ML20212P790

Rev 2 to Operating Procedure B.2A, Plant Operation W/Either or Both DHS Trains Not Operable

ML20212P790
Person / Time
Site:	Rancho Seco
Issue date:	02/28/1987
From:	SACRAMENTO MUNICIPAL UTILITY DISTRICT
To:
Shared Package
ML20212P471	List: ML20212P469 ML20212P790 ML20212P797 ML20212P800
References
B.2A, TAC-64896, NUDOCS 8703160266
Download: ML20212P790 (32)

Text

.

?.

,'D EFFECTIVE DATE 02-28-87 f.-;

Rev. 2 WP3774P D-0052P B.2A PLANT OPERATION WITH EITHER OR BOTH DHS TRAINS NOT OPERABLE 1.0 PURPOSE 1.1 Provides major operator guidance for preparing the plant and maintaining cold shutdown, using the OTSGs for RCS heat removal, while either or both Decay Heat Removal System Train are not operable.

2.0 REFERENCES

2.1 SMUD Rancho Seco Unit 1 FSAR, Section 15, Technical Specifications 2.2 SMUD Rancho Seco Unit 1 Process Standards 2.3 SMUD Rancho Seco Unit 1, Chemistry and Radiochemistry Manual, AP.306 2.4 SMUD Rancho Seco Unit 1, Plant Operations Manual-3.0 LIMITATIONS AND PRECAUTIONS 3.1 If the OTSG is drained, or the water level is below the feedwater heating steam aspirating ports in the tube bundle (383 inches above the top of the lower tube sheet or 85% on the operating range) it should be

-filled to this level prior to filling the RC system.

NOTE:

(a) This provides a means of heating the OTSG shell and assures allowable tube-to-shell temperature differentials when the RC System is filled and vented.

(b) For RC System temperature above 230*F, the OTSG level can decrease below minimum startup level. Shell heating is accomplished by flow induced by condensation of steam above the water level.

3.2 Minimum allowable feedwater temperature to the main feed nozzles is 350*F below OTSG downcomer outlet temperature.

3.3 Maximum allowable AT between RCS and OTSG average shell temperature is 60*F.

(See OP A.6, Enclosure 8.6) 8703160266 870310 ADOCK0500g2 DR p

B.2A-1

s LIMITATIONS AND PRECAUTIONS (Continued) rg.

3.4 The auxiliary feed nozzles must be used for filling an empty OTSG

(<8 inches startup level) when RC temperature >200*F.

3.5 Maximum allowable OTSG fill rate is 500 gpm.

3.6 Use of a N2 blanket in the pressurizer -to maintain plant pressure shall only be used when at pressures of 0-50 psig. When RCS pressure is e

raised above 50 psig, a steam bubble shall be formed in the pressurizer and the N2 vented.

3.7 No batches shall be added to the Makeup Tank which, calculated by B.9, would cause a decrease in RCS boron concentration.

3.8 Observe RCS Heatup Limits per Process Standards, Figure 101.la.

3.9 Prior to any RCS temperature change, verify per OP 8.6, a 1% Ak/k f

Reactor shutdown margin will exist at a new RCS temperature.

3.10 If boron concentration is to be changed while a Decay Heat Pump is in service, insure that the calculation of change in concentration uses only the Reactor Vessel and Decay Heat System volume, not the total RCS j

volume. The RCS total volume will not be circulated, or mixed when' on Decay Heat.

3.11 If 02 Analyzer is out of service, notify Chemistry to sample within four (4) hours of the start of plant heatup.

3.12 Minimum water temperature to OTSGs through the auxiliary feedwater nozzles shall always be maintained >40*F.

3.13 Condensate Storage Tank Water shall meet chemistry specificat'- s set forth in the Rancho Seco Unit 1 Chemistry Manual, for filling OTSGs.

3.14 Minimum OTSG shell temperature is 70*F.

3.15 Maximum operating temperature for the OTSG drain booster pumps is 250*F.

i j

3.16 Maximum operating pressure for the OTSG drain booster pumps is 100 psig.

3.17 Auxiliary Feedwater Pump Motor Start Limitations:

3.17.1 Two successive starts are allowed with the motor at ambient temperature.

3.17.2 An interval of four hours running time is allowed before another start is permitted.

3.17.3 An interval of five hours must elapse with the motor not running before another start is permitted.

I I

Rev. 2 B.2A-2

,, -c ;,,'. ~.. J *. -

..s %,.

,**=?....

....t

• i. *

' +

• [

.,_g L

• 'j

..L

4.0 PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FROM SERVICE

,-~

4.1 Initial Conditions INITIAL 4.1

.1 Component cooling and turbine plant cooling water systems are in service according to OP A.26, Section 5.0.

I i

4.1

.2 Plant cooling water and reservoir system are in service according to OP A.36, Section 5.0.

4.1

.3 Plant air system is in service according to OP A.40, Section 5.0.

4.1

.4 Nuclear service raw water system A and/or 8 in service according to OP A.25, Section 5.0.

i 4.1

.5 Nuclear service cooling water system A and/or B in service according to OP A.24, Section 5.0.

I 4.1

.6 Decay Heat Removal System A and/or B in service according to OP A.8, Section 4.3.

4.1

.7 Reactor Coolant System filled and vented (or in progress),

in accordance with OP A.1.

4.1

.8 Establish levels in both OTSGs a't 85%-95% on their

,.~.

Operate Range indication per A.51 (to fill) or

~

A.6 (to drain).

s, 4.1

.9 Baron concentration in reactor coolant system is as required for reactor shutdown margin in accordance with OP B.6.

4.1

.10 Concentrated boric aci'd system available for service in accordance with OP A.12.

4.1

.11 Reactor Building HVAC operating per OP A.14, Section 4.1.

NOTE:

The following step refers to power supplies for SFAS analog and digital channels ONLY - not to individual SFAS equipment.

4.1

.12 Safety Features Actuation System energized per OP A.70.

4.1

.13 Integrated Control System energized per OP A.71, Section 4.0.

4.1

.14 Reactor Non-Nuclear Instrumentation System energized per OP A.73, Section 4.0.

l Rev. 2 B.2A-3

_g

' 3._.z.......

• Q-

~. - ~.

. 3,

._.3._

m

(;.

.,y.

N-i q

n.

V

/

4

.g_

f

. PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FRON' SERVICE (Continued)

' INITIAL d.'1

.15 Emergency shutdown panel instrumentation verified against -

i duplicate control room indicators for operability, except for narrow range Th.

/ '4'.1 '.' 16 Reactor Protection System and TSAT calculators are energized per OP A.69, Section 4.0.

