ML20236Y083

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Proposed Tech Specs Changing TS 3.7.1.3, Plant Sys - Condensate Storage Tank & Adding TS 3.7.1.7, Plant Sys - Atmospheric Steam Dump Valves
ML20236Y083
Person / Time
Site: Millstone Dominion icon.png
Issue date: 08/04/1998
From:
NORTHEAST NUCLEAR ENERGY CO.
To:
Shared Package
ML20236Y081 List:
References
NUDOCS 9808110159
Download: ML20236Y083 (16)
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Text

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i Docket No. 50-336

B16902 l

l Attachment 3 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Condensate Storage Tank and Atmospheric Steam Dump Valves Marked Up Pages 1

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August 1998 9808110159 990004 F PDR ADOCK 05000336 P PDR ,

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i g -- Novemt,ei 3,1335 --  ;

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS (-

SECTION EAE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE . . . . . . . . . . . . . . . . . . . . . 3/4 7-1 l Safety Valves . . . . . . . . . . . . . . . . . . . . . 3/4 7-1 Auxiliary Feedwater Pumps . . . . . . . . . . . . . . .

3/4 7-4

! Condensate Storage Tank . . . . . . . . . . . . . . . . 3/4 7-6 Activity . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-7 Main Steam Line Isolation Valves . . . . . . . . . . . 3/4 7-9 i Main Feedwater Isolation Components (MFICs) . . . . . . 3/4 7-9a 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION . . . 3/4 7-10 3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM . . . . . 3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM . . . . . . . . . . . . . . . . . 3 / 4 7- 12 i

3/4.7.5 FLOOD LEVEL . . . . . . . . . . . . . . . . . . . . . . 3/4 7-13 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM . . . . . . . 3/4 7-16 3/4.7.7 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . . . 3/4 7-19 3/4.7.8 SNUB 8ERS .................... . . 3/4 7-21 [

3/4.7.9 DEL ETED . . . . . . . . . . . . . . . . . . . . . . . . 3 /4 7-3 3 3/4.7.10 DE LETED . . . . . . . . . . . . . . . . . . . . . . . . 3 /4 7-33 3/4.7.11 ULTIMATE HEAT SINK . . . . . . . . . . . . . . . . . . 3 / 4 7-3 4 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES . . . . . . . . . . . . . . . . . . . . . 3/4 8-1 Operating . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-1 Shutdown . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-5 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS . . . . . . . . . . . 3/4 8-6 A.C. Distribution - Operating . . . . . . . . . . . . . 3/4 8-6 A.C. Distribution - Shutdown . . . . . . . . . . . . . 3/4 8-7 D.C. Distribution - Operating . . . . . . . . . . . . . 3/4 8-8 D.C. Distribution - Shutdown . . . . . . . . . . . . . 3 /4 8-10 D.C. Distribution (Turbine Battery) - Operating . . . . 3/4 8-11 t

/Woybc $h ba y n /~, ...... 3'/V 9 - 7 c l

MILLSTONE - UNIT 2 VIII Amendment No. 77, p, pp, JM, HE, 47,177,///

azzs

-August 1, 'o75-PLANT SYSTEMS .

CONDENSATE STORAGE TANK .

LIMITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank shall be OPERABLE with a minimum contained volume ofl50,000 gallons.

at >

APPLICABILITY: MODES 1. 2 and 3.

/G 5,000 ACTION:

With less than 150,000 gallons of water in the condensate storage tank, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

a. Restore the water volume to within the limit or be ing HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or '
b. Demonstrate the OPERABILITY of the fire water system as a backup supply to the auxiliary feedwater pumps and restore the condensate storage tank water volume to within its limits within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS

, 4.7.1.3. The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the water level.

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! MILLSTONE - UNIT 2 3/4 7-6 i j i

INSERT NEW PAGE - Pace 3/4 7-9c PLANT SYSTEMS ATMOSPHERIC STEAM DUMP VALVES LIMITING CONDITION FOR OPERATION 3.7.1.7 Each atmospheric steam dump valve shall be OPERABLE.

1 APPLICABILITY MODES 1,2, and 3.

ACTION:

a. With one atmospheric steam dump valve inoperable, restore the inoperable valve to OPERABLE status within 7 days or be in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. i
b. With more than one atmospheric steam dump valve inoperable, restore one inoperable valve to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.1.7 Verify one complete cycle of each atmospheric steam dump valve at least once per 18 months.

