ML20205Q796

From kanterella
Jump to navigation Jump to search

Forwards Documentation from Preliminary Discussions with Licensee on Proposed Changes to Atmospheric Steam Relief Valve Tss.Licensee Subsequently Made Formal Application on 990322 (Accession Number 9903300195)
ML20205Q796
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 04/15/1999
From: Alexion T
NRC (Affiliation Not Assigned)
To:
NRC (Affiliation Not Assigned)
References
TAC-MA5078, TAC-MA5079, NUDOCS 9904220070
Download: ML20205Q796 (25)
v • d • e


Text

.. *.

MEMORANDUM TO: File April 15, 1999 FROM: Thomas W. Alexion, Project Manager, Section 1 ORIG SIGNED BY:

Project Directorate IV & Decommissioning Division of Licensing Project Management

SUBJECT:

PRELIMINARY DISCUSSIONS WITH LICENSEE ON PROPOSED CHANGES TO ATMOSPHERIC STEAM RELIEF VALVE TECHNICAL SPECIFICATIONS, SOUTH TEXAS PROJECT, UNITS 1 AND 2 (TAC NOS. MA5078 AND MA5079)

The NRC staff had several conference calls with the licensee (STP Nuclear Operating Company) to discuss the licensee's desire to propose changes to Technical Specification 3.7.1.6 (Atmospheric Steam Relief Valves). The licensee provided the information in the j attachment to facilitate the conference calls. The purpose of this memorandum is to place the attachment in the Public Document Room.

The licensee subsequently made a formal application to the NRC on March 22,1999 (ACN 9903300195).

Docket Nos. 50-498 and 50-499

Attachment:

As stated 1

l DISTRIBUTION:

Docket Files (50-498 and 50-499)

PUBLIC I

DOCUMENT NAME: 1:\STPFINAL\MEMA5078.WPD To recebe a copy of the document, bdcate e the bon C= Copy w/o attachment / enclosure E Copy with attachment / enclosure N = No copy OFFICE PM/PDIV-1 aE LA/PDIV-1 E SC/PDIV-1 A ,

NAME TAlex CJamerson k RGramm h / D\

DATE Ifh /99 i/ li /99 Y ([ /99 OFFICIAL RECORD COPY 3C)O TJ'*i@85 kJ8 P

sk m fuq g *a UNITED STATES

  • } NUCLEAR REGULATORY COMMISSION 2 WASHINGTON, D.C. 30006 4001

'+,*****,o April 15,1999 MEMORANDUM TO: File FROM: homas W. Alexion, Project Manager, Section 1 Project Directorate IV & Decommissioning Division of Licensing Project Management

SUBJECT:

PRELIMINARY DISCUSSIONS WITH LICENSEE ON PROPOSED CHANGEL TO ATMOSPHERIC STEAM RELIEF VALVE TECHNICAL SPECIFICATIONS, SOUTH TEXAS PROJECT, UNITS 1 AND 2 (TAC NOS. MA5078 AND MA5079)

The NRC staff had several conference ca'Is with the licensee (STP Nuclear Operating Company) to discuss the licensee's desire to propose changes to Technical Specification 3.7.1.6 (Atmospheric Steam Relief Valves). The licensee provided the information in the attachment to facilitate the conference calls. The purpose of this memorandum is to place the attachment in the Public Document Room.

The licensee subsequently made a formal application to the NRC on March 22,1999 (ACN 9903300195).

Docket Nos. 50-498 and 50-499

Attachment:

As stated

  • MAR-03-1999 14:27 NUCLEAR LICENSING 512 972 8290 P.02/11 1

.. .. l i

M \

LSMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION FAG.E i

Meteorological Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-68 3/4 3-59 TABLE 3.34 METEOROLOGICAL MONITORING INSTRUMENTATIGN . . . . . . '

TABLE 4.3 5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILI.ANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . 3/4340 Remote Shutdown System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-61 TABLE 3.3-9 REMOTE SHUTDOWN SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4342 TABLE 4.34 REMOfE SHUTDOWN MONITORING INSTRUMENTATION SURVEILI.ANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . 3/4346

- Accident Monitoring Instmmentation . . . . . . . . . . . . . . . . . . . . . . . . . 3/4347 TABLE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION . . . . . . . . . . . .

