ML20246B553
| ML20246B553 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/18/1989 |
| From: | William Cahill, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89567, NUDOCS 8908230393 | |
| Download: ML20246B553 (25) | |
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EE Log # TXX-89567 File'# 10010 p . .
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- nlELECTRIC "* # **C'"'****(
i August 18, 1989 Esecutwe Vice President U. S. Nuclear Regulatory Commission Attn: Document Control Desk-Washington, D. C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION-(CPSES)
' DOCKET NOS. 50-445 AND 50-446 ADVANCE FSAR SUBMITTAL ELECTRICAL ISOLATION OF NON-CLASS IE MOTOR CONTROL CENTER SPACE HEATERS Gentlemen:
This letter provides an advance copy of chan;es to be included in a future FSAR amendment-regarding electrical isolation of the non-Class 1E space heaters for Class 1E motor control centers (MCC). These changes are provided
.to trip the MCC space heater transformer supply breaker on receipt of an "S" (Safety Injection) signal. This will properly isolate the Class IE MCC's from the non-Class IE space heaters and meets the requirements of Regulatory Guide 1.75, Revision 1, as. discussed in FSAR Section 8.3. This is consistent with TXX-89428 of July 7, 1989, concerning SDAR CP-87-136.
In addition, this letter includes an advance copy of FSAR changes regarding
-design modifications of reset circuits of Engineered Safety Features (ESF).
The control circuit "S" contact is being removed to delete the "S" trip on the containment lighting transformers and vent control cooling unit cooler / chilled water M0V's cs.a corrective action per TXX-89488 dated July 26, 1989.
In order to facilitate NRC staff review of these changes, the enclosure is organized as follows:
I
- 1. Draft revised FSAR pages, with changed portions indicated by a bar j in the margin, as they are to appear in a future amendment >
(additional pages immediately preceding and/or following the revised pages are provided if needed to understand the change). A hand markup is provided for figure changes.
I
- 2. A line-by-line description / justification of each item revised.
- 3. A copy of related SER/SSER sections.
- 4. An index page containing the title of " bullets" which consolidates ,
and categorizes similar individual changes by subject and related q SER section. O l
l 8908230393 89031g PDR ADOCK 0500o445 a
pf 400 North Ohve Street LB 81 Dallas, Texas 75201 gf l
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- TXX 89567 August 18,1989
. Page 2 of 2
- 5. A discussion.of each " bullet" which includes:
The line-by-line description / justification for each item related to the " bullet" which has.been screened as a group 1
-or 2 item or a group 3 or 4 item which impacts-the existing SER/SSER's. (The discussion of these' groups is' contained in TU Electric letter.TXX-88467 dated June.1, 1988.)
The bold / overstrike version'of the revised FSAR pages referenced by the description / justification for each item identified above. The bold / overstrike version facilitates review of the revisions by highlighting each addition of
.new text 'in bold type font and overstriking with a slash
(/) the portion of the text that is deleted. A hand-markup is provided for figure changes.
1 TU Electric requests that the NRC perform an expedited review of the above FSAR changes.and inform us as to their acceptability.
If.you'have any questions regarding thir submittal please contact Joe Harnden at (214') 812-8226.
Sincerely, su L p k U>jh William J. Cahill, Jr.
by: c*,$2a b . k ,
Roger 1. Walker Manager, Nuclear Licensing WJH/vid Enclosure c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3) l 1
I l
s.
9, Enclosure to TXX-89567 August 18, 1989 Advance FSAR Change Regarding Electrical Isolation of Non-Class IE Hotor Control Center Space Heaters Item 1 Draft Revised FSAR Page pg. 2 thru 10 Item 2 Description / Justification for FSAR Change pg. 11 thru 12 Item 3 Related SER/SSER Pages pg. 13 thru 18 Item 4 Index Page Containing the pg. 19 Title of " Bullets" Item 5 Discussion of " Bullets" pg. 20 thru 23-pg I of 23 I
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r a is i.:1 .CPSES'FSAR AMENDMENTH
- Enclosurd-toLTXX-89567.
(LMAugust-18.3 1989f DETAILED DESCRIPTION ,
ll ,
j 'Page'11'of'23.
L FSAR'Page?
,1(as amended), Group Descriptio_rt Table 8.3-11 '4 See Sheet No(s): 1, 11 12 & 13 Editorial:
.Repaginated table.due to adding text.