~4.1

.17 OTSGs are lined up for recirculation per A.6,

?.3.

4.1

.18 Confirm operability and, through the Surveillanc,e Group, that surveillance requirements are current, i ;

s and will rummin current (or the duration of the DHS q,.

A v.<

outage, for the foilowing equipment:

14. 1

.18.1 Pressurizer level instrumentation N.1,t

.18.2 OTSGFullRangeadg'OperateRangellevel indications'

~

4.1

.10.3 RCS Subcooling Margin Monitors 1

4.1

.18.4 EMOV Positien indicator-power indicator I'

~

4.1

.18.5 EMOV Position indicator acoustic or T/C u

4.1

.18.6 EMOV Block. Valve indicator 4.1

.18.7 PZR Safety Valve indicato'r - acoustic and T/C '

4.1

.18.8 Containment Area High Range radiation monitors 4.1

.18.9 Wide Range Containment Water level instrumentation 4.1

.18.10 Containment Hydrogen Analyzers 4.1

.18.11 RB Emergency' Sump level instrumentation 1

4.1

.18.12 Containment Wide range pressure monitor / recorder 4.1

.18.13 Aux. Building Stack High Range Noble Gas Effluent Monitors 4.'

.18.14 Main Steam Lines Radiation Monitors i

4.1

.16.15 Incore Thermoccuples 4.1

.18.16

"-actor Building Furge isolation on high radiation 4

Rev. 2 B. 2 A -4 1

. <, '3{f' s

• ? '.

N.Y '?

, ::. ':. l? ' _ = * *~.' " "

' L -- --

• =L -l " '% '.

, 3. }..

• 4

__l'h,

K

.s f

PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FR.0M SERVICE (Continued) 4.l'

.18.17 Source Range NIs

~

4.1

.18.18' Reactor Protection Manual Pushbutton 4.1

.18.19 Reactor Bldg. Exhaust Stack High Range Noble i

.Sas Effluent Monitor 4.1

.19 RC Drain Tank (V-600) level is greater than 11 feet (30500 gals.), with V-600 boron concentration greater then RCS boron concentration, and chemistry requirements are met for RCS makeup.

4.2 Procedure i

_ CAUTION:

Verification of operability must include visual observation of the valves and the Control = Room indication.

4.2

.1 Cycle the following valves to verify operability:

VALVE NO.

DESCRIPTION INITIAL 4

HV-20570 A Main Steam Line Trap Isolation

.HV-20571 B Main Steam Line Trap Isolation HV-35069 B Main Steam Line Trap Isolation HV-35070 A Main Steam Line Trap Isolation FV-20527 Loop A Auxiliary Feedwater Control Valve FV-20528 Loop B Auxiliary Feedwater Control Valve PV-20562A Loop B Atmospheric Dump Valve PV-20562B Loop B Atmospheric Dump Valve PV-20562C Loop B Atmospheric Dumo Valve l

PV-20571A Loop A Atmospheric Oump Valve PV-205718 Loop A Atmospheric Dump Valve l

PV-20571C Loop A Atmospheric Dump Valve 4.2

.2 Verify TBV and ADV AUTOCLOSE switches, on HlRI, in NORMAL position.

~~

I Rev. 2 B.2A-5

• t.,_,,

• -4*

Y-

• • • E~~

- l PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FROM SERVICE (Continued)

INITIAL 4.2

.3 Fill Circulating Water System and maintain flow from Plant Cooling Water System in accordance with A.38, Section 4.1.

g 4

4 4.2

.4 Establish condensate system operation (condensate pump operating on mini-fiow to condenser) per OP A.47, Section 7.22.

p 4.2

.5 Place reactor sampling system in' service according to OP A.ll, Section 4.0.

4.2

.6 Place the Reactor Building Hydrogen Analyzer System in Standby in'accordance uith OP A.52, Section 4.1.

.I_

(R 4.2

.7 Verify Containment Atmosphere Radiation Monitor R-15044 is operable, and place in Sta.1dby in accordance with J+

OP A.65, Section 4.9.

s.

4.2

.8 Verify that the coolant radwaste system is lined up per OP A.16, Section 4.1.

Verify that the coolant waste receiver tanks, r-607A and B, have sufficient capacity for reactor coolant expansion volume.

4.2

.9 Place reactor chemical addition system in service according

/,,, '

to OP A.12, Section 4.0.

4.2

.10 Complete reactor coolant system initi'al filling and venting according to OP A.1, Section 4.1.

t

/

4.2

.10.1 Verify the Reactor Coolant System nitrogen spool pieces are removed as follows:

"A" OTSG Hot' Leg nitrogen spool piece removed AND blank flanges installed l

"B' OTSG Hot Leg nitrogen spool piece removed AND "dununy" spool piece installed L

Pressurizer nitrogen spool piece removed AND "dunray" spool piece installed '

I Spool pieces removed are NOT wired off or in any other way attached to any system piping or associated supports.

CAUTION:

DO NOT EXCEED DECAY HEAT SYSTEM PRESSURE / TEMPERATURE LIMITS (SEE PROCESS STANDARDS CURVE 101-3d to 101-4).

Rev. 2 B.2A-6 0

y

.;,w...

)_(.,g ;...,y -.,..,..'; _

o b

}'

PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FROM SERVICE (Continued) INITIAL j

/7s f:

4.2.11 Form a steam bubble in the' pressurizer according to b

OP A.3, Section 4.2.

NQT[:

Observe RCS Heatup Limit per Process Standards, Figure 101.la.

i CAUTION:

If the demineralizer being placed in service is i

not boron saturated, the RCS boron concentration will decrease.

4.2

.12 Place the letdown and purification makeup system in service in accordance with OP A.15, Section 4.2.

4.2

.13 Maintain PZR level at approximately 100 inches by

!i opening the level control valve, then closing it (Batch makeup). Controller NOT to De placed in AUTO -

with ' excessive AP across valve.

4.2

.14 IF necessary, TH[N close SFV-23604 to limit makeup to the RCS.

4.2

.14

.1 Record the time and RCS T in Control Room Log e

when SFV-23604 is opened or closed.

4.2

.15 Prepare to Complete RCS Venting

. 4.2

.15.1 Start RCS seal injection per OP A.15, Section 4.0.

Verify RCP seal flow.

4.2

.15.2 Adjust letdown flow to balance RCP seal in leakage.

If adequate letdown is not possible, reduce the RC pump seal flow control valve setpoint accordingly.

(Do not reduce flow to less than 3 gpm seal flow per RC pump.)

NOTE:

Ouring RCS heatup, it may be necessary to close SFV-23604 to limit makeup to RCS.

If this is

{

done, record the time and RCS Tc in Control Room Log when it is opened and closed.