3/4348 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVElu.ANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . 3/4373

~

Chemical DetecGon Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-75 TABLE 3.3-11 (This table number is not used) . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4377 Radioactive Liquid Effluent Monitor Instumentation DELETED TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION DELETED TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DELETED Explosive Gas MonitorRn9 Instrumentation . . . . . . . . . . . . . . . . . . . 3/4 3-79 TABLE 3.3-13 EXPLOStVE GAS MONITORING INSTRUMENTATION . . . . . . . 3/4340 TABLE 4.3-9 EXPLOSIVE GAS MONITbRING INSTRUMENTATION SURVEILI.ANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . 3/4342 3/4.3.4(ghls specification number is not use[  !

hN W V .

vl Unit 1 - Amendment No. 47;99.10'1 SOUTH TEXAS- UNITS 1 & 2 - Unit 2- Amendment No. 06;es,88 ATTACHMENT

_ _ _ ~ . _ . _ . . _ . . . . . _ _

I r1AR-03-8999 a4:27 NUCLEAR LICENSING 512 972 8299 P.03/18 Proposed Insert to index Page vi, Section 3/4.3.4 l

' Insert 1 ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION.. 3/4 3-85 TABLE 3.3-14 ATMOSPHERIC STEAM RELIEF VALVE INSTRUM ENTATION. . .. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3.4 3-86 I

i

  • MAR-03-8999 14:27 NUCLEAR LICENS!tG 582 972 8298 P.04/18 INSTRUMENTATION 3/4.3.4 ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION:

3.3.4.1 The atmospheric steam relief valve instrumentation shown in Table 3.3-14 shall be OPERABLE.

APPLICABILITY: As shown in Table 3.3-14 ACTION: As shown in Table 3.3-14 SURVEILLANCE REQUIREMENTS:

4.3.4.1 Perform a CHANNEL CALIBRATION on each PORV automatic actuation channel at a setpoint of 1225 psig at least once every 18 months.

SOUTH TEXAS - UNITS 1 &2 3/4 3-85 l

E

. j - ' g gg

. r &$_ b $ 88 '. b$

N _

O

! 1 2 T

C A

E L

N O

BS *4 " _

AE 3 2, I

T CD I "1 A LO 2

_ T PM 1

. N P E A M

U R

T S

N SE

. I LL MEB

_ E 4 V UNA 2 2 MNR 1

L A

N HPAE I

3 V I 3 F E

MCO E l L l B E A R T

M A

E S

_ T L S E C

O.N I

_ R NN A 4 4 E

LH H A P T C S OF

. O TO M

- T A

l a

_ m r

o n 'g a sp i

T h5 t

_ I ni2 o

. N n iw2 t

U ol s als1 L ie t an t ues A c nf no N tun a at O c aha chn alco i i I c t T al l p

C u o r mot ra N nt ot ns U a no t uofi t F Mc Acl i*

' MAR-03-8999 14:27 NJCLEAR LICENSING 512 972 8298 P.06/a1 TABLE 3.3-14 (Continued)

TABLE NOTATIONS

  1. Automatic setpoint may be increased above 1225 psig in response to a steam generator tube leak
    1. Atmospheric relief valve (s) may be in manual operation if relieving sufficient energy to maintain the secondary side pressure at or below an indicated steam generator pressure of 1225 psig.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels less than the total number of channels requirement, declare the affected valve (s) inoperable and apply Technical Specification 3.7.1.6.

ACTION 2 - a. With the number of OPERABLE channels one less than the total number of channels requirement, restore the inoperable channel to OPERABLE status within 7 days; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With the number of OPERABLE channels two less than the total number of channels requirement, restore at least three channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

SOUTH TEXAS- UNITS 1 &2 3/4 3-87

  • MAR-03-1999 14:27 NUCLEAR LICENSING 512 972 8298 P.07/11 )

PpNTSYSTEMS 1

ATMCSPHERIC STEAM RELIEF VALVES l g TING CONDITION FOR OPERATION V

3.7.1 6 least four atmospheric steam relief valves (and associated manua]J (co'iETc hall be OPERABLE.

