ML20247C043
| ML20247C043 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 08/31/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-89634, NUDOCS 8909130223 | |
| Download: ML20247C043 (39) | |
Text
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' Log # TXX-89634 1
C.
File f.- 20010 2
C 918 lilELECTRIC August 31, 1989
' Executive 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: UPDATED RESPONSE TO 010.20 AND 0140.1-CONCERNING' MAIN STEAMLINE BREAKS OUTSIDE CONTAINMENT Gentlemen:
1 The. enclosure to this. letter provides an advance FSAR change related to the main steamline break analysis outside containment. This change revises previously submitted FSAR changes, in Amendment 76, and is the result of revised temperature calculations and the associated equipment operability times.
In addition, to these changes, the enclosure to this letter provides related supporting documentation. 'These changes will be reflected in a future
-FSAR amendment.
In order to' facilitate NRC staff review of these changes, the enclosure is
' organized as follows:
1.
Draft revised FSAR pages, with changed portions indicated by a bar 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).
2.
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 consolidate and categorize similar individual changes by subject and related SER/SSER section.
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' 400 North Olive Street LB 81 Dallas, Texas 75201 u
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I
TXX-89634 August 31,'1989 Page 2 of 2 5.
A discussion of each " bullet" which includes a 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.
In some cases where the bold / overstrike versinn is unavailable, a hand marked up version will be provided.
Sincerely,
)
114 William J. Cahill, Jr.
By:
<A Roger @. Walker Manager, Nuclear Licensing BSD/bsd Enclosure c - Mr. R. D. Martin, Region IV Resident In-ctors, CPSES (3) i
4
+}
i Enclosure to TXX-89634 August 31, 1989 Page 1 of 36 Advance FSAR Change to Response for Questions 10.20 and 140.1 and Supporting Documentation Item 1 Draft Revised FSAR pages pp. 2 - 13 Item 2 Line-by-line Description / Justification pp. 14 - ?.1 for each FSAR Change Item Item 3 Related SER/SSER Pages pp. 22 - 23 Item 4 Index page of bullet title (s) p.
24 Item 5 Discussion of each bullet pp. 25 - 36 i
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___________________________________-___d
a.
CPSES/FSAR
, 11 Auxiliary Feedwater Flow Indicators E.
t DRAFT These instruments indicate flow in the control room for accident monitoring, but have no control function.
They have a demonstrated operability beyond that required for the safe plant shutdown.
I 11 floodino Evaluation g
DRAFT The worst flooding will occur as a result of a fe2dwater k
Ifne break in any one of the feedwater piping compartments 100A1 through 100A4. The water spills over an opening 7' high and 3' wide into compartments 200A5 The maximum flood height in the break through 100AB.
11 The maximum flood level in the compartment is 9*6".
The structural spill over compartment is 7'10".
P integrity of the building will not be impaired as a s
result of these flood levels concurrent with the maximu 4,
f; pressurede(eloped.
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a 11
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- Chrsioloay ofnEyents
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f, 11 l Durjng;the following e{ents, the maximum temperature
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010-28h
p" CPSES/FSAR Enclosure"to TXX-89634 B.
Pom r-Op3 rat;d Main Stea3 Relief Valves (PORV's) 11-Page_2 of 36 These valves are air-to-open, fail closed. The 76 pressure transducers which provfde the signal to open these valves are on the main stem lines within their
'~
respective main steam compartments. The PORVs in the compartment with the crack may fail in either the open or closed position without increasing the sever 1ty of the event beyond the present analysis or decreasing the ability to mitigate the event and safely shutdown the unit. The PORVs and pressure transducers in the compartments without the crack have a demonstrated operability beyond that required for their safety function (See Table 0140.1-1).
C.
Auxiliary Feedwater Turbine Stone Supply Valves l11 The failure mode of the valve in the compartment with 76 the crack due to the accident environment does net prevent safe shutdown of the unit. The valve in the compartments without the crack have a demonstrated operability beyond that required for its safety function.
D.