CAUTION:

OBSERVE CURVES IN PROCESS STANDARDS AP.101-30 THROUGH AP.101.3K FOR SIMULTANEOUS OPERATION OF DECAY HEAT AND REACTOR COOLANT PUMPS.

1 4.2

.15.3 Increase reactor coolant system pressure to approximately 230 psig, as read on low range RCS pressure transmitter. (that pressure required for i

RC pump operation), per OP A.2.

Rev. 2 B.2A-7

- -' ~

~ ~ ~ ~ ~

~ ~~~

Y$ Y'!*'

~ ~. '

,L

.a,.

PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FROM SERVICE (Continued)

INITIAL 4.2

.15.4 Adjust decay heat system cooler outlet and bypass throttle valves as necessary to control reactor coolant system temperature <150*F.

CAUTION:

IF SWITCHYARD VOLTAGE IS >232KV, REFER TO SO 87-14.

CAUTION:

00 NOT RUN "A" OR "C" REACTOR COOLANT PUNPS BY THEMSELVES.

4.2

.16 Run each RC pump for five (5) minutes minimum, in accordance with OP A.2.

4.2.17 Complete RCS venting per OP A.1, Section 4.2.

4.2.18 Verify RCS chemistry is in accordance with AP.306 Section IIIA.

NOTE:

C1, F1, and 02 in the pressurizer must be within RCS specification prior to exceeding that pressure which allows simultaneous operation of RCPs and a decay heat system.

4.2.19 Start control rod drive cooling water system per OP A.9.

4.2.20 Verify that during heatup the reactor will be greater than 1% subcritical.

NQTE:

The 1% subcritical requirement is met when the l

boron concentration is greater than the COLD SHUTOOWN boron concentration value from OP B.6,-.7, Figure 2.

The shutdown calculation of Section 5.3 (OP B.6) is required when the I

boron concentration falls below this value. This boron concentration will satisfy the 1% shutdown.

4.2

.21 Verify OTSG valve lineup is per OP A.6, Section 4.2.

CAUTION:

00 NOT PLACE AUX FEEDWATER CONTROLS IN AUTO.

4.2

.22 Line up the Aux FW System per OP A.51 Section 4.2, except for equipment under Operations clearance.

Rev. 2 B.2A-8

.

.]

.*l. ?...v.c.I'l.{.',.,{. t..::ll~.'.'. ;.g __ *

/-

'*^26-

,0

. ~...

h'.

~ PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FROM SERVICE (Continued)

Ih1TIAL

.MgTLi One Diesel Generator may be taken out of service for maintenance providing normal power is available to both 4A and 48 4160 volt buses.

4.2

.23 Place A and B Diesel Generators in SFAS Standby per_ OP A.31, Section 4.1.

NQT[:

With Operations Unit Superintendent permission, dual verification requirements of SP.214.03 may be waived.

4.2

.24~ Verify Locked Valve List, SP.214.03, Enclosure 6.4 completed.

4.2

.25 Review 10 ADS ALARM IGNORE and POINT OFF SCAN groups per A.74A.

Review Bailey 855 DELETED POINT

SUMMARY

and DELETED MONITOR

SUMMARY

per A.75 and return points to normal as re. quired.

4.2

.26 Initiate RCS leakage monitoring in accordance with SP 207.048.

Perform SP 207.048 at least once per shift 4.2

.27 Verify Mechanical Maintenance Dept. has installed-a pipe cap

.immediately downstream of RCS-017 (temporary).

4.2

.28 Complete Enclosure 5.1, Tech Spec Operability Requirements 4.3 Decay Heat System Removal From Servict 4.3

.1 Instruct Tech Support Group to calculate time allowable to have_ Decay Heat Pumps out of service and maintain Incore Thermocouple temperature less than 190*F, from Dresent RCS temperature.

Time hrs 4.3

.2 Contact Maintenance Scheduling and Planning departments to ensure work is ready to start immediately ANO work is scheduled 'to be complited on one DHS train within time calculated by Tech Support.

4.3

.3 Establish the following plant conditions AND maintain throughout the Decay Heat System outage:

(

4.3

.3.1 RCS pressure within allowable limits for simultaneous operation of Decay Heat System and Reactor Coolant Pumps, in accordance with Process Standards Figure 101-3d through k.

i 4

Rev. 2 B.2A-9

- Wi

.x...lL l. &.r J i

.J

..~.

~'

PREPARATION FOR DECAY'iiEAT SYSTEM REMOVAL FROM SERVICE (Continued) 4.3

.3.2 Monitor incore thermocouples by using either:

4.3

.3.2.1 IDADS Computer 4.3

.3.2.2 SPOS 4.3

.3.2.3 Bailey Computer 4.3

.3.3 Pressurizer level within 90-115 inches.

CAUTION:

Maximum Makeup Tank level allowable with Cold Overpressure Protection selected is 36 inches.

i i

4.3

.3.4 Makeup Tank level 60-75 inches.

4.3

.3.5 OTSG levels 85%-95% on the Operate Range.

4.3

.4 To preclude accidental RCS dilution, place a Unit Operations Superintendent clearance on:

NOT(: The clearance on pumps P-622A and P-622B ONLY may be temporarily lifted and the pumps run for the minimum time necessary with the Unit

. Operations St perintendent's permission. When pump operatit'n is complete clearance requirements on both pumpt; apply once again.

P-622A and P-6226, CRCST pumps AND PLS-095 and PLS-096, DRCST Demin inlet velves (CLOSED).

AND PLS-073 and PLS-074, demin water isolation valves to Purif Demins 0-225A and B, CLOSED.

AND SFC-034, demin water isolation valve to SFP Demin 0-276, CLOSED.

4.3

.5 Verify Enclosure 5.1, Tech Spec Operability Requirements, is complete.

4.3

.6 Either or both Decay Heat Removal trains may now be shutdown in accordance with A.8, Decay Heat System.

Rev. 2 B.2A-10

}-. *** h '

• l.j._- __ y

~

. -. _... ~,.; _ f '[ _ ' *,'

PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FROM SERVICE (Continued) g,s 4.4 Plant Operation with Decay Heat System Secured

!{QTE:

If the period of plant shutdown is sufficiently long, losses to ambient may be adequate to allow reactor coolant temperature to stabilize below 212? F without forced RCS circulation or OTSG steaming: natural circulation is an acceptable means of decay heat removal. However, the. normal natural circulation parameters, as discussed in B.4, Section 6.0, will not be continuously evident. At low decay heat loads, natural circulation will be intermittent as sufficient driving force develops. Sufficient driving force may take hours to days to develop, depending on decay heat.