APPLICHILITY: MODES 1, 2, 3, and 4.*

ACTION:

a. With one less than the required atmospheric steam relief valves OPERABLE, rtstore the required atmospheric steam relief valves to OPERABLE status within 7 days; or be in at least HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and iri HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and place the required RCS/

RHR loops in operation for decay heat removal.

b. Eth two less than the required atmospheric relief valves OPERABLE, re-store at least three atmospheric relief valves to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and place the required RCS/RHR loops in operation for decay heat removal.

SURVEILLANCE REOUIREMENTS l

. __ v 4.7.1.6 Each atmospheric relief valve [and associated manual contro13shall je_

demonstrated OPERABLE orior to startup Toilowing any refuenna snutdown err COLD SHUTDOWN of 30 days or longe:T by verifying that all valves will open and l close f,ully by operations ofpmanual controls. S&s,% o ]

%r bbw3 a. 3 <=La 3 %y C

l l

SOUTH TEXAS - UNITS 1 & 2 3/4 7-10 Unit 1 - Amendme.it No. 4 1

1

INSTRUMENTATI'6N j BASES i l

3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION (Continued) quadrant. The unit specific response to lie'm II.F.2 of NUREG 0737 further discusses the core exit thermocouples. Two sets of two'thermocouples ensure a single failure will not disable the ability to determine the radial temperature gradient. The subcooling margin monitor requirements are not affected by allowing 2 thermocouples/ channel / quadrant as long as each channel has at least four operable thermocouples in any quadrant (e.g., A Train has four operable thermooouples in one of the quadrants, and C Train has four operable thermocouples i in the same quadrant or any other quadrant.). This preserves the ability to withstand a single failure.

3/4.3.3.7 (Not Used) 3/4.3.3.8 (Not Used) 3/4.3.3.9 (Not Used) 3/4.3.3.10 DELETED 3/4.3.3.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mixtures in the GASEOUS WASTE PROCESSING SYSTEM.

3/4.3.4 hot Used[

(\MSMT ~1]

SOUTH TEXAS-UNITS 1 & 2 B 3/4 3-6 Unit 1 - Amerndment No,47;96;f7,101 Unit 2- Amendment No.96:65:66,88

MAR-03-1999 84:28 NL;0 LEAR LICENSING 512 972 8290 P.09/11

.' \

1 Proposed Insert to Technical Specification Bases Page 3/4 3-6, Section 3/4.3.4, insert 2 ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION The atmospheric steam relief valves must be OPERABLE in manualin Modes 1, 2,3, and 4 (Mode 4 when the steam generator is required for decay heat removal) to allow operator action needed for decay heat removal and safe

! cooldown in accordance with Branch Technical Position RSB 5-1.

l l

The atmospheric steam relief valves must be OPERABLE in automatic with an indicated setpoint of 1225 psig in Modes 1 and 2 because the safety analysis assumes automatic operation of the atmospheric steam relief valves with an indicated setpoint of 1225 psig with uncertainties for mitigation of the small break LOCA. During a steam generator tube leak, the automatic setpoint may be raised above 1225 psig to reduce off-site dose release. The atmospheric relief valves may be operated in manual in Modes 1 and 2 to provide a load on the plant provided they are relieving sufficient energy to maintain the secondary side pressure at or below an indicated steam generator pressure of 1225 psig.

The uncertainties in the safety analysis assume a channel calibration on each atmospheric steam relief valve automatic actuation channel to include verification of automatic actuation at the 1225 psig setpoint every 18 months.

MAR-03-1999 14:28 NUCLEAR L1 CENSING 512 972 8298 P.10/11 I PLANT SYSTEMS BASES 3/4.7.1.6 ATMOSPHERIC STEAM RELIEF VALVES The atmospheric steam relief valves are required for decay heat removal and safe cooldown in accordance with Branch Technical Position RSB 5-1. In the safety analyses, operation of the atmospheric steam relief valves is assumed in accident analyses for mitigation of small break LOCA, feedwater line break, loss of nonnal feedwater and loss-of-offsite power.

m o et 3 3 /4. 7.1.7 FEE 0_ WATER _ ISOLATION VALVES The OPERABILITY of the feedwater isolation valves ensures that no more than one steam generator will blow down in the event of a steam line or feedwater line rupture. The operability of the Feedwater Isolation valves i will minimize the positive reactivity effects of the Reactor Coolant System '

cooldown associated with the blowdown, and limit the pressure r.ise within containment. The OPERABILITY of the feedwater isolation valves within the closure times of the Surveillance Requirements are consistent with the l assumptions used in the safety analysis. -

l 3/4.7.2 STEAM CENERATOR 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 RT , of 10*F and are sufficient to prevent brittle fracture.