Auxiliary Feedwater Containment. Isolation Valves 11 These valves are motor operated, fail-as-is and are 11 normally open and de-energized. Consequently, the accident environment cannot cause these valves to close.
It is postulat:Ad that there is a requirement to close DRAFT the valve supplying auxiliary feedwater to the faulted steam generator. The valves have a demonstrated operability beyond that required for their safety function.
010-28g Draft Version
_________________1-__
r CPSES/FSAR
' Enclosure to TXX-89634 Paga 3 of 36:
E.
Auxiliary Fcedwater Flo3 Indicators l11 1
These instruments indicate-flow in the control room for DRAFT.
accident monitoring, but have no control function, j
They have a demonstrated operability beyond that required for the safe plant shutdown.
I Floodina Evaluation 11 j
I The worst flooding will occur as a result of a feedwater DRAFT line break in any one of the feedwater piping compartments 100A1 through 100A4. The water spills over an opening 7' high and 3' wide into compartments 100A5 through 100A8. The maximum flood height in the break compartment is 9'6".
The maximum flood level in the 11 j
spill over compartment is 7'10".
The structural integrity of the building will not be impaired as a result of these flood levels concurrent with the maximum pressure developed.
Chronoloav of Events 11 During the following events, the maximum temperature 11 occurs inside the compartments during the main steam line. crack and the maximum pressure occurs during the feedwater line crack,
'i 010-28h Draft Version
osu TXX-89634 Mass and en:rgy releaso data tas calculated for 76 both full power and 70% power.
. Full power with 1.0 ft2 brea_k provided the worst 1
environmental results.
Table-140.1-2 provides the mass and energy release data.
j b.
The time sequence based on'a 1.0 ft2 break
]
and an initial power level of 100% is as follows:
)
1
.l Reactor Trip on high neutron - 11.0 seconds.
76 flux 76 J
Feedwater Isolation (due to
- 28.9 seconds 76 reactor, trip and low Tavg) 76 Safety Injection Signal
- 36.4 seconds 76 (due to low pressurizer pressure signal)
DRAFT Steam Generator Tube Uncovery - 195 seconds 76 Steauline Isolation (due to
- 304 seconds ORAFT low steam 11ne pressure) 76
~
Auxiliary Feedwater Isolation - 1800 seconds 76 (manual) 76 4
140-4 Draft Version
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.CPSES/FSAR:
Enclosura to TxX-89634 TABLE 140.1-2' 76 7
LPage 13:of.'36.
' COMANCHE PEAK MASS / ENERGY RELEASES 76 FULL POWER - 1.00 FT2 STEAMLINE BREAK
~76
. TIME FLOW ENTHALPY SUPERHEAT 76
-(SEC)
(LB/SEC}-
___JBTU/LB)
(BTU /LB)*
76 0.5 2047.
1190.
76 19.0 2134.
1190.
76:
12.0
- 1767, 1195.
76
'22.0 2110.
1191.
76 29.5 1960.
1194.
76 50.0 1740.
1197.
76 100.0 1325.
1202.
76 135.0 1237.
1203.76-195.0 1218.
1203.
1.
76 299.0 1011.
1227.
24.
76
~
319.0 541.5 1253.
52.
76 345.0 115.1 1281.
106.
76 373.0.
70.15 1286.
120.
76 413.0.
73.07 1285.
119.
76 495.0 72.69 1285.
119.
76 611.0' 72.83 1283.
117.
76 815.0 72.89 1279.
113.
76 895.6 72.91
~1278.
112.
76 993.0 73.00 1277.
111.
76 1073.0 72.99 1277.
111.
76 1319.0 73.00 1276.-
110.
76 1539.0 73.03 1276.
110.
76 1757.0 73.04 1276.
110.
76 1799.0 73.04 12)6.
110..
76
- above saturation enthalpy 76 Reactor Trip on High Neutron Flux at 11.0 sac.
76 Safety injection on' Low Pressurizer Pressure at 36.4 sec.
76 feedwater Isolation at 28.9 scc.