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3/4 7-9c L_______________________________--_-_-__-___ - - - -

s. ..

.J - PLANT SYSTEM __S -

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matrt 4

3/4.7.1.2 AUXILIARY f>TDWATER PUMPS The OPERABILITY of the auxiliary feedwater pumps ensures tshat the Reactor Coolant System can be cooled down to less than 300*F from normal operating c,onditions in the event of a total loss of.off-site power.

Any single actor driven or steam driven pump has the required capacity to provide sufficient feedwater flow to remove reactor decay heat and reduce the RCS temperature to 300*F where the shutdown cooling-system may be placed into operation for continued cooldown.

3/4.7.1.3 CONDENSATE STORAGE TANK The OPERABILITY of the condensate storage tank with the minimum water volume ensures that sufficient water is available for cooldown of 1 ') the Reactor Coolant System to less than 300*F in the event of a total

> loss of off-site power. The minimum water volume is sufficient to maintain the RCS at HOT STANDBY conditions for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with steam discharge to atmosphere. 4 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction w

[be enfzu.tal walu volume

/v.,j{ includa a" 'llpwa"N

-fu wa }v m + usa b /c dar h duel me n m /< ppe e/rw h w abm %k 6.4%, y/ur as alhwa m & uwM 6.,rdsw.

MILLSTONE - UNIT 2 8 3/4 7-2 0323 Amendment No. JE,.87 77, g g

PLANT SYSTEMS #E=^

IAEIt i

3/4.7.1.4 ACTIVITY (Continued) of 10 CFR Part 100 limits in the event of a steam line rupture. The dose calculations for an assumed steam line rupture include the effects of a coincident I.0 GPM primary to seconiuy tube leak in the steam generator of the affected steam line and a concurrent loss of offsite electrical power. These values are consistent with the assumptions used in the accident analyses. .

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES

- The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the-surveillance requirements are consistent with the assumptions used in the I accident analyses.

3/4.7.1.6 MAIN FEEDWATER ISOLATION COMP 0NENTS (MFICs1

~

Feedwater isolation response time ensures a rapid isolation of feed flow to the steam generators via the feedwater regulating valves, feedwater bypass valves, and as backup, feed pump discharge valves. The response time includes signal generation time and valve stroke. Feed line block valves also receive a feedwater isolation signal since the steam line break accident analysis credits them in prevention of feed line volume flashing in some cases. Since the block valves are not credited with isolation, they are not required to <

operate as fast as the isolation valves although equal response times for all l valves are specified. Feedwater pumps are assumed to trip tamediately with an I fI**** (Zwsu7 /3) l 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION l

The limitation on steam generator pressure and temperature ensures l that the pressure induced stresses in the steam generators do not exceed {

the maximum allowable fr.acture toughness stress limits. The limitations

. of 70*F and 200-psig are based on a steam generator RT m of 50*F l j

j and are sufficient to prevent brittle fracture.

{

3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM The OPERABILITY of the reactor building closed cooling water

system ensures that sufficient cooling capacity is available for continued operation of vital components and Engineered Safety Feature )

l i equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with

} the assumptions used in the accident analyses.

M. =ILLSTONE - UNIT 2 B 3/4 7 3 Amendment No. 77 gp l

o .

INSERT B - Paae B 3/4 7-3 3/4.7.1.7 ATMOSPHERIC STEAM DUMP VALVES The atmospheric steam dump valves (ASDVs) provide a method for maintaining the unit in HOT STANDBY, and to cool the unit to Shutdown Cooling (SDC) System entry conditions if heat removal by the condenser steam dump valves is not available.

The ASDVs are normally operated from the main control room. Local manual operation of the ASDVs is provided. The ASDVs are OPERABLE as long as the valves can be opened from the control room, or locally at the valvet.

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i Docket No. 50-336

! B16902 1

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Attachment 4 Millstone Nuclear Power Station, Unit No. 2 l

Proposed Revision to Technical Specifications Condensate Storage Tank and Atmospheric Steam Dump Valves Retyped Pages 1

J August 1998  !

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It!0fl LIMITING CONDITIONS FOR OPERATION AM SURVEILLANCE REQUIREMENTS SECTION PME 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE . . . . . . . . . . . . . . . . . . . . . 3/4 7-1 Safety Val ves . . . . . . . . . . . . . . . . . . . . .

