ML20203J609

Forwards Rev 26 to Technical Requirements Manual, for Cpses.Detailed Description of Changes,Encl

ML20203J609
Person / Time
Site:	Comanche Peak
Issue date:	02/26/1998
From:	Terry C, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20203J613	List: ML20203J615 TXX-9802, Forwards Rev 26 to Technical Requirements Manual, for Cpses.Detailed Description of Changes,Encl
References
TXX-98022, NUDOCS 9803040211
Download: ML20203J609 (5)

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E """l: Lo # TXX 98022 l C. F1 e # 10010 C C 916 (TRM)

MlELECTRIC Ref # 10CFR50.36 c, % % February 26, 1998 senior we rmu no

& PrincipelNuclear Officer U. S, Nuclear Regulatory Ccomission ,

Attn: Document Centrol Room Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) u DOCKET NOS. 50 445 Al;D 50 446 TRANSHITTAL 0F TECHNICAL REQUIREMENTS MANUAL (TRM)

REVISION 26 TU Electric herewith submits Revision 26 (enclosed) of the CPSES Technical Requirements Manual (TRM). Enclosed is the following document:

. Technical Requirements Manual 1 signed original Revision 26 and 10 copies The Attachment contains a description of the changes. As has been the TU Electric practice in the past several TRM revisions, all changes described in the Attachment have been evaluated for relative significance (i.e., the group number 1, 2, 3, or 4 corresponds to each change justification as discussed in TV Electric letter TXX 88467 dated June 1,1988). In addition, '

all changes applicable to CPSES Units 1 and 2 have been reviewed under the TV Electric 10CFR50.59 process and found not to include any "unreviewed safety questions *.

TRH Revision 26, dated February 24, 1998, became effective at 11:01 PM CST on February 24, 1998.

This communication contains no new licensing basis commitments regarding CPSES Units 1 and 2.

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TXX 98022 Page 2 of 2 If you should have any questions, please contact Carl B. Corbin at -

(254) 897 012;.

Sincerely.

Vi I

C. L. Terry

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By:

. Walker Roger Regula V" tory Affairs Manager CBC/cbc Attachment Enclosure cc: Mr. E. W. Herslhoff, Region IV Hr. J. I. Tapia, Region IV Hr. T. J. Polich. NRR Resident Inspector, CPSES h _ - _ _ _ _ _ _ _ - _ _ _ _ _ . _ _ _ _ _

Attachment to TXX.98022 4

4 CPSES - TEClINICAL RIIQUIREMENTS MANUAL REVISION . 26 DI: Tall 1D Di'.SCRipilON Prefit page Page I laulmendsd) ihWP DnEdclim 12 2 Change the response time for item 8, "Oscrpower N.16", from Ic>n than or equal to 7 seconds to less than or equal to 2 seconds. Also for item 8 delete the reference to the following note " Response tirne include . the thermal well response time."

Clarification 1hc temponse times for the reactor (rip functions are defined as the time from when the monitored parameter exceds its setpoint until the RCCAs are free to fall. Within this context, RTDs should be included only when they provide input to the utpoint, as for the 01N.16 trip fbnction, llecause the OpN.16 setpoint is a constant value, there is no need for the RTD respotise time allowance llence, only the ciectronic response time allowance assumed in the accident analysis (2.0 reconds) should be included in this table.1his revision makes the TpM table consistent with I'SAR Table 15.0.4 for this ihnetion.

1he N.16 power signal, which is compared against the overpower and overtemperature reactor trip netpoints, is nonnallied daily, if necessary, to the plant calorimetric measurement.1his power signal contains a temperature-compensation term. During steady. state operations, any deviations caused by a faulted temperature compensation would be normatlied out. The input to the compensation tenn, from RTDs hicattd in cach of the reactor coolant cold legs, is the same input as is used in the overtemperature N.16 reactor trip function.1he response time associated with the RTD is included in the measurement of the response time of tbc overtemperature N.16 reactor trip function.

During any power excur 5ns, if the rete of power increase is rapid relative to the loop transit time of approximately 10 seconds, any required reactor trips will be initiated by t.ic high neutron flux or overpower N-16 trip functions.

Under these conditions, theic would not be any significant change in the reactor coolant temperature as measured in the cold legs. If the rate of power excursion is slow relative to the loop transit time (-10 sec), the reactor coolant cold leg temperatures will begin to increase, and a reactor trip is expected to be initiated by the overtemperature reactor trip function.