76 ~
Low Steam Pressure Setpoint reached at 304 sec.
i 76 Steamline Isolation at 409 sec.
l77 Tube Bundle Uncovery predicted at 195 sec.
76 AFW Isolation assumed at 1800 sec.
76 AMEN 6 MENT 77 SEPTEMBER 8,1989 a
m wem veun m m DETAILED DESCRIPTION Page 1 l
Enclosure't'oLTXX-89634'
< I ',. -
'Page 14 of L FSAR Page-(as amended)
Group Description
..H a
O&R 010&l40-a11 2
Environmental impact of an MSLB with superheat releases Update:
O&R010.20 and Q&R140.1 have been revised since Amendment 76. Several of the environmental conditions have been updated to reflect the results of revised calculations, current vendor documentation and correct errors (including omissions) in Amendment 76.
FSAR Change Request Number: 89-611.25 Related SSER Section: SSER12 3.11.6
~SER/SSER Impact: Yes Generically, the information in 0&R010 and 140 require NRC review to close-out Outstanding Issue (39) regard-ing the environmental impact of an MSLB outside con-tainment. The information in this change in conjunction with the changes in Amendment 76 require NRC review.
~
Q&R 010"28g 2
Environmental impact of an MSLB with superheat releases Correction:
Revised ter.t to describe the correct function of the auxiliary feedwater containment isolation valves. These valves are postulated to be closed / energized to isolate auxiliary feedwater to a faulted steam generator, and-therefore are qualified for their intended use.
FSAR Change Request Number: 89-611.1 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No O&R 010-28h 2
Environmental impact of an MSLB with superheat releases Correction:
Revised text to reflect th3t although the auxiliary feedwater flow indicators do not provide a control function, these indicators are required for accidtnt monitoring and therefore meet the qualification requirements of Reg Guide 1.97, Rev. 2.
FSAR Change Request Number: 89-611.2 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No O1R 010-28h 2
Environmental impact of an MSLB with superheat releases Correction:
Revised text to provide clarification of the flooding evaluation and provide the correct room numbers. The worst case flooding resulting from a feedwater line break could develop from a break in any of the fee 1 water piping compartneri s resulting in the worst t
case flood level (s) in the compartment with the break of nine feet six inches (9't") and seven feet ten inches (7'10") in an adjacent compartment.
FSAR Change Request Number: 89-611.3
Enclosura to TXX-89634 '
DETAILED DESCRIPTION Page 2 Page.15 of 36 i
FSAR Page' (as amended) far_gigt Description Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R 140-4 4
Environmental impact of an MSLB with superheat releases j
Clarification:
Added the term " pressure" to better describe the initiating safety injection signal.
FSAR Change Request Number: 89-611.4 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R 140-4 2
Environmental impact of an MSLB with superheat releases Correction:
Revised the, response time for steamline isolation based on a 1 square foot break when the plant is at full power. After the initiating event, steam 11ne isolation was determinnd to occur at 304 seconds instead of 311 seconds.
FSAR Change Request Number: 89-611.5 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 4
See Sheet No(s):See sheets 1 through 8 Environmental impact of an MSLB with_superheat releases Correction:
Note s was incorrectly referenced as being applicable to "tise margin" in the header of the table. However, the correct application is " demonstrated operability time."
FSAR Change Request Number: 89-611.6 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 2
See Sheet No(s):1 Environmental impact of an MSLB with superheat releases Update:
Updated the required operability time for the main steam isolation valves to 309 seconds. The previous time of 12 minutes was derived from an earlier calculation that has since been revised and updated.
The corresponding demonstrated operability time is consistent with the latest information in the environmental profiles which were developed based on vendor test documents, with the associated time margin being the difference between demonstrated and required operability times to the Learest minute.