3/4 7-1 l Auxiliary Feedwater Pumps . . . . . . . . . . . . . . . 3/4 7-4 Condensate Storage Tank . . . . . . . . . . . . . . . . 3/4 7-6 Activity . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-7 Main Steam Line Isolation Valves . . . . . . . . . . . 3/4 7-9 l Main Feedwater Isolation Components (MFICs) . . . . . . 3/4 7-9a Atmospheric Steam Dump Valves . . . . . . . . . . . . . 3/4 7-9c l l 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION . . . 3/4 7-10 3/4.7.3 REACTOR BUILDING CLOSED COOLING WATER SYSTEM . . . . . 3/4 7-11 3/4.7.4 SERVICE WATER SYSTEM . . . . . . . . . . . . . . . . . 3/4 7 - 12 1

3/4.7.5 F LOOD L EV E L . . . . . . . . . . . . . . . . . . . . . . 3/4 7 - 13 l 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION SYSTEM . . . . . . . 3/4 7-16 3/4.7.7 SEALED SOURCE CONTAMINATION . . . . . . . . . . . . . . 3/4 7-19 3/4.7.8 SNUB 8ERS . . . . . . . . . . . . . . . . . . . . . . . 3/ 4 7 - 21 3/4.7.9 DEL ETED . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7 - 3 3 3/4.7.10 DEL ETED . . . . . . . . . . . . . . . . . . . . . . . . 3/4 7-33 3/4.7.11 ULTIMATE HEAT SINK . . . . . . . . . . . . . . . . . . 3/ 4 7 - 3 4 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES . . . . . . . . . . . . . . . . . . . . . 3/4 8-1 Operating . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-1 Shutdown . . . . . . . . . . . . . . . . . . . . . . . 3/4 8-5 l 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS . . . . . . . . . . . 3/4 8-6 A.C. Distribution - Operating . . . . . . . . . . . . . 3/4 8-6 l A.C. Distribution - Shutdown . . . . . . . . . . . . . 3/4 8-7 D.C. Distribution - Operating . . . . . . . . . . . . . 3/4 8-8 D.C. Distribution - Shutdown . . . . . . . . . . . . . 3/4 8 - 10 D.C. Distribution (Turbine Battery) - Operating . . . . 3/4 8-11

( VIII MILLSTONE - UNIT 2 Amendment No. //, M , M. [ # ,

0370 [M,[f[,[h,[f[,

_ _ _ _ _ _ - _ - _ _ _ - - _ - _ _ _ _ _ . a

4 PLANT SYSTENS CONDENSATE STORAGE TANK LINITING CONDITION FOR OPERATION 3.7.1.3 The condensate storage tank shall be OPERABLE with a minimum contained volume of 165,000 gallons.

l APPLICABILITY: N00ES 1, 2 and 3.

ACTION:

With less than 165,000 gallons of water in the condensate storage tank, l within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

a. Restore the water volume to within the limit or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or
b. Demonstrate the OPERABILITY of the fire water system as a backup supply to the auxiliary feedwater pumps and restore the condensate storage tank water volume to within its limits within 7 days or be in HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SURVEILLANCE REQUIREMENTS

4. '/ .1. 3 The condensate storage tank shall be demonstrated OPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by verifying the water level.

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l NILLSTONE - UNIT 2 3/4 7-6 Amendment No.

0371

. 4 PLANT SYSTENS ATMOSPHERIC STEAN DUNP VALVES LINITING CONDITION FOR OPERATION 3.7.I.7 Each atmospheric steam dump valve shall be OPERABLE.

APPLICABILITY MODES I, 2, and 3.

ACTION:

a. With one atmospheric steam dump valve inoperable, restore the inoperable valve to OPERABLE status within 7 days or be in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
b. With more than one atmospheric steam dump valve inoperable, restore one inoperable valve to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SURVEILLANCE REQUIREMENTS 4.7.I.7 Verify one complete cycle of each atmospheric steam dump valve at least once per 18 months.

1 NILLSTONE - UNIT 2 3/4 7-9c Amendment No.

0372 I

F16NT SYSTit$

RACFC 3/4.7.1.2 AUXILIARY FEEDWATER PUMPS The OPERABILITY of the auxiliary feedwater pumps ensures that the Reactor Coolant System can be cooled down to less than 300*F from normal operating conditions in the event of a total loss of off-site power.

Any single motor driven or steam driven pump has the required capacity to provide sufficient feedwater flow to remove reactor decay heat and reduce the RCS temperature to 300*F where the shutdown cooling system may be placed into operation for continued cooldown.