3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related 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 safety analyses.

3/4.7.4 ESSENTIAL COOLING WATER SYSTEM The OPERABILITY of the Essential Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety-related 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 safety analyses.

When a r,isk-important system or component (for example Essential Cooling Water) is take'n out of service, it is important to assure that the im' pact on plant risk of this and other equipment simaltaneously taken out of service can be assessed. The Configuration Risk Management Program evaluates the impact SOUTH TEXAS - UNITS 1 & 2 B 3/4 7-3 Unit 1 - Amendment No. 49,85

' Unit 2 - Amendment No. 9,72 l

' MAR-03-1999 14:20 NUCLEAR LICENSING 512 972 8290 P.11/11 Proposed Insert to Technical Specification Bases Page B 3/4 7-3, Section 3/4.7.1.6, Atmospheric Steam Relief Valves insen 3 The verification that all atmospheric steam relief valves will open and close fully prior to startup following a COLD SHUTDOWN of 30 days or longer or following any refueling shutdown allows for operations using either manual or automatic controls.

TOTAL P.11

I

, MAR-85-1999 09:42 NUCLEAR LICENSING 512 972 8298 P.02/a4 NOC-AE-000462 Attachment 5 Page 2 of 14 l

l PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS l The Technical Specification and Technical Specification Bases pages listed below are l proposed as new pages or as marked-up pages to identify the proposed changes associated with this submittal and are enclosed in this attachment. l Eags- ,

Marked up index page vi '

Marked upindex page xiii New page 3/4 3-85 New page 3/4 3-86 New page 3/4 3-87 l

Marked up page 3/4 7-10 l Marked up page B 3/4 3-6 l Marked up page B 3/4 7-3 1

i l

l

, t1AR-15-8999 09:42 NUCLEAR LICENSING 512 972 8298 P.03/14 INDEX

' LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION RAGE Meteorological Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-68 TABLE 3.3 8 METEOROLOGICAL MONITORING INSTRUMENTATIGN . . . . . . 3/4359 TABLE 4.3-5 METEOROLOGICALMONITORINGINSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . 3/4360 Remote Shutdown System . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4341 TABLE 3.S 9 REMOTE SHUTDOWN SYSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-62 TABLE 4.3 6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . s . . . . . . . . . . . . . . . . . . . . 3/4346 Accident Monitoring instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . 3/4347 TABLE 3.310 ACCIDENT MONITORING INSTRUMENTATION . . . . . . . . . . . . 3/4368 TABLE 4.3-7 ACCIDENTMONITORINGINSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-73 Chemical Detection Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 3-75 TABLE 3.311 (This table number is not used) . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4377 Radioactive Uquid Effluent Monitor instumentation DELETED TABLE 3.3-12 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION DELETED TABLE 4.3-8 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS DELETED Explosive Gas MonitorRn9 Instrumentation . . . . . . . . . . . . . . . . . . . 3/4379 TABLE 3.3-13 EXPLOSIVE GAS MONITORING INSTRUMENTA110N . . . . . . . 3/4380 i TABLE 4.3-9 EXPLOSIVE GAS MONITbRING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . 3/4382 3/4.3.4 (This specification number is not used) l

. N 5t.*~T ,

SOUTH TEXAS- UNITS 1 & 2 vi Unit 1 - Amendment No. 47;99.10i

- Unit 2- Amendment No. 96;es,88

  • e-Pv* **m*. .,-no,, %. a,e . - ~,

, MAR-15-1999 09:42 NUCLEAR L!CENS1NG 512 972 8290 P.04/14 Proposed insert to index Page vi i

l Insert 1 3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE INSTRUM ENTATION.......... .. . . .. . . .. . .. . . .. .. . . . . . . . . ... . . .. . . .. 3/4 3-85 TABLE 3.3-14 ATMOSPHERIC STEAM RELIEF VALVE i IN STRU M ENTATION..... .... ...... ... . . . .. . .. . . . . .. . . . . . . . . . . .. . . . 3/4 3-86 I

i I

1.

