TXX-8924, Affirms & Certifies That Tech Specs Accurately Reflect as-built Plant & FSAR Per .Exceptions Listed, Including Accident Monitoring Instrumentation

Affirms & Certifies That Tech Specs Accurately Reflect as-built Plant & FSAR Per .Exceptions Listed, Including Accident Monitoring Instrumentation

ML20247G723
Person / Time
Site:	Comanche Peak
Issue date:	05/15/1989
From:	William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TXX-89243, NUDOCS 8905310052
Download: ML20247G723 (14)

Text

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Log # TXX-89243

..__ File # 10014 r C 916 7UELECTRlC Ref. # 10CFR50.36 May 15, 1989 W. J. Cahm becutive Vice Prendent U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 5UBJECT: LOMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NO. 50-445 TECHNICAL SPECIFICATION CERTIFICATION REF: 1) TV Electric letter (TXX-89169) from W. J. Cahill, Jr. to the NRC dated April 14, 1989.

2) TV Electric letter (TXX-89225) from W. J. Cahill, Jr. to the NRC dated May 2, 1989.

Gentlemen:

Reference 1 provided TV Electric's affirmation and certification regarding the adequacy and accuracy of the CPSES Unit 1 Technical Specifications with the following exceptions:

Plant Systems (Auxiliary Feedwater flow requirements / Condensate Storage Tank volume),

Accident Monitoring Instrumentation, Area Temperature Monitoring Our review of the above Technical Specifications is complete. Attached are additional corrections to the Final Draft Technical Specifications transmitted by your letter, dated March 17, 1989, which are required for the above specifications to adequately and accurately reflect the CPSES as-bui't design.

These corrections are in addition to the corrections transmitted by reference 1.

This letter affirms and certifies that to the best of my knowledge, with the corrections noted, the above listed Technical Specifications accurately reflect the as-built plant (as it will be upon completion of design modifications in progress) and the FSAR.

8905310052 890515 ADOCK 05000445 ofl PDR g PDC i l 400 North Olive Street LB81 Dallas, Texas 75201  !

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TXX-89243 May 15, 1989 Page 2 of 3 Should you require additional information or desire further discussions on the CPSES Unit 1 Technical Specifications, do not hesitate to contact me.

Si nc.erely ,

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William J. Cahill, Jr.

'* /4 JDS/vid Attachment c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3)

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.H TXX-89243-

-May 15,' 1989~

Page 3 of.3-STATE-OF TEXAS )- ,

.S.~ r . \\) .SS.

COUNTY OF BAL4A&)

I, W. J. Cahill, Jr.,'being duly sworn, subscribe to and say that I im'the Executive Vice President, Nuclear of TV Electric Company; that I have full authority to execute this oath; that I have read the foregoing Technical S>ecifications Certification Letter logged TXX-89243 and know the contents t1ereof; and that.to the best of my knowledge, information, and belief.the statements made-in it are true.

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.J.Cahill,pr.'

SUBSCRIBED AND SWORN to before me, a Notary Public, in and for the County and State above named, this ID% day of A ,, , 1989.

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LAttachment.td TXX-89243

. .May;15,-1989: <

Page 1 of 11-

.J Page: Descript:on

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3/4' 3-43 The Accident M aitori..g' Instrumentation.

Specification. ;- modified to reflect the addition - u of Reactor Ve el Water Level instruments and-changes to a' cady existi g required channels.

The ACTION 5.atements are organized in a tabular _

form >' ' .iuman factor concerns.

3/4 3-45 Table 3.3-6 has been corrected-to include all type.

. .A, category 1 accident monitoring instrumentation-plus the additional instrumentation' identified by the NRC in.the Final Draft Technical Specifications, except as corrected below.