FSAR Change Request. Number: 89-503.1 m SER/SSER Impact: No
! Table 8.3-11 4 See Sheet No (s): 10 Editorial:
Corrects typographical error on power source ID No.~
for service water screen wash pump 2.
FSAR Change Request Number: 89-503.2 SER/SSER Impact: No -
- . Table 8.3-11 4 See Sheet No(s): 12 1 Clarification of Note (1).
3
" ~ ~
Clarification:
Clarifies Note (1) to detail that operator actions are required after resetting SIAS, consistent with TXX-89488 dated July 26, 1989.
FSAR Change Request Number: 89-503.3 Commitment Register Number: X2-0603' Related SER Section: 7.3.2.1; .SSER2 7.3.2.1 SER/SSER Impact: No Table 8.3 3 See Sheet No (s): 3&4
' To delete "S" trip on containment lighting transformer and vent control cooling unit' cooler / chilled water MOV's.
Revision:
Containment lighting transformer and vent control cooling unit cooler / chilled water MOV's have two Class IE circuit breakers in series which meets the electrical separation requirements of Section 8.3.
The control circuit "S" contact is being removed as ,
a corrective action per TXX-89488 dated July 26, 1989.
FSAR Change Request Number: 89 503.J ;
Commitment Register Number: X2-0603 Related SER Section: 8.4.5 SER/SSER Impact: No
' Table:8.3-11 3 See Sheet No(s): 11' Adds transformers for non-Class IE MCC space heaters to table (supply breaker is tripped on an "S" signal).
~
Addition:
The safety injection trip of the MCC space heater transformer supply breaker provides' isolation between the Class IE power source and the non-Class IE loads.
~v= = , ._
... v-n'
$ nclosura1to TXX-89567 E
- v7 August 18; 1989' DETAILED-DESCRIPTION-
. ~ ?Page.12Lof 23
.e FSAR Page (as' amended) Group Description I
This is consistent with. Reg. Guide 1.75 Revision 1 and the corrective actions.of SDAR-CP 87-136 (see TXX-89428 dated July 7, 1989).
FSAR Change Request Number:.89-503.5 Commitment Register Number: NL-0787 Related SER Section: 8.4.5: SSER17 Append.B SER/SSER Impact: Yes SSER 17' Appendix B DIR No. D-2169 disposition and evaluation are impacted by change to isolation device-meeting Reg. Guide 1.75 criteria.
Figure 8.3-11 3- See Sheet No(s): 1 &L2 Adds safety injection signal trip to MCC space heater transformer supply breaker.
Revision:
Adds safety injection signal trip to transformer supply breaker associated with the non-Class IE Motor Control-Center (HCC) space heaters to isolate the non-Class IE 110 ads from the Class 1E power source. This is consistent with Reg. Guide 1.75, Revision 1, and the corrective actions of SDAR-CP-87-136 (see TXX-89428 dated July 7, 1989).
FSAR Change Request Number: 89-503.6 Commitment Register Number: NL-0787 Related.SER Section: 8.4.5: SSER17 Append.B SER/SSER Impact: Yes SSER 17 Appendix B DIR No. D-2196 disposition and evaluation are impacted by change to isolation device meeting Reg. Guide 1.75 criteria.
h
________A____ _ _ _ _ _ _ _ _ _ _ _ - _ _ ________.msi ____..__m_________.__.________.m_ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ , . _ _ _ _ _ _ _ _
Enclosure to TXX-89567
..: August 18, 1989
'Page 13 of 23 ,
The chilled water recirculation pumps start when they receive a safety injection or blackout sequence signal.
7.3.1.12 Containment Ventilation Isolation Acutation The containment purge isolation valves close automatically on detection of high-radiation levels, a manual containment spray actuation signal, or a safety injection signal. The containment pressure relief system relieves excess containment pressures caused by temperature transients or air leakage 1
from pneumatic actuators during normal operation. The pressure relief containment isolation valves automatically close on a containment ventilation isolation signal.
7.3.1.13 Combustible Gas Control Actuation Following a DBA, hydrogen gas may be generated inside the containment. To ensure that the hydrogen concentration is maintained on a safe level, electrical, redundant hydrogen recombiners and a backup hydrogen purge system are provided.
Each recombiner is provided with a separate power panel and control panel, and each is powered from a separate safeguard bus. Operation of the recombiner is performed manually from a control panel located in an accessible area outside the containment. The power panel for the recombiner centains an isolation transformer plus an SCR controller to regulate power into the recombiner.