FSAR Change Fequest Number: 89-611.7 Related SSER Section: SSER12 3.11.6
(
-Enc 1csuro'to TXX-89634 DETAILED DESCRIPTION-Page 3
.Page 16 of 36 lFSAR'Page (as amended)
Group Description SER/SSER Impact: No Q&R Table 140.1-1 2
See Sheet No(s):1 Environmental impact of an MSLB with superheat releases Update:
Updated the demonstrated qualification peak temperature for the main steam drain pot isolation valves. This value represents the test temperature identified in the_ vendor test report.
FSAR Change Request Number: 89-611.8 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 2
See Sheet No(p):1 Environmental impact of an MSLB with superheat releases Update:
Updated the required operability time for the main steam drain pot isolation valves to 309 seconds. The previous time of 12 minutes was derived from an earlier calculation that has since been revised and updated.
The corresponding demonstrated operability time represents the qualified test duration identified in the vendor test report, with the time margin being the difference between the demonstrated and required operability times to the nearest day.
FSAR Change Request Number: 89-611.9 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 2
See Sheet No(s):2 Environmental impact of an MSLB with superheat releases Update:
Updated the required operability times for the feed-water isolation, bypass and sample isolation valves to 34 seconds. The previous time of 12 minutes was derived from an earlier calculation that has since been revised and updated.
Secondly, revised the demonstrated peak qualification temperatures to be consistent with the environmental profiles identified in the applicable vendor test report.
Thirdly, revised the demonstrated operability times to reflect the duration for which equipment is qualified.
with the time margin being the difference between the demonstrated and the required operability times to the nearest minute for the feedwater isolation valves and to the nearest day for the feedwater bypass and feedwater sample isolation valves.
FSAR Change Request Number: 89-611.10 l
k CP5ES FSAR AMENDMENT 77 Enclosure to.TXX-89634 DETAILED DESCRIPTION Page'4 y
y
~Page-17 ef 36 y
FSAR Page
-(as amended)
Group Description Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No O&R Table 140.1-1.
2 See Sheet No'(s):2 Environmental impact of an MSLB with superheat releases Update:
Revised the equipment title such that turbine driven auxiliary feedwater pump " turbine" steam supply valve better describes the component. Secondly, revised the postulated peak temperature to reflect the calculated value for this equipment. Thirdly,' revised the demonstrated peak temperature to be consistent with the environmental profiles supplied by the vendor with the time margin being the difference between the demonstrated and required operability times of the equipmefit.
FSAR Change Request Number: 89-611.12 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No l
0&R Table 140.1-1 2
See Sheet No(s):3 Environmental impact of an MSLB with superheat releases Update:
. Revised the demonstrated peak qualification temperature for the main steam power operated relief valves to be
. unsistent with the environmental profile identified in the vendor test report.
FSAR' Change Request Number: 89-611.13 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No O&R Table 140.1-1 2
See Sheet No(s):3 Environmental impact of an MSLB with superheat releases Update:
Updated the required operability time for the barton steam line pressure transmitters. These transmitters have been determined as not required operate for the 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> duration (i.e. to achieve cold shutdown), but is required for a shorter duration of 304 seconds.
Seccndly, revised the demonstrated peak qualification temperature to be consistent with the environmental profiles in the applicable vendor document (s),
Thirdly, revised the demonstrated operability time to reflect the duration for which the equipment is qualified, with the tint margin being the difference between the demonstrated and required operability times. Finally, added Note 12 to indicate that this equipment is utilized for accident monitoring. The term " provide steamline isolation signal" is a
LPSES FSAR AMEWDMENT 77 Enclosure to TXX-89634 DETAILED DESCRIPTION Pago 5 Page 18 of-36
'FSAR Page (as amended)
Group Description
~
duplicate of Note 6 and was therefore deleted.
FSAR Change Request Number: 89-611.14 Related SSER Section: SSER12 3.11.6 i
SER/SSER Impact: No O&R Table 140.1 2 See Sheet No(s):4 Environmental impact of an MSLB with superheat releases Update:
Revised the demonstrated peak qualification temperature, and demonstrated operability time to be consistent with the vendor test report for the rosemount steam line pressure transmitters. Secondly, revised the time margin, to the nearest day, to reflect the change in demonstrated operability time. Thirdly, deleted the words in the notes column of the table and added them at the end to the notes section of the table.