Item #'s 2 & 3 --Increased the Minimum Channels Fiierable requirement to include insta' led Wide Range T (hot) and T (cold) Instrumentation. the 1/ loop requirement ensures single-failure criterion is met, per CPSES design. Redundancy for T(hot) and.T(cold) is met using diverse instrumentation-(i.e., Core Exit Temperature for T(hot) and Steam Generator Pressure for T(cold)). ,

The associated ACTION Statement considered the I availability cf the diverse instrumentation _in i establishing the time' required to restore '

OPERABILITY of the instrumentation. 1 Item #6 - This instrumentation has been modified i to meet the requirements of SER Section II.E.1.2, j Part 2, Clarification 2a, Page :'2-48. o

.i Item #7 - The Steam Generator Water Level (Narrow  ;

Range) Required Number of Channels has been )

increased to encompass redundancy for this instrumentation.

Item #9 - The Required Number of Channels for Core liTt Temperature has been modified to clarify the requirement to ensure single-failure criterion is q satisfied for Required Number of Channels.

Item #10 - The Containmen' .trea Radiation (High Range) instrumentation hN 'Jeen modified-to j clarify that the ACTION S .tement only applies to d o the Minimum Channels Operable requirement as written in the Standard Technical Specifications. 'l l

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? Attach'mentLto> TXX-89243

, . .May'15, 1989

. Page 2 of 11'  !

I Item #11 - The Reactor Vessel Water level (RVWL) has been' modified to define OPERABILITY for the U number of sentors required i'n a probe for the

! system to.be 0PERABLE. The ACTION Statement has been changed to the industry accepted ACTION 4 Statement for RVWL Systems identical to the CPSES RVWL System. This ACTION Statement allows the determination for the feasibility of performing the repair and if determined not feasible informing the NRC per Specification 6.9.2, Special-Report, outlining the event and actions to be taken.

Old Item #16 - The Containment Isolation Valve -

Position Instrumentation is being deleted based on two reasons. The first reasua is that this-rec uirement is covered by. Specification 3/4.6.3 anc, the definition of OPERABILITY. For the valve to be OPERABLE it must satisfy the requirements of ASME Section IX, i.e., Specification 4.0.5, which incluries the requirement that position indication be tested periodically per Section XI. .The testing .

methodology for stroke testing these valves is to time these valves using the position indication.

This'will identify problems with the position .

. indication so that they can be rectified. .The second reason for deletion is based on.the fact 4 that at CPSES the Containment Isolation Valve Status is a type C, category 2. variable. This.

designation is based on the fact that it is the ,

preferred backup monitoring indication for Containment Boundary Integrity. .The CIV Status is not one of the KEY variables used to determine Containment Integrity as described in FSAR, Section 7.5.

3/4 7-4 The required head for the auxiliary feedwater B 3/4 7-2 pump has been correlated, by calculation, to a testable configuration due to test line'  !

limitations. The resultant flow and differential I pressure are provided in the attached corrections.

3/4 7-5 ValidationoftheCondensateStorageTank(CST) l-B 3/4 '7-2 required volume has resulted in a revision to the; usable volume. The minimum required CST volume is that volume required to remove heat at hot standby-for four hours followed by a five hour cooldown to 3500 F as stated in the BASES. This usable volume is provided in the attached correction.

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Attachment to TXX-8.9243 a e 3 of ten

.. INSTRUMENTATION ACCIDENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The accident monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

, ACTION: g, g gu (n Ta to l e., S . 3 - 4:,

. With the number of OP RABLE accident monitoring instrumentation channels less than the Required Number of Channels shown in Table 3.3-6, restore the inoperable channel (s) to DPERABLE status within 7 days, or be in at least 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 />,

b. With the number of OPERABLE accident monitoring instrumentation channels less than the Minimum Channels OPERABLE requirements of Table 3.3-6, restore the inoperable channel (s) to OPERABLL status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in HOT SHUTDOWN within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

( c. With the number of OPERABLE channels for the containrr,st atmosphere-high range radiation monitor less than required by the .'nimum j Channels OPERABLE requirements, initiate an alternate met..od of monitoring the appropriate parameter, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and either restore the inoperable channel to OPERABLE status witnin 7 days or prepare and submit a Special Report to the Commission, pursuant to Specification 6.9.2, within 14 days that provides actions taken, l cause of the inoperability, and the plans and schedule for restoring the channe status.

b. E The provisions of Specification 3.0.4 are not applicable.