7.3.2 Resolution of Concecns Related to ESFAS 7.3.2.1 Loss of Safety Function After Reset As was done for operating reactors through IE Bulletin 80-06, the staff has requested that the applicant review all safety equipment to determine which, if any, safety functions might be unavailable after reset, and what changes would be implemented to correct any problems.
The applicant provided a response stating that he has reviewed the design and determined that it is in conformance with the applicable guidelines, except for !
one case that contravenes the staff position. The logic to initiate containment ventilation isolation uses a radiation high-level signal and ESFAS T signal input to a retentive memory with actuation block gate. Thus a reset of a i high-radiation signal would block the ESFAS input signal. The applicant will modify the design so that the reset of one input signal will not block system -
actuation by the other input signal. At this time, the design modifications have not been completed. The staff will review the design for this system before the issuance of the Operating License. The applicant further committed that a test will be conducted during the preoperational test program to confirm l the conclusion of this review. The staff finds this acceptable. !
l 7.3.2.2 Level Measurement Errors Due to Environmental Temperature Effects on Level Instrument Reference Legs !
l The staff asked the applicant to evaluate the effects of high temperatures in reference legs of water level measuring instruments after high energy-line breaks. This issue was addressed for nperating reactors through IE Bulle-tin 79-21. In response to these concerns, the applicant has committed to )
i 4
7-17
5Ericlosure to TXX-89567 l . Augu'st 18, 1989
' ' Page 14 of 23 7 INSTRUMENTATION AND CONTROLS
- 7. 3 Engineered-Safety-Features Actuation System 7.3.1 Description 7.3.1.5 Feedwater Line Isolation Actuation As a result of the staff's review of current operating license applications for Westinghouse plants, a concern about control and protection systems inter-action has been identified which was not addressed in the earlier review. The concern relates to steam generator level measurement channels which are used for both protectica and control. The protection system initiates feedwater isolation when 2 of 3 channels indicate high level. Since one of these level channels is used for control, the failure of this channel would result in steam generator overfill by action of the level control system. As a consequence of this failure, the two remaining channels must operate to provide the required protective action.
This does not satisfy the requirements for control and pro-tection system interaction in that the remaining channels of the protection system must satisfy the single failure criterion. Therefore, the staff has requested that the applicant respond to this concern and the staff will address its resolution in a future. supplement to the SER.
7.3.2 Resolution of Concerns Related to ESFAS l 7.3.2.1 Loss of Safety Function After Reset I
In the SER, the staff indicated that the logic to initiate containment ventila-tion isolation uses a radiation high-level signal and an ESFAS signal input to a retentive memory with actuation block gate. Thus a reset of a high-radiation signal would block the ESFAS input signal. In Amendment 29 of the FSAR, the applicant provided a design change to address this issue. The high radiation signal was changed to a pulsed signal. If the gate was set because of a high-radiation signal, resetting the gate after the pulse would not invoke the actuation block feature, and thus it would initiate protective action on a sub-sequent ESFAS signal. The staff finds that the applicant's modification is acceptable, and therefore, this issue is resolved.
- 7. 7 Control Systems Not Required for Safety
- 7.7.2 Conclusions -
In the SER it was noted that the staff had requested a review by the applicant to determine whether the barsh environments associated with high energy line breaks might cause control system malfunctions and result in consequences more severe than those calculated in the Chapter 15 analyses or beyond the capability h of operators or safety systems. j w i The applicant has performed a review to evaluate the impact of control system f ailures as a consequence of harsh environments due to high-energy.line breaks.
Based on this review, the applicant concludes that'the f6110 wing failures ~could occur and that the consequences of these failures are not bounded by the safety ,
analysis provided in Chapter 15 of the FSAR. I Comanche Peak SSER #2 7-1
- ,En' closure to TXX-89567
% August 18. 1989
- Page-15'of:23
- Exposed raceways containing Class IE cables are marked by color codes in a distinct percenant manner at intervals not to exceed 15 ft and at points or' entry to and exit from enclosed areas. In general, all Class 1E cables and associated cables are jacket color-coded throughout their entire length.
Cables that require field color coding will be so worked at intervals not to exceed 5 ft. Non-Class IE equipment, raceways, and cables in raceways are not marked by color code and have a black outer jacket.
