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3 .-TRANSMITTAL OF TECHNICAL REQUIREMENTS MANUAL, REVISION 2 | 3 .-TRANSMITTAL OF TECHNICAL REQUIREMENTS MANUAL, REVISION 2 | ||
'Y qGentlemen: '' | 'Y qGentlemen: '' | ||
e | e | ||
'TV. Electric, the lead applicant, acting for itself and the other applicants: | 'TV. Electric, the lead applicant, acting for itself and the other applicants: | ||
| Line 102: | Line 101: | ||
- Subscribed and sworn to before me, a Notary Public, on this 12TH day of j | - Subscribed and sworn to before me, a Notary Public, on this 12TH day of j | ||
= JANUARY ,.1990. ' | = JANUARY ,.1990. ' | ||
PATR' CIA WILSON jmy Notary Public | PATR' CIA WILSON jmy Notary Public | ||
/v[5 i' m w*wa was o %,i March 16,1993 h.;t-- | /v[5 i' m w*wa was o %,i March 16,1993 h.;t-- | ||
| Line 119: | Line 117: | ||
SER/SSER Impact: No l I | SER/SSER Impact: No l I | ||
0 1' 4 Update the description of the Administrative Control i Process for the Technical Requirements Manual. r Update: ' | 0 1' 4 Update the description of the Administrative Control i Process for the Technical Requirements Manual. r Update: ' | ||
t,larify that the TRM is evaluated per 10CFR50.59 which includes a written safety evaluation, when required. | t,larify that the TRM is evaluated per 10CFR50.59 which includes a written safety evaluation, when required. | ||
TRM Change Request Number: TR89 008.2 i: SER/SSER Impact: No i p | TRM Change Request Number: TR89 008.2 i: SER/SSER Impact: No i p | ||
| Line 163: | Line 160: | ||
y Attachment to TXX*90012 CPSES TRM REVISION 2 jy3 Page 3 of 6 DETA! LED DESCRIPT!0N' ! | y Attachment to TXX*90012 CPSES TRM REVISION 2 jy3 Page 3 of 6 DETA! LED DESCRIPT!0N' ! | ||
.TRM Page . . | .TRM Page . . | ||
(as amended) Group Description ' | (as amended) Group Description ' | ||
TRM Change Request Number: TR 89 007 Related SER Section: 6.2.5: SSER6 6.2.3 SER/SSER Impact: No Table 2.1.1 4 See Sheet No(s):page 2 24 . | TRM Change Request Number: TR 89 007 Related SER Section: 6.2.5: SSER6 6.2.3 SER/SSER Impact: No Table 2.1.1 4 See Sheet No(s):page 2 24 . | ||
| Line 352: | Line 347: | ||
U COMANCHE PEAK - UNIT 1 2-5 REVISION 2 JANUARY 15, 1990 | U COMANCHE PEAK - UNIT 1 2-5 REVISION 2 JANUARY 15, 1990 | ||
g i p l | g i p l I | ||
f' TECHNICAL REQUIREMENT 2.1 (continued) 7 ) | |||
TECHNICAL REQUIREMENT 2.1 (continued) 7 ) | |||
( ) TABLE 2.1.1 (Continued) ! | ( ) TABLE 2.1.1 (Continued) ! | ||
x_/ < | x_/ < | ||
| Line 432: | Line 425: | ||
RC Pump (Loop #3) | RC Pump (Loop #3) | ||
ICS-8368D 50 Seal Injection to N.A. N.A. | ICS-8368D 50 Seal Injection to N.A. N.A. | ||
RC Pump (Loop #4) | RC Pump (Loop #4) 10S 8180 51 Seal Water Return N.A. C and Excess Letdown 101-145 54 Containment Spray N.A. Note 4 2 to Spray Header (Tr. B) l lM 00HANCHE PEAK - UNIT 1 2 17 REVISION 2 JANUARY 15, 1990 ; | ||
10S 8180 51 Seal Water Return N.A. C and Excess Letdown 101-145 54 Containment Spray N.A. Note 4 2 to Spray Header (Tr. B) l lM 00HANCHE PEAK - UNIT 1 2 17 REVISION 2 JANUARY 15, 1990 ; | |||
: i. - 1 i | : i. - 1 i | ||
b p ; | b p ; | ||
| Line 441: | Line 432: | ||
MAXINUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO. REFERENCE NO.* LINE OR SERVICE (Seconds) RE0VIREMENTS j L i | MAXINUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO. REFERENCE NO.* LINE OR SERVICE (Seconds) RE0VIREMENTS j L i | ||
] | ] | ||