Development of the driving force will be indicated by a divergence of incore thermocouples and cold leg temperatures as incores heat up. When the AT becomes sufficient to push cold water over the RCP lip and into the core, incores and cold leg temperatures will tend to converge (incores decrease). Termination of the

" slug-flow" form of cooling will be indicated by the divergence of incore and cold leg temperatures once again as incores heat up.

4.4

.1 Monitor and maintain system parameters listed in Step '

4.3.3.

NOTE:

The Source Range NI count rate is expected to increase proportionate to any increase in RCS temperature.

4.4

.2 IF at any time Source Range NI count rate increases above i

6 cps, l

l THEN:

.1 Notify the Plant Nuclear Engineer and the Unit Operations Superintendent.

.2 Start P-705A and P-705B, Concentrated Boric Acid pumps.

.3 Open CBAST supply valve to suction of running MU/HPI pump.

BWS-040 to P-236 and P-238A, BWS-054 to P-23BB.

Rev. 2 B.2A-ll

/

/

-* ' 2

6.. -

e.' :.. (..~.....'**:.

... ~

t e.

PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FROM SERVICE (Continued)

.4-Continue to supply concentrated boric acid until count rate stops increasing or as directed by the Plant Nuclear Engineer or Unit Operations Superintendent.

.5 Isolate any inputs to the RCS which may be causing dilution.

.6 Letdown to the Flash Tank as required to maintain pressurizer and MUT levels.

4.4

.3 Once per day, have letdown sampled for boron concentration. These results should be trended by the Chemistry Dept. and provided to the Shift Supervisor for his review.

4.4

.4 1F RCS makeup is needed, THEN supply makeup with one of the following methods, listed in order of preference:

4.4

.4.1 Jog.open SFV-25003 or SFV-25004, BWST outlet valves, to the running MU/HPI pump.

4.4

.4.2 Makeup from V-600 as follows:

4.4

.4.2.1 Request sample to verify V-600 chemistry is satisfactory, and that boron concentration is greater than RCS boron concentration.

4.4

.4.2.2 Start P-601A and P-601B, RC Orain Tank pumps.

4.4

.4.2.3 Open RCD-027, RC Drain Tank pump discharge to Letdown System.

4.4

.4.2.4 When makeup is sufficient, stop P-601A and P-6018, and close RCD-027.

4.4

.4.3 Batch to the Makeup Tank as follows:

4.4

.4.3.1 Obtain Unit Operations Superintendent permission to remove DRCST administrative clearance.

4.4

.4.3.2 Calculate required batch per B.9, ensuring batch will not decrease RCS boron concentration.

4.4

.4.3.3 Add batch to Makeup Tank in accordance with OP A.15, Section 5.2.

4.4

.4.3.4 Restore clearance removed in Step 4.4.5.3.1.

l l

Rev. 2 8.2A-12 l

C'.. ; c. :

.6

r'a.

PREPARATION FOR DECAY HEAT SYSTEM REMOVAL FROM SERVICE (Continued) 4.5 RCS Heatuo Mitiaation with Both Decav Heat Trains Shutdown 4.5

.1 IE RCS incore temperature reaches 150*F (except for testing),

THEN maintain Heat Removal as follows:

4.5

. l.1 Initiate OTSG filling / draining per Enclosure 5.2 of this procedure.

4.5

.l.2 Maximize RCS Letdown flow, consistent with available makeup.

This will increase RCS heat removal by the_ Letdown System.

4.5

.2 Notify those personnel issued DHS clearances of the importance of returning Decay Heat Removal System to operability.

4.5

.3 lE RCS incore temperature increases to 190*F (except for testing), lHEN 60 TO C.12, Loss of Decay Heat Removal System.

4.6 Decav Heat Removal System Return to Service 4.6

.1 WHEN either Decay Heat Removal Train is returned to 1

service, THEN Startup DHS Train and establish DHS

(~

cooling in accordance with A.8, Decay Heat System.

5.0 ENCLOSURES 5.1 Tech Spec Operability Requirements i

5.2 OTSG Filling / Draining i

i s

Rev. 2 B.2A-13

.....;- \\ '.. ;..', :

.; J.' :..

.'..[

m g.

ENCLOSURL

,1 j

TECH SPEC OPERABILITY REQUIREMENTS L.

((

NOTE:

The attached Technical Specifications are considered to be applicable should the RCS temperature be permitted to exceed 200* F but remain below 280" F and, of course, the reactor remains subcritical.

It is Regulatory Compliance's understanding that each of these Technical Specification requirements will be complied with as a precaution, against the RCS exceeding 200, F.

Tech Spec section 1.3 defines " operability" and applies when verifying the requirements of this Enclosure.

Applicable Requirements

_.l Tech Spec Requirement Comments Tech Spec Met (Initial)

[

1) Definition 1.2.1 These are the only modes proposed by the Decay Heat 1.2.1 N/A

" Cold Shutdown" and System outage configurat{ons. Temperature is also 1.2.12 "Heatup-limited to less than 280 F by excluding several 1.2.12 N/A Cooldown Hode" Technical Specifications, which would become appli-cable at that temperature, from this list.

2) Definition 1.3 This applies to all systems required to be operable 1.3 N/A "Operabili ty" as tabulated in this list. This includes their f

required auxiliaries (e.g. Diesel Generators).

[

3) Section 2 " Safety The applicability statement excludes these specifi-NONE N/A Limits and Limiting cautions because these setpoints are "during power Safety System Set-opera tion. " Clearly the plant will not exceed these tings", Section 2.1 limits during the Decay Heat outage.

" Safety Limits, Reac-tor Core" l

4) Section 2.2 " Safety Superseded by the more limiting requirements of Tech.

'NONE N/A-

.c Limits, Reactor System Spec. 3.2.2 (LTOP)

Pressure" ENCLOSURE 5.1 PAGE 1 0F 10 Rev. 2 l

B.2A-14 k

-. ~, _ _.

-w s

'/

ENCLOSt

.'5.1 I

TECH SPEC OPERABILITY REQUIREMENTS (Continued)

Applicable Requirements Tech Spec Requirement Comments Tech Spec Met (Initial)

5) Section 2.3 " Limiting Although not explicitly stated, this Section is not NONE N/A b

Safety System applicable during the decay heat outage because,

'f '

Settings, Protective as the Bases states that these instrument channels Instrumentation" monitor plant conditions and "will cause a reactor trip." Since the plant will already be tripped and 9

shutdown by greater than 1 percent ak/K, it is not

.j logical for this Section to apply. All the setpoints

f.,

and limits in Table 2.3-1 and Figures 2.3-1 and 2.3-2 either cannot be approached or are permitted to be bypassed during cold shutdown (e.g. RCS temperature t

M less than 280'F, pressure less than a maximum of l}

500 psig).

a

6) Section 3.1 The applicability statements states that Section 3.1 3.1.1.3(B) i,;

" Reactor Coolant

" Applies to the operating status of the Reactor System" Coolant System." Since the RCS loop must be operable 3.1.1.5 per 3.1.1.5, this group of specifications are

[.

applicable. This means that the proper group of RC 3.1.1.6

^

Pumps and OTSGs, must be operable. The required a-auxilaries for operable Reactor Coolant Loop and J..