, r1AR-15-1999 09:42 NUCLEAR LICENSING 582 972 8290 P.05/14 l INDEX ,

i l

e-BASES EAG.E SECTION B 3/4 0-1 3/4.0 APPUCABitJ1Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4.1 REACTIVITYCONTROLSYSTEMS B 3/41-1 3/4.1.1 BORATION CONTROL . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/41-2 3/4.1.2 BORAT10N SYSTEMS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/41-3 3/4.1.3 MOVABLE CONTROL ASSEMBLIES . . . . . . . . . . . . . . . . . . . . . . . . . . . i B 3/4 2-1 j 3/4.2 POWER DISTRIBUTION LIMITS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/4 2 1 1 3/4.2.1 AXtA1. M.UX DFFERENCE . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

j 3/4.2.2 and 3/4.2.3 HEAT FLUX HOT CHANNEL FACTOR and B 3/4 2-2 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR . . . . . . . . . . . .  ;

RGURE B 3/4.2-1 TYPICALINDICATED AX1AL FLUX DIFFERENCE,8VERSUS 3/4 2-3 THERMAL POWER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/42 5 3/4.2.4 QUADRANT PCIWER TILT RATIO . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/4 2 5 3/4.2.5 DNB PARAMETERS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

l 3/4.8 INSTRUMENTA110N 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM and ENGINEERED SAFETY B3/43-1 FEATURES ACTUATION SYSTEM INSTRUMENTATION . . . . . . . . . .

B 3/4 3-3 3/4.3.3 MONITORING INST RUMENTATION . . . . . . . . . . . . . . . . . . . . . . . . . . .

l 3/4.3.4 (This specification number is not used)

({mco.T ":V 3/4.4 REACTOR COOtANT SYSTEM B 3/4 4-1 3/4.4.1 REACTOR COOLANT LOOPS AND COOLANT CIRCULATION . . . . . .

B 3/4 4 1 3/4A.2 SAFETY VALVES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

8 3/4 4-2 3/4.4.3 P RESSURIZER . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/44-2 3/4.4.4 RELIEF VALVES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/4 4 2 3/4.4.5 STEAM GENERATORS . . . . . . . . . . '. . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/4 d 4 3/4.4.7 CHEMISTRY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

B 3/4.4 6 3/4.4.8 St ECIFIC ACTIVITY . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

xiil Unit 1 - Amendment No.101 SOUTH TEXAS-UNITS 1 & 2 Unit 2. Amendment No. 88

MAR-15-1999 09:42 NUCLEAR LICENSING 512 972 8298 P.06/84 )

Proposed insert to index Page xiii insett2 3/4/3.5 ATMOSPHERIC STEAM RFT M VALVE INSTRUMENTATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .B 3/4 3 -6 l

l

[ ,

MAR-15-1999 09:42. NUCLEAR L1 CENSING 512 972 B290 P.07/84 t

1 INSTRUMENTATION {

l 3/4.3.5 ATMOSPHERIC STEAM REllr!F VALVE INSTRUMENTATION LIMITING CONDITION FOR OPERATION: .

3.3.5.1 The atmospheric steam relief valve instrumentation shown in Table 3.3-14 shall be OPERABLE.

l APPLICABILITY: As shown in Table 3.3-14 l

l ACTION: As shown in Table 3.3-14 l

SURVEILLANCE REQUIREMENTS:

4.3.5.1 Perform a CHANNEL CAllBRATION on each atmospheric steam relief valve automatic actuation channel at a setpoint of 1225 psig at least once every 18 months.

i SOUTH TEXAS- UNITS 1 &2 3/4 3-85 l l

l

. $ 8e mB ER@a O b 8m o8s

_ N O

I 1 2

_ T C

A

_ N O

I _

T E _

A L

T BS *4, N AE 3, .

E CD 2 8

2,

_ M I LO 1 U PM ,

_ R P 1

T A

- S _

N I

E

_ 6 4 V 8 L

1 A 3 3 V 4

/

3 F 3 E E I

L L _

B

- E .