In summary, any reasouable deviation in the response charseteristics of the RTD would net alTect the capability of the overpower N.16 reactor trip function and would be detected during response time surveillances of the overtemperature N-16 reactor trip function.

Change Request Number TR 5 . 1 Related SER 153.2 SSI:R SI:R/SSI:R impact N m

Attachment to TXX 98032 CPSES - TECIINICAL REQUIREMENTS MANUAL RI VISION . 26 DETAILED DESCRIPilON Prefix Page Page 2 f as amertdtd) Onnta Description 2 12 2 l'or valve llV 2452 2. under the column "Eine or Service." *#4" is added to designate the steam line. This was a typo, llV 24521 and ilV.24$2 2 the steam admission valves to the turbine driven auxiliary feedwater pump, are being swnpped with respect to which valve is associated with each steam line for tr;in considerations. This change w!!!

result in the valves t eing placed on different steam lines and thus different containment penetrations.

Note 9 is aJded for theae valves to explain when this change becomes cfTective. Note 9 states, " Valves llV.24521 and ilV 2452 2 are being swapped with respect to which valve is associated with each steam line. Valve llV.2452 1 is being changed from steam line # 1 to steam line # 4; and valve llV 2452 2 is being changed from steam line # 4 to steam line # l. This change (design modification 97-013) was implemented for Unit 2 in the third refueling outage for Unit 2. For Unit I, the change will be implemented in the sixth refuelmg outage ihr Unit I and is eITeetive following operations acceptance of design modification 97-015."

Revision 1his change is part of the corrective action prescribed to the condition reported in I.ER l 97 001-00. Th( condition reported in the Ll?R involved the postulated scenario of a feed line break occurring to an "A" Train Steam Generator (SO) coincident with the single active failure of the *ll" Train Solid Statc Protection System (SSPS) and was considered outside of the CPSES design basis. The modification was required to restore the design basis for operation of CPSES.

Change Request Number TR 6 . I Related SER : 6.2.4 SSER :

SER/SSER impact N 2- 2$ 4 Corrects the incorrect reference to technical specification in Note 5 of Table 2.1.1. " Containment Isolation Valves." The Technical Specification reference is changed from "4.6.1.3b" to "4.6.1.3a" Editorial Technical Specification Amendment 51/37 revised the Appendix J requirements for tne airlock.1his editorial change makes the TRM consistent with the primaty requirements in the Technical Specification.

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Attghment to TXX-98022 CPSES - TECllNICAL REQUIREMENTS MANUAL RI' VISION - 26 DI:TAILI:D DI:SCRIPilON Preibt Page Page 3 (ALWiltndnD Grwp Unstiplieu Change Request Number TR 1 . I j Related SI:R : 6.2.4 SSI:R .

SI:R/SSCR impact N 2-26 2 Adds Note 9 for valves llV 24521 and llV 24$2 2. Note 9 states," Valves j  !!V 24$21 and ilV-2452 2 are being swapped with respect to which valve is associated with each steam line. Valve llV 2452 1 is being changed from 2

steam line # 1 to steam line # 4; and valve llV 2452 2 is being changed from steam line # 4 to stearn line # l. This change (design modific.ition 97 013) was implemented for Unit 2 in the third refueling outage for Unit 2. l'or Unit 1, the change will be implemented in the shtth refueling outage for Unit I and is eITective following operations acceptance of design m <lification 97-Ol$."

Revision 1his change is part of the corrective action prescribed to the condition reported in 1.1:R 197-00100.1he condition reported in the L.l:R involved the postulated scenario of a feed line break occurring to an "A" Train Steam Generator (SG) coincident with the single active f ailure of the "11" Train Solid State Protection System (SSPS) and was considered outside of the CPSI:S design basis. 'the modification was required to restore the design basis for operation of CPSI:S.

Change Request Number TR 6 . 2 Related SI:R , SSI:R SI:R/SSI R impact N ,

4- 6 4 Corrects the a typo in Section 3.2 of Table 4.1.la " Unit 1. Containment Penetration Conductor Overcurrent Protective Devices " Column heading l "MCC 11:1112" is changed to "MCC 11:112 2"

(. 1:ditorial 1:ditorial change. As depicted directly above in Section 3.2, it should be j 11:112-2. This typo occured when this Section was reissued in TRM Re: vision 20.

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j Change Request Number TR -97 10 . 1 I Related SI:R: SSI:R +

SI:R/SSI R Impact N e

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