In plant areas which are free from potential hazards such as missiles, external fires, and pipe whip, the minimum separation between redundant cable trays is 3 ft between trays separated horizontally and 5 ft between trays separated vertically. In the cable spreading areas and the control room,'the minimum separation between redundant cable trays is 1 ft between trays separated horizontally and 3 ft between trays separated vertically. Where plant arrangements preclude maintaining the minimum separation distance, the redundant circuits are run in solidly enclosed raceways or other barriers p mvided between redundant circuits in accordance with Regulatory Guide 1.75.
In addition, each reactor protection system or ESF system at the channel level has its own distinct color. Protection of equipment against simultaneous
' failures is achieved by physical arrangement and separation between redundant Class 1E systems.
Each diesel generator, including its associated auxiliaries, is located in a separate room. The electrical switchgear of train A is separated from that of train B by locating them on different elevations.
Each Class IE 125-V de battery is located in a separate and independently ventilated room. Battery chargers, distribution panels, and SUPS of one train are separated from those of other trains by locating them in separate rooms.
The Class 1E MCCs and distribution panels of one train are separated from -
those of the other train by's distance of at least 20 ft. Where it is not possible to maintain a 20-ft distance, barriers are provided to maintain proper separation. The control room and cable spreading at es do not contain high-energy equipment such as switchgear, transformers, rotating equipment, high-energy piping, or other potential sources of missiles.
Based on its review of the applicant's design criteria regarding physical identification, separation, and independence of redundant safety-related electrical systems, the staff finds these criteria to be in accordance with Regulatory Guide 1.75 and, therefore, acceptable. However, the staff will -
verify the implementation of applicant's design criteria for these areas during a site visit.
8.4.5 Nonsafety Loads on Emergency Sources Present regulatory practice for Operating License applications allows the connection of nonsafety loads--in addition to the required safety loads--to Clars 1E (emergency) power sources if it can be shown that the connection of nonsafety loads will not result in degradation of the Class IE system. The Comanche Peak design provides for the connection of both safety and selected nonsafety loads to the Class 1E emergency buses of the ac and de onsite emergency power systems. ._. __ .,. .
l i
8-16
hk [ [En'closuro'to TXX-89567 i l '
1 Augu'st 18 '1989.-
Page'16 of.23 .
The design provides for the automatic disconnection of all nonsafety loads connected.to ths.5.9-W and 480-V swit-hgear upon catection of a sare.ty injec- ;
tion signal except the following:
(1) radiation monitoring system
.(2) fire detection system (3) security system I
- l. (4) communication system (5) annunciator logic cabinet
'(6) chlorine detection system These non-Class IE loads are connected to Class IE buses via isolation which tion. are constant voltage transformers and are subject to Class 1E qualifica-tion with a phase-to phase, three-. These transformers are designed for continu output of the secondary windings. phase, or phase-to ground fault at the l The transformers input current under short-circuit conditions is limited to 150% of rated.
input has been considered a continuous' load for sizing the diesel generatorThe and all distribution equipment associated with the isolation transformer to ensure that no failure in the non-Class 1E circuits will-cause unacceptable influences in the Class IE circuits. The staff finds this aspect of design acceptable.
When a Class IE contact performs a non-Class 1E control function-(such as energizing a solenoid for a non-Class 1E valve), isolation is provided by an
' auxiliary relay.. When a Class IE contact performs a non-Class IE monitoring function (such as activating an alarm or input to a computer), an isolation is provided by a phototransistor coupled pair (LED and a transistor).
Based on its evaluation of the information provided by the applicant, the staff concludes that the design provides for the automatic disconnection of nonsafety loads connected to the 6.9-kV and most of the 480-V buses upon detection of therefore, an ESFAS signal in accordance wih Regulatory Guide 1.75 and is, acceptable.
Use of isolating transformers as current-timiting isolation devices to the rest of the 480-V switchgear meets the requirement of
- isolation devices per IEEE-384-1977 and is, therefore, acceptable. -
8.4.6 Fire Protection
.Special requirements for the plant electrical systems to satisfy Appendix A to BTP APCS 8 9.5-1, " Guidelines for Fire Protection of Nuclear Power Plants," will ,
'be reviewed later during the fire protection review. After this review, additional of the electrical recommendations systems. may be proposed to further improve the capability a, - ,3 ;
8-17 '
w_-______m._____ _ _ . _ _ _ _ _ . _ . . _
.Encicsura to TXX-89567
, E 7 Augu'st 18, 1989
- Page 17 of-23 and 57977 have been issued. These DCAs add interposing relays to isolate the h;aters in the event of an accident conditon and to correct voltage problems.
NRC EVALUATION-
'The four concerns were addressed by replacement calculations and appropriate subsequent followup actions. We agree with this resolution.