A T R OSL N E ) )

M e e A DN v v E EN l a

l a

T RA 4v 4v S I UH / /

C Q C (1 1

(

EF

_ I R

E RO H

_ P S

O M

T 2 A 8 1

_ S T

I N

T n U I

N o -

_ U n ol s it als S L ie ue A c

an t

A an

_ t X

na N c un E t

a T O ahc i ch a c t

I T l H C al mor l

T uro U N nt n ot t n U a o uo O F Mc Ac S

, MAR-15-1999 09
43 NUCLEAR LICENSING 512 972 8298 P.09/84

! l TABLE 3.3-14 (Continued)

TABLE NOTATIONS When steam generators are being used for decay heat removal.

  1. Atmespheric steam relief valve (s) may be in manual operation to maintain secondary side pressure at or below an indicated steam generator pressure of 1225 psig.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels less than the required number of channels, declare the affected valve (s) inoperable and apply Technical Specification 3.7.1.6.

l ACTION 2 - s. With one less that the required number of OPERABLE i channels, restore the inoperable channel to OPERABLE status within 7 days; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

l

b. With two less than the required number of OPERABLE l channels, restore at least three channels to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

i SOUTH TEXAS - UNITS 1 &2 3/4 3-87 L

F MAR-15-1999 09:43 NUCLEAR LICENSING 512 972 8298 P.10/14 l' l

PLANT SYSTEMS ATMOSPHERIC STEAM RELIEF VALVES LIMITING CONDITION FOR OPERATION 9-3.7.1.6 4t,1 cast four atmospheric steam relief valves (and associated manuaD fontrols)shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3, and 4.*

ACTION:

a. With one less than the required atmospheric steam relief valves OPERABLE, restore the required atmospheric steam relief valves to OPERABLE status within 7 days; or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and place the required RCS/

RHR loops in operation for decay heat removal.

b. With two less than the required atmospheric relief v:1ves OPERABLE, re-store at least three atmospheric relief valves to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and place the required RCS/RHR loops in operation for decay. heat removal.

SURVF11 LANCE REQUIREMENTS 4.7.1.6 Each atmospheric relief valv$(iind associated manual contro 11 be

_ demonstrated OPERABLE prior to startup following anytrerueling shutdown orV I __ COLD SHUTDOWN of 30 days or longe:T by verifying that all valves will open and l

\ close f,ully by operatio@f manual (o.Jo mky up controls.

r habwq oc c.3 veMt.Mg sbOcw

50tJTH TEXAS - UNITS 1 & 2 3/4 7-10 Unit 1 - Amendment No. 4

MAR-15-1999 V):43 HUCLEAR LICENSING 512 972 8298 P.11/14 INSTRUMENTATI'dN BASES 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION (Continued) quadrant. The unit specific response to item II.F.2 of NUREG-0737 further discusses the core exit thermooouples. Two sets of two thermocouples ensure a single failure will not disable the ability to determine the radial temperature gradient. The subcooling margin monitor requirements are not affected by allowing 2 thermocouples/ channel / quadrant as long as each channel has at least four operable thermocouples in any quadrant (e.g., A Train has four operable thermooouples in one of the quadrants, s.nd C Train has four operable thermocouples in the same quadrant or any other quadrant.). This preserves the ability to withstand a single ,

l failure.

3/4.3.3.7 (Not Used)_

3/4.3.3.8 (Not Used) l 3/4.3.3.9 (Not Used) 3/4.3.3.10 DELETED 3/4.3.3.11 EXPLOSfVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gas mb(tures in the GASEOUS WASTE PROCESSING SYSTEM.

3/4.3.4 (Not Used) hWtlT .

O SOUTH TEXAS- UNITS 1 & 2 B 3/4 3-6 Unit 1 - Amendment No. 47,70,7,101 Unit 2 - Amendment No. 00,00,30,88

, MAR-15-1999 e9:43 NUCLEAR L1 CENSING 512 972 8298 P.12/14 l

Proposed insert to Technical Specification Bases Page 3/4 3-6, 1

I Insert 3 3/4.3.5 ATMOSPHERIC STEAM RELIEF VALVE INSTRUMENTATION The atmospheric steam relief valves must be OPERABLE in manualin Modes 1,2,3, and 4 (Mode 4 when the steam generator is required for decay heat removal) to allow operator action needed for decay heat removal and safe l cooldown in accordance with Branch Technical Position RSB 5-1.