FSAR Change Request Number: 89-611.15 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table-140.1 1 2
See Sheet Ho(s):4 Environmental impact of an MSLB with superheat releases Addition:
Added the applicable information for the HVAC isolation dampers. The previous infromation was incorrect.
FSAR Change Request Number: 89-611.26 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 2
See Sheet No(s):5 Environmental impact of an MSLB with superheat releases Update:
Revised the required operability times for the accessory limit switches for the main steam isolation and bypass valves, main steam PORV's, feedwater 0_
isolation and bypass valves, main steam drain pot isolation valves, turbine driven auxiliary feedwater pump turbine steam supply valves, feedwater sample isolation valves; and auxiliary feedwater flow transmitters. Secondly, revised the demonstrated qualification peak temperature and operability times to be consistent with the environmental profiles in the vendor test report, with the margin being the difference between the demonstrated and required operability times. Thirdly, deleted note 10 which states that this equipment is not required to function, and added note 12 to indicate that the limit switches e
9
' Enclosure to TXX-89634 CPSES FSAR AMENDMENT 77 i
Page 19 of 36 DETAILED DESCRIPTION Pag 2 6 f
FSAR Page (n amended)
Group Description and flow transmitters are utilized for accident monitoring.
FSAR Change Request Number: 89-611.16 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 2
See Sheet No(s):5 Environmental impact of an MSLB with superheat releases Addition:
Added main steam safety valve position indicator and auxiliary feedwater containment isolation motor operated valves to the table. This equipment was not included in the previous Amendment 76 submittal.
FSAR Change Request Number: 89-611.17 Related SSER Section* SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 2
See Sheet No(s):6 Environmental impact of an MSLB with superheat releases Update:
Revised note 2 to be consistent with the changes in the table applicable to the main steam isolation valves. The MSIV's are hydraulically operated. A hydraulic control system maintains hydraulic fluid below the valve actuator piston which controls valve closure. To close the valves, hydraulic fluid is bled from below the piston to a reservoir. Since the demonstrated operability time for these valvi.s is 90 minutes, the potential exist for the valves to reopen due to the solenoid valves in the hydraulic lines failing close. To ensure that the MSIV's remain closed following a MSLB, procedurally, the operator secures instrument air to the hydraulic pump, such that the pump does not resume to open the MSIV's.
FSAR Change Request Number: 89-611.18 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 3
See Sheet No(s):6 Environmental impact of an MSLB with superheat releases Correction:
Clarification of Note 4 to better describe the operation of the noted valves.
FSAR Change Request Number: 89-611.19 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 4
See Sheet No(s):6
pj o
',.y AnclosurytoTXX-89634
-DETAILED DESCRIPTION Page 7-Page 20 of 36
.FSAR Page
-(31 amended)
Group Description Environmental impact of an MSLB with superheat releases Clarification:
Clarification of Notes 5 to indicate that the 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> required operability time is based 7n the I
plant reaching a cold shutdown condition.
FSAR Change Request Number: 89-611.20
)
Related SSER Section: SSER12 3.11.6 j
SER/SSER 1mpact: No Q&R Table 140.1-1 2
See Sheet No(s):7 Environmental impact of an MSLB with superheat releases Addition:
Revised Note 9 to clarify that the environmental information is applicable to gasket material for j
FSAR Change Request Number: 89-611.11 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No Q&R Table 140.1-1 2
See Sheet No(s):7 Environmental impact of an MSLB with superheat releases Correction:
Clarification of Note 7 to indicate that in the room 4
s o with the break, the rosemount transmitters can
- c c o r. -
~
m
' fail without impacting the mitigation and/or preventing the s c '
safe shutdown of the plant.