OTSG's must also be operable. A method of F.

maintaining pressure control'in the RCS (e.g. makeup system, seal injection and letdown) and a source of water and steam' relief to atmosphere for the OTSG's. j, One pressurizer code safety valve must be operable and RCS high point vents must be operaole. t. i-l -ii j ENCLOSURE b.1 PAGE.2 0F 10 i Rev. 2 - B.2A-15 f a i

~ l .__~ ENCLOSt ."S.1 .i ~ + TECH SPEC OPERABILITY REQUIREMENTS (Continued) ? -Applicable: Requirements - .('. Tech Spec Requirement Comments Tech Spec Met (Initial): Section 3.1 Heatup cooldown rates must be controlled per Spec 3.1.2 N/A ~~ " Reactor Coolant 3.1.2. Since criticality will not be attempted, j System" (Continued) Specification 3.1.3 will be complied with. Reactor 3.1.4 Coolant Activity (3.1.4) Chemistry (3.1.5) and Leakage a (3.1.6) necessarily apply. This may present some 3.1.5 questions on the timing for the installation of l-R15044 and 100 as replacement monitors for RIS001 3.1.6 A, B, C, D and E. Moderator temperature coefficient will remain negative (Spec'3.1.7) and no attempt will 3.1.9 be made to do physics testing (Spec 3.1.8). Specifications 3.1.9 " Control Rod Operation" must be complied with, although there are no plans to move - any control rods.

7) Section 3.2 "High Specification 3.2.1 is not applicable since the 3.2.2 Pressure Injection, reactor will remain subcritical. Specification Chemical Addition, and 3.2.2 will be applicable when the RCS is~ closed to Low Temperature Over-atmosphere.

pressure Protection (LTOP) Systems" ~

8) Section 3.3 " Emergency Specification 3.3.1 is not applicable since the 3.3.4 Core Cooling, Reactor The reactor will remain subcritical. Specifications Building Emergency 3.3.2 and 3.3.3 are not very meaningful since Cooling and Reactor Specification 3.3.1 excludes these systems from Building Spray Systems" " Pressure needing to be operable. Specification 3.3.4, " Pressure Isolation Valves" is, however, applicable since RCS pressure may or will exceed the Decay Heat system suction piping design pressure.

i ENCLOSURE 5.1 PAGE 3 0F 10 ~ Rev. 2 -l B.2A-16

s ,); '../; I-ENCLOSb. 5.1 S g TECH SPEC OPERABILITY REQUIREHENTS (Continued)

\\:

? Applicable

Requirements Tech Spec Requirement Comments Tech Spec Met (Initial) i'

9) Section 3.4 " Steam and Specification 3.4.1 is not applicable since it NONE N/A Power Conversion relates to RCS temperature being above 280*F.

System" Specification 3.4.2 is not applicable since it refers 5 to criticality (see also Section 3 above).

10) Section 3.5 Specification 3.5.1.1 refers to "Startup and Table 3.5.1-1

" Instrumentation Operations" and therefore do not apply during the g-Systems" and 3.5.1 decay heat outage. However, the following RPS Man.' Trip PB " Operational System instrumentation shall be operable: Reactor Source Range Instrumentation" protection Manual pushbutton, source range instrument Instrument Chan. P channel, and " Process Instrumentation" described in Pressurizer Water l Table 3.5.1-1 with the exception of safety valve Level 'T position indication. This includes Reactor Building Subcooling Margin Purge Isolation on high radiation (see Spec 3.6.8). Monitors The auxiliary feedwater items in Table 3.5.1-1 are ENOV Pos1tton excluded since the plant will not be in the startup Indicator - Power or power operation modes. Indicator EMOV Position Indicator Acoustic or T/C Safety Valve Position Indicator T/C Safety Valve Position Indicator Acoustic Reactor Bldg. Purge Isolation on High Radiation i ENCLOSURE 5.1 PAGE 4 0F 10 Rev. 2 B.2A-l? O 9 I

J. ,1 ENCLOSL... '5.1 '.I l~ TECH SPEC OPERABILITY REQUIREMENTS (Continued) s k,'. 3 i' - Applicable Requirements .I Tech Spec Requirement Comments Tech Spec Met (Initial) j,,,

11) Section 3.5.2 " Control The applicability statement indicates that this NONE N/A Rod Group and Power Specification applies during " power operation."

lt Distribution Limits" Therefore it is not applicable during the Decay Heat [.{ outage since the rods will not be withdrawn.

s L

12) Section 3.5.3 " Safety See discussion under Section 2.3 " Limiting Safety NONE N/A T.

Features Actuation System Settings, Protective Instrumentation" i;, System Setpoints" Based on the concepts of the discussion for ? ' Section 2.3 and the specific bypass notes and ~ action statements of Table 3.5.1-1 for safety ~ features equipment (Column C " Bring to hot shutdown), it is evident that this specification will not be applicable during the Decay Heat outage. It should be noted that the RCS will always be below hot shutdown conditions. l.'

13) Section 3.5.4 "Incore Since the plant will remain shutdown (below NONE N/A f

80 percent operating power), this specification is not required to be operable. Source range 1... L instrumentation will be available and incere l thermocouples will be available (see below). I

14) Section 3.5.5 Should the plant go above 200*F, Table 3.5.5-1, TABLE 3.5.5-1 3

L " Accident Monitoring would become applicable. Therefore these [^ i Instrumentation" instruments shoula be made operable, with the Containment Area U exception of the Radwaste Vent (note 4). This liigh Range if l may not have been the NRC's intent but this is Radiation Monitor 1.. what the Tech Spec says. Wide Range Contain-j !, ment Water Level Containment [. 9 Hydrogen Analyzer j, Emerg. Sump Level ENCLOSURE 5.1 PAGE 5 0F 10 ? Rev. 2 8.2A-18

~. ,I ~ .' i ENCLOSL. 5.1 TECH SPEC OPERABILITY REQUIREMENTS (Continued) Applicable Requirements Tech Spec Requirement Comments Tech Spec Met (Initial) Section 3.5.(Continued) Containment Wide ?. " Accident llonitoring Range Pressure Instrumentation" Honitor/ Recorder

/

High Range Noble j Gas Effluent Monitors: . R.B. Exhaust Stack . Aux. Bldg. Stack Main SteamI1ne Raa Monitors Subcooling Margin Monitors Incore Thermocouples I

15) Section 3.6 " Reactor The applicability statement indicates that 3.6.8 Building" since the plant will be shutdown by more than 1 percent ak/k that containment integrity is not required.