3/4.7.1.3 CONDENSATE STORAGE TANK l The OPERABILITY of the condensate storage tank with the minimum wator volume ensures that sufficient water is available for cooldown of the Reactor Coolant System to less than 300*F in the event of a total loss of off-site power. The minimum water volume is sufficient to l maintain the RCS at HOT STANDBY conditions for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> with steam i discharge to atmosphere. The contained water volume limit includes an allowance for water not usable due to discharge nozzle pipe elevation above j tank bottom, plus an allowance for vortex formation. 4 3/4.7.1.4 ACTIVITY The limitations on secondary system specific activity ensure that the resultant off-site radiation dose will be limited to a small fraction l

f l

MILLSTONE - UNIT 2 8 3/4 7-2 Amendment No. EJ, EJ, E/, JJJ, 0374 l

'~ o PLANT SYSTEMS BASES 3/4.7.1.4 ACTIVITY (Continued) of 10 CFR Part 100 limits in the event of a steam line rupture. The dose calculations for an assumed steam line rupture include the effects of a coincident 1.0 GPM primary to secondary tube leak in the steam generator of the affected steam line and a concurrent loss of offsite electrical power. These values are consistent with the assumptions used in the accident analyses.

3/4.7.1.5 MAIN STEAM LINE ISOLATION VALVES The OPERABILITY of the main steam line isolation valves ensures that no more than one steam generator will blowdown in the event of a steam line rupture. This restriction is required to 1) minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and 2) limit the pressure rise within containment in the event the steam line rupture occurs within containment. The OPERABILITY of the main steam isolation valves within the closure times of the surveillance requirements are consistent with the assumptions used in th2 accident analyses.

3/4.7.1.6 MAIN FEEDWATER ISOLATION COMPONENTS (MFICs)

Feedwater isolation response time ensures a rapid isolation of feed flow to the steam generators via the feedwater regulating valves, feedwater bypass valves, and as backup, feed pump discharge valves. The response time includes signal generation time and valve stroke. Feed line block valves also receive a. feedwater isolation signal since the steam line break accident analysis credits them in prevention of feed line volume flashing in some cases. Since the block valves are not credited with isolation, they are not required to operate as fast as the isolation valves although equal response times for all valves are specified. Feedwater pumps are assumed to trip immediately with an MSI signal.

3/4.7.1.7 ATMOSPHERIC STEAM DUMP VALVES The atmospheric steam dump valves (ASDVs) provide a method for maintaining the unit in HOT STANDBY, and to cool the unit to Shutdown Cooling (SDC) System entry conditions if heat removal by the condenser steam dump valves is not available. The ASDVs are normally operated from the main control room. Local manual operation of the ASDVs is provided. The ASDVs l are OPERABLE as long as the valves can be opened from the control room, or l

locally at the valves.

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and temperature ensures that the pressure induced stresses in the steam generators do not exceed the maximum ~ allowable fracture toughness stress limits. The limitations of 70*F and 200-psig are based on a steam generator RTmn of 50*F and are sufficient to prevent brittle fracture.

MILLSTONE - UNIT 2 B 3/4 7-3 Amendment No. 77, Jpp, 0374

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PLANT SYSTENS M3fl 3/4.7,3 REACTOR BUILDING Cl&SfA COOLING WATER SYSTEM The OPERABILITY of the reactor building closed cooling water system ensures that sufficient cooling capacity is available for continued operation of vital components and Engineered Safety Feature equipment during normal and accident conditions. The redundant cooling capacity of this system, assuming a single failure, is consistent with the assumptions used in the accident analyses.

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{IglSTONE-UNIT 2 B 3/4 7-3a Amendment No. 77, Jpp,

Docket No. 50-336 B16902 Attachment 5 Millstone Nuclear Power Station, Unit No. 2 Proposed Revision to Technical Specifications Condensato Storage Tank and Atmospheric Steam Dump Valves NNECO Commitments August 1998

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U. S. Nucl=r R:gulatory Commission l

B16902/ Attachment 5/Page 1 Proposed Revision to Technical Specifications Condensate Storage Tank and Atmospheric Steam Dump Valves List of Regulatory Commitments 1

The following table identifies those actions committed to by NNECO in this document.

Please notify the Manager - Regulatory Compliance at Millstone Unit No. 2 of any quesdons regarding this document or any associated regulatory commitments.

Commitment Committed Date or Outage NONE N/A l

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