to c; a
V FSAR Change Request Number: 89-611.21 Related SSER Section: SSER12 3.11.6 o o wo r:cm wtes. the poi-n1,? evnSER/SSERrimpact: No
-w tc the g, m
m3 s
4 I400 Cl0SP
*!bdi
!ne Q&R1 Table f140ci-1
'2
- See^ Sheet No(s):7: e (Environmentaltimpact of an MSLB with superheat releases secures instr e m o
a the cump does not re.uw tcCorrection:a n
= M Change Reue r h uwe r - es-Revised Note 10 to reflect that the noted valves are ce:ated SSER Sec" %
N 912 3 required to accomplish a safety function. For this particular application, the auxiliary feedwater
> "ss E P impact.
m isolation motor operated valves are necessary to isolate the auxiliary feedwater supply for a faulted a
steam generator condition.
FSAR Change Request Number: 89-611.22
,n t ? 4 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No w
mue Re;ue a
- Q&R Table-140:1-1 2
< See Sheet No(s):7 Environmental impact of an MSLB with superheat releases Correction:
Revised Note 12 to reflect that the noted equipment
,xs is utilized for accident monitoring.
.:<2 CPSES FSAR AMENOMENT 77-Enclosure to TXX-89634 ~
DETAILED DESCRIPTION Page 8
-Page 21 of 36
~
, FSAR Page.
-(As amended)'
Group Description FSAR Change Request Number: 89-611.23 Related SSER Section: SSER12 3.11.6 SER/SSER Impact: No D
Q&R. Table 140.1-1 i
See Sheet No(s):7 Environmental impact of an MSLB with superheat releases Correction:
Revised Note 15 to better describe the function of the noted equipment.
FSAR Change Request Number: 89-611.24 Related SSER Section: SSER37. 3.11.6 SER/SSER Impact: No n- 't ne - 11
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4
Enclosure to TXX-89634 Page 22.of 36 Summary and License Candittens -
on the basis of the SQRT sita audit and he submittals free the appiteant, the staff concludes that the applicant's equipment setanic and tynseic qualification program, having been satisfactorily defined and taplemented according tc the cur-rent staff Itcensing eMteria, is in conformance with the pertirsent poniens of sne General Design Criteria as stated above.
The staff, therefore, rScwamends issuance of tho'eperating license, subject to the following conditions, which 2re being added te section 1.9 as License Conditten (17):
The applicant's resolutten af Generic Itas 1 relating te equipment instala (1) lation is found acceptable. Newever, this acceptante is subject te overall ac:eptance of the adequacy of the quality assurance program institutes at Cemenche Peak by the NRC Technical Soview Team.
(2).The applicant should complete qualification, including full documentatten, before exceeding)E power of operation for differential pressure indicating switches (ESE-40 and auxiliary relay recP. (ESE-XX). See Table 3.3.
J.n Environmental qualification of Safetv telated Electrical touissent
- 1. n.4 Oue11fication of Equipment 3.n.4.1 Electrical Equipment Iaportant to Safety
. n. 4.1. 2 Equipment Requiring Additieral Informatt'n and/or Corrective Action a
- a Section 3.11.4.1.2
- sue, the applicant must setsit analyses for the nitrogen (N-18) d
?-la junction hem to confire that this equipment has been environmentally quali-iied.
This was aise identified in Table 8.2 of Supplement 8 as Feetneta c.
The
'nfometten required by the staff was docusested in FSAR Amenesent 53 by the amplicant.
The staff has reviewed this information and finds that it is suffi-cient to fully resolve this issne.
Therefore, Cerfireetery Issue (14), listed in Section 1.8 of the SER and intredeced by Sepplement 8, is considered resolved.
3.n.8 Environmental Iapest of a flate Stees11me Broek Itfth Seperheat Relesse The environmental gus11ficetten programs for safety-related electrical equipment.
aust consider the time dependent taaperature and pressure at the location of the equipment for the meet severe desige-bests accident.
A methodelegy for comput-1 ing mass and enery relswes for postulated main steemline break (MSLS) accidents for Westinpouse reesters is described in Tepical Asperts nCAP-8821 and WCAP-8822.
