u nn i v PSID I0 9527-D-25021 PAGE 6 o f 7___

8 g

9

^

U d

5 M

' El

l ii 2

h a

8 s

W VALVE VALVE c

o og p

y p

p pg g

NU:GER m

Zn CATECORY v

o oH u

<m RE: DRYS

s a s

a sH N

- g hh h

Y H

H ao

~

A m

o m

A N

o v1 o

o a

g y

O A

B C

D E

F036A 2

11 7 X

0.75 CK SA Y

FS-C F036B 2

11 8 X

0.75 CK SA Y

FS-C Valves this Page:

Cycling during normal operation would F036C 2

V7 X

0.75 CK SA Y

FS-C cause loss of operability of safety relief valve.

F036D 2

F8 X

0.75 CK SA Y

FS-C F036E 2

F8 X

0.75 CK SA Y

FS-C F036F 2

E7 X

0.75 CK SA Y

FS-C F036C 2

D7 X

0.75 CK SA Y

FS-C F03611 2

C7 X

0.75 CK SA Y

FS-C F0ltI 2

C8 X

0.75 CK SA Y

FS-C i

F036K 2

D8 X

./5 CK SA Y

FS-C F036L 2

F9 X

0.75 CK SA Y

FS-C I,

I

TABLE 2 VALVE TEST PROGRAM BRt2iSWICK STEA!! ELECTRIC PLANT SYSTf.!! !!A!E Nucl.mr su Supp1v P&ID NO.

9527-D-25021 PACE 7 of 7

~6 9

^

N Y

'h w

il M

C G

8 cr VALVE VAINE c

o oy g

g g

g yg I;1DIT>ER m

Cz CATEGORY v

o oH H

<m REME q

s s

a se a

w

~-E2d ga u

g N'

9 o

d :g u

" Es M

a M

U N.1 o

m 0

o e

O A

B C

D E

Z

'2 p

g V27A 2

11 7 X

0.75 CK SA Y

FS-C Valves this Page:

Cycling during normal operation would V27B 2

!!8 X

0.75 CK SA Y

FS-C cause loss of operability of safety relief valve.

V27C 2

F7 X

0.75 CK SA Y

FS-C V27D 2

F8 X

0.75 CK SA Y

FS-C V27E 2

F8 X

0.75 CK SA Y

FS-C V27F 2

D7 X

0.75 CK SA Y

FS-C V27C 2

E8 X

0.75 CK SA Y

FS-C V2711 2

C7 X

0.75 CK SA Y

FS-C V27J 2

C3 X

0.75 CK SA Y

FS-C V27K 2

E8 X

0.75 CK SA Y

FS-C V27[.

2

'F9 X

0.75 CK SA Y

FS-C

TABLE 2 VALVE TEST PB0 CRAM.

BRUNSWICK STEAM ELECTRIC FLANT SYSTE!! MA:!E liigh Pressure Coolar.t Injection psIn go, 9527-D-25023 PAGE 1 of 3 O

b h

ca a

e e

B B

8 e

VALVE J

p VALVE

_g y

g yg o

og g

g a

Sp y

'NN InDIBER q g3 CATECORY y

v g

d ~d d

U $s9 d

S R

u a

N a

~

a m

a 4

o v2 o

o y

y 4

o A

B C

D E

F001 2

F3 X

10 CA MO C

N FS-Q MT-Q F002 1

C11 X

10 CA M0 O

Y FS-C F002, F003; MT-C Cycling during normal operations VI-R would cause loss of steam to HPCI LT-R X

App. J turbine.

V F003 1

G10 X

10 CA MO O

Y FS-C MT-C VI-R LT-R X

App. J F005 2

E9 X

14 CK SA N

FS-Q F006 1

D10 X

14 CA M0 C

N FS-Q MT-Q LT-R X

App.J F007 2

E9 X

14 GA M0 0

N FS-Q MT-Q F008 2

F8 X

10 GL MO C

N FS-Q MT-Q Test with F011 closed F009 2

F8 X

10 CK SA N

FS-Q i

F0ll 2

G7 X

10 GA M0 C

N FS-Q Test with FC08 closed MT-Q

~

Revised Stepember 1, 1978

TABI.E 2 VALVE TEST PROGRAM BRIJNSWICK STEAM ELECTRIC PLANT SYSTEM ILVE liigh Pressure Coolant Injection P&ID NO.

9527-D-25023 PAGE2 of 3 d

a 1:

e n

a 8

e a

VAIVE VALVE c

o oy g

g y

g gg v

o o-W

<m aEI'N tilDIBER m

Oz CATEGORY 3

as H

4 H H

~

4 lvg de M

N j *$

H o

H "8

U o

o A

B C

D E

4 F012 2

D8 X

4 GL MO C

N FS-Q MT-Q

)

F019 2

F5 X

16 CK SA N

FS-Q F021 2

C10 X

X 20 STOP SA N.