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COMANCHE PEAK - UNIT 1 3/4 3-43

- Attackment to VXX-e)M3 ~R e of INSTRUMENTATION o

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gs z s ACCIDENT MONITORING INSTRUMENTATION gfG m 1 -_

/ SURVEILLANCE REQUIREMENTS \

4.3.3.3 Each accident monitoring instrumentation channel shall be demonstrated OPERABLE:

a. At least once per 31 days by performance of a CHANNEL CHECK, and I k

b. At least once per 18 months by performance of a CHANNEL CALIBRATION *

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• Containment Arc.? Radiation (High Range) CHANNEL CALIBRATION may consist of an electronic calit) ration of the channel, not including the detector, for range decades above 10 R/h and a one point calibration check of the detector below 10 R/h with an installed or portable gamma source.

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COMANCHE PEAL'. - UNIT 1 3/4 3-44

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' Attachment to TXX-89243 L May 15, 1989

.Page 6 of 11'  ;

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l Table 3.3-6 (continued) l ACTTQ'N Statements .

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ACTION 29 - a. With the number of OPERABLE channels less than the l- Required Number of Channels, restore the inoperable channel (s) to OPERABLE status within 7 days, or be in at least 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 />.

b. With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirements, restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in at least 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 />.  !

ACTION 30 - With the number of OPERABLE channels less than the Minimum '

Channels OPERABLE requirement, ooerations may proceed provided one of the following conditions is satisfied:

a. For Th ot, the Core Exit Temperature  !

(Thermocouple) Required Number of Channels requirement is met and the inoperable channel is restored to OPERABLE status within 90 days, or be in at least HOT SHUTDOWN within the next 12 aours, or

b. For Tcold, the Main Steam Line Pressure (Steam Generator Pressure) Required Number of Channels requirement (for the steam generator associated with the loop of concern) is met and the inoperable channel is restored to OPERABLE status within 90 days, or be in at least HOT SHUIDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, or

c. The inoperable channel is restored to OPERABLE 3tatus within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in at least HOT S'IUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 31 - With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, initiate an alternate method of monitoring the appropriate )arameter within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and either restore the inoperaale channel to OPERABLE status within 7 days or prepare and submit a Special Report, pursuant to Specification 6.9.2, within 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring the channels to OPERABLE status.

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JAttachment to TXX-89243 <

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May 15e 19891 g

.Page' 7 of 11-1 Table 3.3-6 (continued)

ACTION Statements l l

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ACTION 32 - a- With the number of OPERABLE channels one less than l the Required Number of Channels requirement, i either restore the system to OPERABLE status within 7 days if repairs are feasible without shutting down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlinirg the action taken, and the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

.b With the number of OPERABLE Channels less than the Minimum Channels OPERABLE requirement, either rastore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, if the repairs are teasible without shutting down, or:

1. Initiate an alternate method of monitoring the reactor vessel inventory;  ;

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2. Prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and

3. Restore the system to OPERABLE status at the next scheduled refueling, i

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LAttachmentto.TXX-8'9243 g May 15,'1989 Page 8_of 11 k PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) _m

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TS I442- 89-019

2) Verihingthatthesteamturbine-dr e pump develo pressure of greater than or equal t psid at a ow of greater than or equal to 860 gpm whe hed ec e da y steam supply pressure is greater than 532 psig. The provisions of i

f. Specification 4.0.4 are not applicable for entry into MODE 3;

3) Verifying that each non-automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in its correct position; and

4) Verifying that each automatic valve in the flow path is in the fully open position whenever the Auxiliary Feedwater System is i in standby fo'r auxiliary feedwater automatic i.nitiation or when '

above 10% RATED THERMAL POWER. . .

b. At least once per 18 months during shutdown by:

1) Verifying that each automatic valve in the fl9w path actuates to its correct position upon receipt of an Auxiliary Feedwater Actuation test signal, and

2) Verifying that each auxiliary .feedwater pump starts as designed automatically upon receipt of an Auxiliary Feedwater Actuation test sirjnal. The provisions of Specification 4.0.4 are not applicable to the turbine driven auxiliary feedwater pump for entry into Mode 3.