1 The atmospheric steam relief valves must be OPERABLE in automatic with i an indicated setpoint of 1225 psig in Modes 1 and 2 because the safety analysis assumes automatic operation of the atmospheric steam relief valves with an indicated setpoint of 1225 psig with uncertainties for mitigation of the small break LOCA. In order to support startup and shutdown activities (including post-refueling low power physics testing), the atmospheric steam relief valves may be operated in manual in Mode 2 to maintain the secondary side pressure at j or below an indicated steam generator pressure of 1225 psig.

l The uncertainties in the safety analysis assume a channel calibration on each atmospheric steam relief valve automatic actuation channel, including verification of automatic actuation at the 1225 psig setpoint, every 18 months.

l

\

1 l

l l

l

, MAR-15-1999 09:43 NUCLEAR LICENSING 512 972 8298 P.13/14 l PLANT SYSTEMS I

BASES l

3 /4.7.1.6 ATMOSPHERIC STEAM RELIEF VALVES The atmospheric steam relief valves are required for decay heat removal and safe cooldown in accordance with Branch Technical Position RS8 5-1. In the safety analyses, operation of the atmospheric steam relief valves is  ;

assumed'in accident analyses for mitigation of small break LOCA, feedwater line break, loss of normal feedwater and loss-of-offsite power a )

3 /4.7_.1.7 FEEDWATER ISOLATION VALVES hMN N The OPERABILITY of the feedwater isolation valves ensures that no more than one steam generator will blow down in the event of a steam line or i feedwater line rupture. The operability of the Feedwater Isolation valves l will minimize the positive reactivity effects of the Reactor Coolant System cooldown associated with the blowdown, and limit the pressure r.ise within i I

containment. The OPERABILITY of the feedwater isolation valv'es within the closure times of the Surveillance Requirements are consistent with the assumptions used in the safety analysis. -

j 3 /4.7.2 STEAM GENERATOR FRESSURE/ TEMPERATURE LIMITATION j 1

The limitation on steam generator pressure and temperature ensures that the pressure-induced stresse in the steam generators do not exceed the maximum allowable fracture toaghness stress limits. The limitations of 70*F and 200 psig are based on a steam generator RT, of 10*F and are sufficient ,

to prevent brittle . fracture. l 3/4.7.3 COMPONENT COOLING WATER SYSTEM The OPERABILITY of the Component Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety- .

related 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 safety analyses. l J/4.7_._4__ ESSENTIAL COOLING WATER SYSTEM The OPERABILITY of the Essential Cooling Water System ensures that sufficient cooling capacity is available for continued operation of safety- i related equipment during normal and accident conditions. The redundant cooling cap.acity of this system, assuming a single failure, is consistent with the assumptions used in the safety analyses.

When a risk-important system or component (for example Essential Cooling Water) is tak'e'n out of service, it is important to assure that the im' pact on plant risk of this and other equipment simultaneously taken out of service can be assessed. The Configuration Risk Management Program evaluates the impact SOUTH TEXAS ' UNITS 1 & 2 B 3/4 7-3 Unit 1 - Amendment No. +9,85

' Unit 2 - Amendment No. 9,72

, MAR-15-8999 09:44 NUCLEAR LICENSING 512 972 8298 P.84/14

~

/

Proposed insert to Technical Specification Bases Page B 3/4 7-3, Section 3/4.7.1.6, Atmospheric Steam Relief Valves Insert 4 The atmospheric steam relief valves must be OPERABLE in manualin Modes 1, 2,3, and 4 (Mode 4 when the steam generator is required for decay heat removal) to allow operator action needed for decay heat rernoval and safe cooldown in accordance with Branch Technical Position RSB 5-1.

The atmospheric steam relief valves must be OPERABLE in automatic with an indicated setpoint of 1225 psig in Modes 1 and 2 because the safety analysis assumes automatic operation of the atmospheric steam relief valves with an indicated setpoint of 1225 psig with uncertainties for mitigation of the small break LOCA. In order to support startup and shutdown activities (including post refueling low power physics testing), the atmospheric steam relief valves may be operated in manual in Mode 2 to maintain the secondary side pressure at or below an indicated steam generator pressure of 1225 psig.

The verification that all atmospheric steam relief valves will open and close fully prior to startup following a COLD SHUTDOWN of 30 days or longer, or following any refueling shutdown, allows for operations using either manual or automatic controls.

TOTAL P.14

Retrieved from "https://kanterella.com/w/index.php?title=ML20205Q796&oldid=3326206"