In the course of its revleu of WCAp-88tt, the staff noted that the steam genera-ter bleudoun andel did not account for the heet transfer from the uncovered Deetion of the steam genomter tube bundle to the escaping staan.
It was de-termined that certain break sizes would produce superheated bloudewn and greater
- ergy r%1 eases than had been prevleusly calculated.
The superheating of the steam occurs when the break area is sufficiently large se that feedwater flew to the steam generater cannet keep up with the steam less through the break and the water level in the generater falls, thus uncovering the steam generator tube bungle.
I The steam produced in the generater is thus superheated by the uncovered M he Peat S$ER 12 3-19 L....
Enclosure to TXX-89634 Page-23 of 36 portion of the tube handle 2nd is released through the break. The primary concern is the qualification of safety-relasted electrical equipment to the proper tam-perature environment.
On June 4 and July 2,190's, the applicant elly and by letter infomed Region IV of a deficiency regarding the temperature envelope requirements en the environmental qualiftdation of equipment outside containment for high-energy line breaks. % a letter dated Augest N,1984, the applicant advised the staff that the teestinpouse tuners Greg has developed a to address the issue en a generic heats. % a letter ested Septemer N,
, the appli-cant prwided en evaluation of the effects of en ItdLS outside containment.
Staff reviam of that evaluetten resulted.in a letter ested December 21, 1994, in which the staff requested addittensi taformation. The applicenc responded in a letter dated February M.195. That lettee indicated that a plant-specific analysis of the ames and enery release rete will be prepared for Comanche Peak.
Staff evaluation of the applicant's seemittals is sentientes. The guestion of whether the electrieel equipment la the aheve aespertments Is qualified to the worse accident condittens to identified la Section 1.7 of this ogplement as Outstanding Issue (39).
e e
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hi
' ^
P Enclosure to TXX-89634 1;-
.'Paga 24.of 36
{
L 3.11' Environmental Qualification of Safety-Related Electrical Equipment.
i.
a I
28.
The FSAR has revised the response to Q&R 140.1 (and related Q&R's) to change the qualification temperatures and operation durations for Main Steam tunnel components.
e
._______.________._4.________
F T
CPSES/FSAR I
. Enclosure to TXX-89634 Paga 2.5 of 36
'B.
Power-Op3 rated Main Stea] R311ef Valves (PORV's)
Il These valves are air-to-open, fail closed. The 76 pressure transducers which provide the signal to open
, these valves are on the main steam lines within their I
respective main steam compartments. The PORVs in the compartment with the crack may fail in either the open or closed position without increasing the severity of the event beyond the present analysis or decreasing the ability to mitigate the event and safely shutdown the unit. The PORVs and pressure transducers in the compartments without the crack have a demonstrated operability beyond that required for their safety function (See Table 0140.1-1).
C.
Auxiliary Feedwater Turbine Steam Supply Valves 11 The failure mode of the valve in the compartment with 76 the crack due to the accident environment does not prevent safe shutdown of the unit. The valve in the compartments without the crack have a demonstrated oprability beyond that required for its safety function.
D.
Auxiliary feedwater Containment Isolation Valves l11 These valves are motor operated, fail-as-is and are 11 normally open and de-energized. Consequently, the accident environment cannot cause these valves to close.
It is ddt postulated that there is didTd 5d a requirenerst to close theid valved supplying auxiliary feedwater to the faulted stese generater dd/fdd fMd diffdddf 5didd ddddfdd/dd in tNii Addififf. The valves have a Gemeestrated operability beyond that required for their safety function.
010-28 g Bold /0verstrike Version
i Enclosure to TXX-59634 CPSES/FSAR 98
+
E.