It should be noted that the reactor g, coolant pressure should not exceed 300 psig. therefore "all three" conditions of specification 3.6.1 will not be met. It should also be noted that the reactor coolant system will be closed to atmosphere prior to temperature exceeding 140*F (see Specification 3.6.2 and 1.2.6). Specification 3.6.7 is not applicable since the plant will be shutdown by greater than 1 percent ak/k. a. i '. '. ENCLOSURE 5.1-PAGE 6 0F'10 Rev. 2 B.2A-19 3

s i ENCLOSL '5.1 ,j, TECH SPEC OPERABILITY REQUIREMENTS (Continued) Applicable Requirements .( Tech Spec Requirement Comments Tech Spec Met (Initial) 16) Section 3.7 " Auxiliary Specifications 3.7.1 and 3.7.2 do not apply since the 3.7.3 N/A plant will remain subcritical. However, those required auxiliaries for the. operating systems will be 3.7.4 required to be operable (e.g. Definition 1.3). Specification 3.7.3 will require the plant to be placed in " Cold Shutdown" if both Diesel Generators become inoperable. Specification 3.7.4 requires the pressurizer to be operable with 126 Ku of heaters. Specification 3.7.6 indicates that "Startup and operation are not permitted" without voltage protection, and the action statement requires the plant to be brought to hot shutdown. This clearly implies that the under voltage and over voltage protection relays are not required during tne decay heat outage (see also note 1 of Table 3.7-2). ?

17) Section 3.8 " Fuel Does not apply during the Decay Heat outage.

NONE N/A Loading and Refueling" ~

18) Section 3.10 " Secondary Does not apply during the decay Heat outage because NONE N/A System Activity" the reactor will not be in operation. However,

'C secondary chemistry shall be. carefully controlled to protect the OTSGs. It should be noted that the plant has been shutdown for a sufficient period to virtually eliminate iodine 131 by natural decay. i

19) Section 3.11 " Reactor This specification applies (see 3.11.4).

3.11.4 Building Polar Crane and Auxiliary Holst" ENCLOSURE 5.1 PAGE 7 0F 10 Rev. 2 B.2A-20 ~

_. ~. N '4 ENCLOSL 5.1 ) f. y TECH SPEC OPERABILITY REQUlkEt1EWlS. (Continued) kl Applicable Requirements' i. Tech Spec Requirement Coensents Tech Spec Met (Initial) 'i: c i.

20) Section 3.12 " Snubbers" This specification applies during the Decay Heat 3.12-outage. Although not explicitly stated in the second T[*

sentence of the applicability statement, the intent is that snubbers required for the heatup-cooldown mode must be operable. Those snubbers which are " required auxilaries" for operating systems shall be operable. 1.'

21) Section 3.13 " Air Section 3.13.1 will not be. applicable since 3.13.2 Filter Systems" containment integrity will not be required as a result of the plant being shutdown by more than 1 percent ak/k 5

(see Section 3.6). Section 3.13.2 has always been fe,' applicable. The action statement requires shutdown to at least hot shutdown and the suspension of fuel r?. handling and crane operations. Specifications 3.13.3 jf and 3.13.4 are simply action statements for 3.13.1. h.

22) Section 3.14 These Specifications have always been applicable and 3.14 i ;* t will continue to be applicable for the Decay Heat 1.,

outage. It should be noted that action 3.14.2.3.d would require placing the plant in cold shutdown in j' 60 hours of loss of all fire suppression systems. g-l :;

23) Sections 3.15 through Applicable at either "all times" or "during releases",

3.15 thru 3.26 N/A p '. 3.26 " Radiological therefore, applicable during the Decay Heat outage. p Effluent Technical j-Specifications" r i f-ENCLOSURE 5.1 PAGE 8'0F 10 i,* i Rev. 2 i-B.2A-21 -h i

..~

s s

ENCLOSb. 5.1 )- ,, l TECH SPEC OPERABILITY REQUIREMENTS (Continuest)

-f Applicable Requirements Tech Spec Requirement Comments Tech Spec Met (Initial)

$h

24) Section 4 " Surveillance This section is invoked for those items requireo to 4.0 N/A Standards" be operable as described above.

It should be noted

f that the surveillance final due date will expire for the Internals Vent Valves during the Decay.

'C Heat outage. Should NRC approval of our Proposed l-Amendment not be forthcoming, a safety analysis, demonstrating that the internal vent valves are ~ not required to be operable, will be developed and approved prior to the decay heat outage (see 4 Table 4.1-2 item 13). It.should be noted that the IST Program for valves a'nd pumps shall be implemented for those components which are required to be operable. The ASME B and PV Code 5 Section IX does not specify only cold shutdown for relief from testing during periods of plant shutdowns. Specification 4.3, " Testing Following i Opening of Systems", relates to taking the ' reactor critical and therefore does not apply specifically, however, the OTSGs and RCS Loops will have to be determined to be operable. It should also be noted that any LLRT failures, to date, would require the RCS to remain depressurized (Specification 4.4.1.2.4). 1 I. ENCLOSURE 5.1 PAGE 9 0F 10 .J Rev. 2 B.2A-22 3i w

t s ENCLOSL '5.1 .). TECH SPEC OPERABILITY REQUIREMENTS (Continued) TIME COWLETED: DATE: +;- OPERATOR: f. I' REMARKS: 'i: e. j.- ,:i 1.. g._ r. ]? .s