DIR NO: 0-2041, Rev. O PROBLEM STATEMENT Process instrument sizing is normally accomplished by following the vendor re-
'quirements. Those requirements are specified in the cable specification ES-13C.
However, for other miscellaneous process and electrical instrument cables for which there is no specific vendor input, there is no G&H document to establish their design basis.
DISPOSITION instrument cables that are supplied by a process instrument manufacturer as part of a package or skid unit are not purchased through a G&H instrument cable specification. However, the cable selected by the instrument manufacturer must be consistent with the design basis and criteria established for the package /
skid unit as a whole as defined in the instrument purchase specification. The manufacturer has guaranteed that the unit meets the established design require-ments; it is ; hat manufacturer's responsibility to insure adequate cable siz-ing. No case has been found in which cable was procured without an appropriate requireter.t being specified either in the G&H cable specification or the equip-ment procurement specification.
NRC EVALUATION i
The concern is adequately addressed since the cable selected by the instrument }
m:nufacturer must be consistent with the design basis and criteria established for the package / skid unit as defined in the instrumer.t purchase specification.
We agree with this disposition. .
+ DIR NO: D-2169, Rev. 1 ,
PROBLEM STATEMENT i I
(Rev'd. 11/28/86) DCA 2861 (Rev. 1) changes the classification of the MCC l space heaters to non-Class IE. This then required that these have isolation devices. Acceptable isolation devices are not provided per Reg. Guide 1.75 (1975). '
DISPOSITION Space heaters are not required when the MCC is energized and are to be dist;anected.
l l
l Comanche Peak SSER 17 32 Appendix B
En'c1csura to TXX-8;567 p l Augru's t 18, 1989
'tPage 18 of 23 -
1
?
NRC EVALUATION l
Design Change Authorization (DCA) Number 59664, Revision 1, dated August 25, 1988 acknowledges that non-Class IE motor control center space heaters are electrically connected to Class IE motor control center buses through a trans-former. This DCA requires that two fuses feeding non-Class 1E space heater circuits and located on the secondary side of space heater transformers be removed and replaced with red plastic plugs when attendant Class 1E motor con-trol centers are energized. This design change provides adequate electrical isolation between applicable Class 1E power sources and non-Class IE spac2 heaters and as such we agree with this resolution.
i l
I l l l
1 i
Comanche Peak SSER 17 33 Appendix B 1
l- _. . . l
.En'cicsura to TXX-89567 q, Augu'st 18,.1989
- Page 19 of.23 8.3.1 AC Power System
- 31. The FSAR has been clarified regarding electrical isolation for Motor Control Center non-Class IE space heaters (their transformer supply breaker trips on an "S*' signal).
1 O
_i_.______._______._.____._ __
e
~
-*Pagc120~of:23' FSAR'Page (as amended) Group Description Table 8.3 3 See Sheet No(s): 11 Adds transformers for non-Class IE MCC space heaters to table (supply breaker is tripped on an "S" signal).
Addition:
The safety injection trip of the MCC space heater transformer. supply breaker provides isolation between the Class IE power source and the non Class IE loads.
This is consistent with Reg. Guide 1.75 Revision 1, and the corrective actions of SDAR CP-87-136 (see TXX-89428 dated July 7, 1989).
FSAR Change Request Number: 89-503.5 Commitment Register Humber: NL-078/
Related SER Section: 8.4.5; SSER17 Append.B SER/SSER Impact: Yes SSER 17 Appendix B DIR No. D-2169 disposition and evaluation are impacted by change to isolation device meeting Reg. Guide 1.75 criteria.
Fi gure' 8.3'-11 3 See Sheet No(s): 1&2 Adds safety injection signal trip to MCC space heater transformer supply breaker.
Revision:
Adds sbfety injection signal trip to transformer supply.
breaker associated with the non-Class IE Motor Control Center (MCC) space htaters to isolate the non-Class IE loads from the Class IE power source. This is consistent with Reg. Guide 1.75, Revision 1, and the corrective actions of SDAR-CP-87-136 (see TXX-89428 dated July 7, 1989).
FSAR Change Request Number: 89-503.6 Commitment Register Number: NL-0787 Related SER Section: 8.4.5: SSER17 Append.8 SER/SSER Impact: Yes SSER 17 Appendix B DIR No. D-2196 disposition and evaluation are impacted by change to isolation device meeting Reg. Guide 1.75 criteria. ,
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