Auxiliary Feedster Flow Indicators 11 These instruments indicate flow in the control room for 11
)
accident monitoring. /ddd but ddd have no control function. They have a demonstrated operability beyond 75 that required for the safe plant shutdeun ifd ddf
/ddditdd fd difMdfddd fMd ddWitdddddfdl dffdLid df fMd pdifdrifdd tidtt dintd dfudt fdditiffdd fd didffd57d (diddi 4dddfdtdt Edidil.
l
}
l11 Floodina Evaluation The worst flooding will occur as a result of a feedwater line break in any one of the feeduster piping compartments 100A1 through 10044. The water spills over an opening 7' high and 3' wide into compartments 100A5 through 10048. The maximum fleed height in the break compartment is 9*6".
The maximes fleed level in the 11 spill ever compartment is 7'10".fdM dddedt 199ft TNd difdt in fNdt /dM #fli tidd fd i Idddl~df 71/07 (NdidNf,
df fNd ididd/fddi Nf fM/dd/fddf diddfddl ddd fMdd ipf77 d/dt inid /dM dddedt 19961 TNd id5dd(dddf fiddd TdidT id fNd (dMd Will ddf didddd 71/971 The structural integrity of the building will not be impaired as a result of these flood levels concurrent with the maximum pressure developed.
Chronolony of Events 11 During the following events, the maximus temperature 11 occurs inside the compartments during the main steam line crack and the riaximum pressure occurs during the feedwater line crack.
010-28h Bold /0verstrike Version
r.
k CPSES/FSAR
[.i.
Enclosure to'TXX-89634 Pags 27 of 36 Mass and en:rgy release data tas calculated for 76 both full power and 70% power.
Full power with 1.0 ft2 break provided the worst environmental results.
Table 140.1-2 provides the mass and energy release data.
b.
The time sequence based on a 1.0 ft2 break and an initial power level of 1005 is as follows:
Reactor Trip on high neutron - 11.0 seconds 76 flux 76 Feedwater Isolation (due to
- 28.9 seconds 76 reactor trip and low Tavg) 76 Safety Injection Signal
- 36.4 seconds 76 (due to low pressurizer pressure signal) 76 Steam Generator Tube Uncovery - 10% seconds 76 Steamline Isolation (due to
- 304311 seconds low steamline pressure) 76 Auxiliary Feedwater Isolatio'n - 1800 seconds 76 (manual) 76 i
140-4 Bold /0verstrike Version
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41
.Encibsure'to TXX-89634 CPSES/FSAR Paga 36'of 36 TABLE 140.1-2 76 COMANCHE' PEAK MASS / ENERGY RELEASES 76 FULL POWER - 1.00 FT2 STEAMLINE BREAK 76
]
1 TIME FLOW ENTHALPY SUPERHEAT 76 (LB/SEC)
(BTU /LB)
(BTU /LB)*
76 (SEC) 0.5 2047.
1190.
76 19.0-2134.
1190.
76 12.0 1767.
1195.
76 22.0 2110.
1191.
76 29.5 1960.
1194.
76 50.0 1740.
1197.
76 100.0 1325.
1202.
76 135.0 1237.
1203.
76 195.0 1218.
1203.
1.
76 299.0 1011.
1227.
24.
76 319.0 541.5
- 1253, 52.
76 345.0 115.1 1281.
106.
76 373.0 70.15 1286.
120.
76 413.0 73.07 1285.
119.
76 495.0 72.89 1285.
119.
76 611.0 72.88 1283.
117.
76 815.0 72.89 1279.
113.
76 895.0 72.91 1278.
112.
76 993.0 73.00 1277.
111.
76 1073.0 72.99 1277.
111.
76 1319.0 73.00 1276.
110.
76 1539.0 73.03 1276.
110.
76 1757.0 73.04 1276.
110.
76 1799.0 73.04 1276.
110.
76
- above saturation enthalpy 76 Reactor Trip on High Neutron Flux at 11.0 sec.
76 Safety Injection on Low Pressurizer Pressure at 36.4 sec.
76 Feedwater Isolation at 28.9 sec.
76 LowSteamPressureSetpgoitreachedat304sec.
76 Steamline Isolation at M sec.
76 Tube Bundle Uncovery predicted at 195 sec.
76 AFW Isolation assumed at 1800 sec.
76 Amendment 76 May 1, 1989
.