.~.,

is l... 1. ENCLUSURE 5.1 PAGE~10 0F 10 c. END-Rev. 2 B.2A-23 i. j O l

("5 ENCLOSURE 5.2 OTSG FILL / DRAIN 1.0 PROCEDURE 1.1 Complete the valve lineup in accordance with Section 2.0 of this Enclosure. NQT[: Both OTSG 1evels are to be maintained between 85% and 95% on their respective Operate Range indications. It is also advisable to maintain both OTSG levels approximately the same at all times. NQTE: It is expected that a fill / drain rate of 20 gpm will be sufficient to reduce RCS temperature below 150*F. NOTE: Either OTSG fill or drain may be established first, depend,ing on initial OTSG 1evels. i 1.2 Establish OTSG draining as follows: 1 CAUTION: The OTSG drain booster pump should not be operated for extended periods without a discharge flow path. ._( ' 1.2 .1 START P-3098, 'B" OTSG Drain Booster Pump" at MCC 202. 1.2 .2 THROTTLE OPEN HV-20612. "0TSG Drain to H.P. Condenser" at Panel H2YS as necessary to achieve either of the following, as applicable: IF OTSG fill was established first, THEN adjust the drain rate to match fill rate; i.e., maintain a constant OTSG 1evel. 1F OTSG draining is being established first, THEN adjust drain rate to achieve an OTSG level decrease of 0.5 in/ min; i.e., 20 gpm. A higher or lower rate is acceptable if better suited to the current plant conditions. 1.2 .3 WHEN OTSG draining is no longer required, THEN: CLOSE HV-20612, "0TSG Orain to HP Condenser". STOP P-3098, "B" OTSG Orain Booster Pump. 1.3 Establish OTSG filling as follows: NOTE: Both OTSGs must be at or near atmospheric pressure for gravity filling from the CST to occur. ENCLOSURE 5.2 PAGE 1 0F 3 Rev. 2 B.2A-24 f I l ._**.i- ~ ~ ~ ~ [ '*;* ~ ~ ~ ' _ __._..__.__ ~ o o.

• S ENCLOSURE 5.2 OTSG FILL /0 RAIN (Continued)

MQTE: OTSG filling will result in RCS cooling. Additional RCS makeup may be required to maintain pressurizer level. 1.3 .1 THROTTLE OPEN FV-20527 ("A" OTSG) AND FV-20528 ("8" OTSG). 1.3 .2 Throttle FV-20527 AND FV-20528 as necessary to achieve the following: lE OTSG draining was established first, THEN adjust the fill rates to match drain rates; i.e., maintain a constant OTSG level. lE OTSG filling is being established first, THEN adjust fill rates to achieve an OTSG level increase of 0.5 in/ min; i.e., 20 gpm. A higher or lower rate is acceptable if better suited to the current plant conditions. 1.3 .3 WER OTSG filling is no longer required, THEN close FV-20527 ANO FV-20528. 1.3 .4 lE a sufficient fill rate cannot be established by gravity draining the CST to the OTSGs AND RCS temperature is 3150' F, THEN: (* NQTE: Opening e.ither AFW pump recirc valve will result in some gravity flow f rom the CST to the Condenser. 1.3 .4.1 QPEN FWS-051, "AFW Pump P-318 Recirc Valve". 1.3 .4.2 VERIFY breaker 4B10. "AFW Pump P-318 Supply" is racked-in AND control power "on". 1.3 .4.3 ,qkQ]i FV-20527 and FV-20528, THEN: NQT[: Limitation and Precaution 3.17 restricts the number of allowable AFW pump starts. I ~ i START AFW Pump P-318. l l throttle open FV-20527 and FV-20528 as necessary to l establish the desired fill rate. 1.3 .4.4 WHEN OTSG fill is no longer required, THEN: 3 Close FV-20527 and FV-20528 Stop AFW Pump P-318 Close FWS-051 l l ENCLOSURE 5.2 PAGE 2 0F 3 Rev. 2 8.2A-25 i i ___,..a_ . _ _$. ta i nf %.' ' I* ..___.i a,. _ _ ; 1 _1_ ;;

• i "'.

ENCLOSURE 5.2 OTSG FILL / DRAIN (Continued) 1.4 Maintain Hotwell level 3'-7" as follows: 1.4 .1 VERIFY Condensate Pit Sump Pump (s) AND Polisher. Sump Pump (s) are operable to transfer water to a RHUT. 1.4 .2 QP E GSC-007 and GSC-009, " Gland Steam Crndenser Drains", to establish Hotwell draining. 1.4 .3 throttle GSC-007 and GSC-009 as necessary to control Hotwell level. 1.4 .4 VERIFY the Condensate Pit Sump Pump (s) AND Polisher Sump Pump (s) operate as necessary to maintain sump levels. 1.4 .5 WHEN Hotwell draining is no longer required, THEN close GSC-007 AND GSC-009. 1 i i ENCLOSURE 5.2 PAGE 3 0F 3 Rev. 2 8.2A-26 c,.., ;,,

~'}.?.:, n ':...,_.,......;..,r,

., ; '.. r!=.'"'~ ~~": '[ '.

SECTION 2.0 r.. VALVE LINEUPS VALVE NO. VALVE NAME POSITION INITIAL MSS-055 OTSG "A" Vent to Atmosphere Closed MSS-038 OTSG "A" Vent to Atmosphere Closed MSS-058 OTSG "A" Nitrogen Supply Closed FWS-069 OTSG "A" Drain Open FWS-065 OTSG "A" Steam Annulus Orain Closed FWS-067 OTSG "A" Steam Annulus Drain Closed FWS-071 OTSG "A" Drain Open FWS-073 OTSG "A" Drain Open FWS-075 OTSG "A" Drain Open FWS-077 OTSG "A" Drain Open HV-20609 OTSG "A" Drain Closed MSS-056 OTSG "B" Vent to Atmosphere Closed MSS-039 OTSG "B" Vent to Atmosphere Closed MSS-059 OTSG "B" Nitrogen Supply Closed FWS-066 OTSG "B" Steam Annulus Drain Closed FWS-068 OTSG "B" Steam Annulus Drain Closed FWS-070 OTSG "B" Drain Open FWS-072 OTSG "B" Drain Open FWS-074 OTSG "B" Drain Open FWS-076 OTSG "B" Drain Open FWS-078 OTSG "B" Drain Open HV-20610 OTSG "B" Drain Closed FWS-081 P-309A Suction Closed Rev. 2 B.2A-27 "~

• L.