FS-Q F021, F022: Eh'D. Flow Verification only CK ET-M as safety function is to open.

F022 2

C9 X

X 2

STOP SA N

FS-Q CK ET-M F040 2

C9 X

2 CK SA N

FS-Q F041 2

G6 X

16 GA M0 C

N FS-Q MT-Q F042 2

B8 X

2 GA M0 C

N FS-Q MT-Q F048 2

11 5 X

2 CK SA N

FS-Q F049 2

C10 X

20 CK SA N

FS-Q F050 3

C6 X

3 RV SA N

RV i

F053 2

C5 X

0.75 GL SOL C

N FS-Q l

Revised December 22, 1978

TABLE 2 VALVE TEST PROGRM!

BRE';%'ICK STEA'1 ELECTRIC PLANT SYSTEM ::A::E Hioh Pressure coolant Iniection PLID I;0.

4527-0-25023 PAGF, 3 of 3

^

5 a

to tu H

f2 to es eo ta

u s

.u a

o S

p w

VALVE o$

VAL'/E E

-"C S

S G:

d m

z<

e s

=c s

ss NU' EER c

- r:

oH

T &

TC P SE 5HHH$r-Asd' o" O

0 EL TE

~

EM VA ac.g 4oHgM0<

D D

c LE I

F AT VS K

2C u"' $ pd <>

A A

I G

G EU LS BN AU TR nnac cwv wUm B

2 2

E v

1 p

Y D _

p ER u

VO S

LC C

AE r

VT i

A A

C B

X X

tn A

e mu mNc.z a$oo r

6 7

o Cyc.$

E E

t sn I

m m?J" 2

2 Z

d

?N T. R E

M UB E

AM 1

3 T

VU 0

0 S

N 1

1 Y

V V

S

TABLE 2 VALVE TEST PROGRAM BRU:lSUICK STEAM ELECTh1C PLANT SYSTE:11AIE Containment Atmosohere Monitoring P&ID HO.

9527-D-72018 PAGE 1 of a

[

h5

.e s

n E

E C

N 5

M M

8 9

m VALVE 3

p g

g g

pg

j...

VALVE o

oy m

v o

o-y

<m REMARFS N1DElER m

Rn CATECORY

$s N.,Nh UN U d$

^

u e

o ee w

e a

A H

a.

O m

A H

ao a

o r,

o o

p uj p

o A

B C

D E

Z M

4 PV1200B 2

F7 X

1 GL AO, O

N FS-Q FL-Q PV1205E 2

D9 X

1 GL A0 0

N FS-Q FL-Q PV1209A 2

E9 X

1 GL A0 0

N FS-Q FL-Q PV1211E 2

D9 X

1.25 GL A0 0

N FS-Q FL-Q PV1211F 2

D9 X

1 CL A0 0

N FS-Q FL-Q PV1215E 2

C10 1

GL A0 0

N PV PV1225B 2

D6 X

1.25 GL A0 0

N FS-Q FL-Q PV1227A 2

D6 X

1 GL A0 0

N FS-Q

_ FL-Q Revised December 22, 1978

TABLE 2 VALVE TEST PROGRAM BRUNSWICK STEAM ELECTRIC PLANT SYSTEM MA12 Containment Atmosobere Monitorine P&ID NO.

9527_n_79nts PAGE

,c 3 __,

S s

E d

E g$

y m

f d

D 8

a a

g y

y pg VALVE J

p g

o VALVE og REP M a

Sp g

NUMBER u) {g CATEGORY v

o

$O N

S f

N d

h H

3 g

C8 h

g g

o 4

0 A

B C

D E

PV1227C 2

D7 X

1 GL AO.

O N

FS-Q FL-Q PV1227E 2

E6 X

1 GL A0 0

N FS-Q FL-Q PV1231B 2

C5 1

GL A0 0

N PV PV1260 2

E6 X

1 GL A0 0

N FS-Q FL-Q PV1261 2

F6 X

1 GL A0 0

N FS-Q FL-Q PV1262 2

D9 X

1 GL A0 0

N FS-Q FL-Q PV3'439 2

D9 X

1.25 GL A0 0

N FS -Q FL-Q PV3440 2

E6 X

1.25 GL A0 0

N FS-Q FL-Q a

Revised December 22, 1978

e M 89 e

aL i

n

=

O g

M.

e'.

N

.a n

=

w TSET 7

EVITANRETLA

?

U TSEUQER FEILER o

e

o. o z

D011 TEM TSET 77 P

MM km 5'

~

ko AERA NOITAIDAR m "N"m liGIH ao

$E

OITISOP LAMR011 O

Hm I

h,$

EPYT ROTS /UTCA 24 wf j EPYT EVLAV

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Dear Mr. Ippolito:

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