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9 COMANCHE PEAK - UNIT 1 3/4 7-4

a men o TXX-89243

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- 1 PLANT SYSTEMS '

CONDENSATE STORAGE TANK U l

LIMITING CONDITION.iOR OPERATION 1

T5 j 3.7.1.3 The condensate tofa yrtank_. ST) shall be OPERABLE with an indicated 1 water level of at leas M-0?i APPLICABILITY: MODES 1, , .

ACTION:

With the CST inoparable, 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 CST to OPERABLE status 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 i the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, or b.

Demonstrate the OPERABILITY of the Station Service Water (SSW) system as a backup supply to the auxiliary feedwater pumps and restore the CST 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' hours.

SURVEILLANCE RE0UIREMENTS 4.7.1.3.1 The CST 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 indicated water volume is within its limits when the tank is the supply source for the auxiliary feedwater pumps.

4.7.1.3.2 The SSW system shall be demonstrated DPERABLE at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> whenever the SSW system is being used as an alternate supply source to the auxiliary feedwater pumps by verifying the SSW system operable and each motor operated valve between the SSW system and each operable auxiliary feed-water pump is operable.

s COMANCHE PEAK - UNIT 1 3/4 7-5

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NaTi5,~ 989 Page 10 of 11 h PLANT SYSTEMS BASES 3/4.7.1.2 AUXILIARY FEEDWATER SYSTEM The OPERABILITY of the Auxiliary Feedwater System ensures that the Reactor Coolant System can be cooled down to less than 350'F from normal operating conditions in the event of a total loss-of-offsite power.

Each electric motor-driven auxiliary feedwater pump is capable of deliver-ing a total feedwater flow of 430 gpm to two steam generators at a presture of 1221 psig to the entrance of the steam generators. The steam-driven auxiliary feedwater pump is . capable of delivering a total feedwater flow of 860 gpm to four steam generators at a pressure of 1221 psig to the entrance of the steam generators. This capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and reduce the Reactor Coolant System temp-erature to less than 350 F when the Residual Heat Removal System may be placed s into operation. -

The Auxiliary Feedwater System is capable of delivering a total feedwater flow of 430 gpm at a pressure of 1221 psig to the entrance of at least two steam generators while allowing for: (1) any possible spillage through the design worst case break of the main feedwater line; (2) the design worst case single failure; and (3) recirculation flow. This. capacity is sufficient to ensure that adequate feedwater flow is available to remove decay heat and - ,T5 reduce Reactor Coolant System temperature to less than 350 F oint g_ g ,

the Residual Heat Removal System may be placed in operation. INSN The auxiliary feedwater flow path is a passive flow path based on the fact that valva actuation is not required in order to supply flow to the steam 1 generators. The automatic valves tested in the flow path are the Feedwater

[ Split Flow Bypass which are required to be shut upon initiation of the Auxiliary Feedwater System to meet the requirements of the accident aralysis.

Both steam supplies for the turbine-driven auxiliary feedwater pump must be OPERABLE in order to meet the design bases for the complete range of accident analyses. The allowed outage time for one inoperable steam source in consistent with the lower probability of the worst case steam or feedwater line break accident.

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 to maintain the RCS at HOT STANDBY conditions for 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> with steam discharge to the atmosphere concurrent with total loss-of-offsite power or 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at HOT STANDBY followed by a cooldown to.350 F at a rate of 50 F/HR for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. The contained water volume limit includes an allowance for water not usable because of tank disc rge line loca-tion or other physical characteristics. The required indicAt includes U M ere nt meas esenta n ertainty, an unusable volume o it,-WJ ga Yons and a 89 - O d L

a ble require 4 v lume "4 o15ac~co271,3 5 g 11ons. apooJ

1. UR_G-0737,NI. tem _M. . 1 requires a backup source to the4STAhich is the tBE5StationServiceWaterSystem,whichcanbemanuallyaligned,ifrequired in lieu of CST minimum water volume.

COMANCHE PEAK - UNIT 1 B 3/4 7-2 i

-Attachment to TXX-89243 May 15, 1989

..Page '11 of 11.

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Insert p. B 3/4 7-2 i The test flow for the steam-driven auxiliary feedwater pump at a pressure of greater than or equal to 1442 psid ensures this capability.

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