. ~ :.:. ',.,]_~ ~ ^ . _. L... ; ( ?.? ~""[ f. . ;(*;

rs SECTION 2.0 (Continued) l VALVE LINEUPS VALVE NO. VALVE NAME POSITION INITIAL FWS-086 P-309A Discharge Closed l FWS-082 P-3098 Suction Open FWS-087 P-3098 Discharge Open SWS-080 P-3098 Seal Water Open j FWS-098 P-3098 Isolation Valve for PI-30929 Open 4 FWS-083 P-309A Bypass-Closed FWS-110 P-3098 Sypass Closed 4 FWS-106 P-309A to 8 Discharge Isolation Closed FWS-102 Acid Cleaning Inlet Inside R8 Locked Closed i FWS-080 OTSG Drain Isolation in R8 Open I HV-20611 OTSG Orain Isolation Outside R8 Open FWS-093 OTSG Orain Isolation to Spent Regen Tanks Closed l FWS-092 OTSG Orain to HP Condenser Open j HV-20612 OTSG Drain to HP Condenser Closed MCM-155 HV-20612 Bypass Valve Closed i FWS-096 OTSG Orain Iso, to Makeup Domin Area Sumps Closed FWS-131 OTSG Chemical Recire Header Isolation Closed SCA-157 Hydrazine Addition to Chemical Recirc Header Closed i SCA-158 Ammonia Addition to Chemical Recirc Header Closed FWS-126 OTSG "A" Chemical Recirc to Aux Feed Iso Closed i FWS-128 OTSG "A" Chemical Recirc to Aux Feed Iso Closed FWS-120 Aux Feedwater from P-318 Isolation to OTSG A Locked Open i j FWS-562 FWS-120 Bypass Closed Rev. 2 I 8.2A-28 I ""y : y 5{:. % :,.%.,d.: :... ' '.".' s : . - - - - - - - ;' R.;': * :.=~~."~ ~~~'; ".

SECTION 2.0 (Continued) VALVE LINEUPS VALVE NO. VALVE NAME POSITION INITIAL FWS-119 Aux Feedwater from P-319 Isolation to OTSG B Locked Open FWS-560 FWS-119 bypass Closed FWS-125 OTSG "B" Chemical Recirc to Aux Feed Iso Closed FWS-127 OTSG "B" Chemical Recirc to Aux Feed Iso Closed FWS-485 Auxiliary Feedwater Drain Valve Closed FWS-554 FWS-063 bypass Closed FWS-551 FWS-064 bypass Closed FWS-063 Auxiliary Feedwater to OTSG "A" Locked Open FWS-064 Auxiliary Feedwater to OTSG "B" Locked Open MCM-057 Condensate Storage Tank Outlet to Turbine Locked.Open Driven Auxiliary Feed Pump ( ~ FWS-045 Turbine Driven Auxiliary Feed Pump Suction Locked Open Valve FWS-733 First Off Isolation for PI/PT-31803 Open PI-31803R Pump P-318 Suction Pressure Indicator Open Root Valve FWS-737 Test Gauge Isolation Closed FWS-734 First Of f Isolation for PI/PT-31801 Open PI-31801R Pump P-318 Discharge Pressure Indicator Open Root Valve FWS-738 Test Gauge Isolation Closed FWS-053 Pump Discharge Valve Locked Open FWS-493 FWS-053 Bypass Closed FWS-051 Pump Recirc Valve Closed FWS-055 Pump Flow Test Valve Locked Closed Rev. 2 B.2A-29 T.'.. ..T: :.:. .. ~ ',, '. .,;..~..- ~.

o (*. SECTION 2.0 (Continued) VALVE LINEUPS. VALVE NO. VALVE NAME POSITION INITIAL FWS-492 FWS-055 Bypass Locked Closed FWS-135 Vent Closed FWS-136 Drain Closed FV-31855 Auxiliary Feedwater Pump Test Valve Closed FWS-710 Auxiliary Feedwater Test Line Vent Closed FWS-704 Pump Casing Vent Closed FWS-705 Pump Casing Vent Closed MCM-542 Condensate Storage Tank level Transmitter Open Root Valve MCM-058 Condensate Storage Tank Outlet to Motor Locked Open Driven Auxiliary Feed Pump I FWS-046 Motor Driven Auxiliary Feed Pump Suction Locked Open Valve FWS-735 First Off Isolation for PI/PT-31903 Open FWS-739 Test Gauge Isolation Closed PI-31903R Pump P-319 Suctio'n Pressure Indicator Open Root Valve FWS-736 First Off Isolation for PI/PT-31901 Open PI-31901R Pump P-319 Discharge Pressure Indicator Open Root Valve 1 FWS-740 Test Gauge Isolation Closed FWS-054 Pump Discharge Valve Locked Open i FWS-559 FWS-054 Bypass Closed f FWS-052 Pump Recirc Valve C'osed FWS-708 Pump Casing Vent Closed l Rev. 2 B.2A-30 l I .'. T :.c. ;;.. ; ,e.. ..;jf.C.,.

.,9

...'. '.~. :.xr.' ~. T Q :';T ~^ Q T-3 : ?..

,e I SECTION 2.0 (Continued) VALVE LINEUPS VALVE NO. VALVE NAME POSITION INITIAL FWS-709 Pump Casing Vent Closed PCW-079 Folsom South Canal Water to Suction Locked Closed Motor Driven Auxiliary Feed Pump PCW-076 Folsom South Canal Water to Suction Locked Closed Turbine Driven Auxiliary Feed Pump FWS-553 "B" Auxiliary Feed Line Vent Outside Closed Reactor Building FWS-555 "A" Auxiliary Feed Line Drain Outside i Reactor Building Closed FWS-557 "A" Auxiliary Feed Line Vent Closed FWS-532 "B" Auxiliary Feed Line Drain Outside i Reactor Building Closed FV-20527 Auxiliary Feedwater to "A" Steam Closed Generator. Level Contr'ol Valve (Bailey in auto / manual and hand jack in neutral.) i FWS-556 Drain Valve Upstream of FV-20527 Closed FV-20528 Auxiliary Feedwater to "B" Steam Closed Generator Level Control valve ~ (Bailey in auto / manual and hand jack in neutral.) HV-31826 Auxiliary Feed Header Cross Connect Isolation Open ~ HV-31827 Auxiliary Feed Header Cross Connect Isolation Open HV-20577 Auxiliary Feedwater Isol Valve to "A" OTSG Closed HV-20581 Auxiliary Feedwater Isol Valve to "A" OTSG Open HV-20578 Auxiliary Feedwater Isol Valve to "B" OTSG Closed HV-20582 Auxiliary Feedwater Isol Valve to "B" OTSG Open i l se l Rev. 2 B.2A-31 / ( '...n* =, - ~7 3 ~ ' ~ " ~ ~ - ~ ' ~ ' ~

m y..:. n-..:,-- .-, :.,ua ,N., yL .ef s Ma m ' .,.,Ry l: 3 , t .e. ,h; - O .:7 s ? 1 =, -SECTION 2 0 (Continued) VALVE LINEUPS' , s,- .a s,. . n.. g i ' DATE t-s s: TIME STARTED 3' + TIME COMPLETED ( OPERATOR t REMARKS: p 6 r d / s e g I g i s I g a f f e ~ f . h, f* I 9 v j 4 ( / f .r I e to t t END l Rey, 2 8.2A-32 ..$/.. e* +5 '.*g*. 1 +

• +a J,

.2 _,., u ;

• _ O * ',"; ",

?8..'*. _' l,? *

• P -}}