: 6. Check Valves (Continued) | : 6. Check Valves (Continued) 1-ICT-142 55 Containment Spray N.A. Note 4 2 l to Spray Header J (Tr. A) , | ||
1-ICT-142 55 Containment Spray N.A. Note 4 2 l to Spray Header J (Tr. A) , | |||
1 101 030 62 Instrument Air N.A. C ] | 1 101 030 62 Instrument Air N.A. C ] | ||
to Containment ; | to Containment ; | ||
| Line 508: | Line 497: | ||
.. q ; | .. q ; | ||
t- | t- | ||
'; i | '; i | ||
: 1 | : 1 | ||
| Line 515: | Line 503: | ||
r- | r- | ||
, y | , y | ||
;. $j FEE 0 WATER ISOLATION VALVE TEMPERATURE I | ;. $j FEE 0 WATER ISOLATION VALVE TEMPERATURE I r | ||
r | |||
[ OPERABILITY CRITERIA Each main feedwater isolation valve shall be greater than or j 3.3 equal to 900F. | [ OPERABILITY CRITERIA Each main feedwater isolation valve shall be greater than or j 3.3 equal to 900F. | ||
p APPLICABILITY: MODES 1. 2 and 3. , | p APPLICABILITY: MODES 1. 2 and 3. , | ||
| Line 528: | Line 513: | ||
L' | L' | ||
: b. Perform an engineering evaluation to determine the effect of l the overpressure on the structural integrity of the main i | : b. Perform an engineering evaluation to determine the effect of l the overpressure on the structural integrity of the main i | ||
/J feedwater isolation valve (s). Determine that the main | /J feedwater isolation valve (s). Determine that the main | ||
' feedwater isolation valve (s) remains acceptable for continued j operations prior to increasing main feedwater pressure above 675 psig. j g | ' feedwater isolation valve (s) remains acceptable for continued j operations prior to increasing main feedwater pressure above 675 psig. j g | ||
| Line 545: | Line 529: | ||
1 l | 1 l | ||
3.3 FEEDWATER ISOLATION VALVE TEMPERATURE ] | 3.3 FEEDWATER ISOLATION VALVE TEMPERATURE ] | ||
p Supplemental impact testing performed on portions of representative l | p Supplemental impact testing performed on portions of representative l samples of the valve' body. neck and bonnet of the feedwater isolation valves (FIV's) yielded results which were not in accordance with the r ASME code requirements for fracture toughness for material (NC 2300) j L based on a minimum service temperature of 400F. The results of the ; | ||
samples of the valve' body. neck and bonnet of the feedwater isolation valves (FIV's) yielded results which were not in accordance with the r ASME code requirements for fracture toughness for material (NC 2300) j L based on a minimum service temperature of 400F. The results of the ; | |||
supplemental testing are discussed in Engineering Report ER DBE ME- J 045. In addition a fracture mechanics analysis is detailed in Calculation 16345 ME(B) 274 R/1 " Resistance of Feedwater Valves to q Brittle Fracture". | supplemental testing are discussed in Engineering Report ER DBE ME- J 045. In addition a fracture mechanics analysis is detailed in Calculation 16345 ME(B) 274 R/1 " Resistance of Feedwater Valves to q Brittle Fracture". | ||
As indicated in the engineering report, the fracture toughness requirements are satisfied with a metal temperature of 900F for the valve body and neck, therefore, these portions will be maintained above this temperature prior to full pressurization of the valves. ; | As indicated in the engineering report, the fracture toughness requirements are satisfied with a metal temperature of 900F for the valve body and neck, therefore, these portions will be maintained above this temperature prior to full pressurization of the valves. ; | ||
| Line 568: | Line 550: | ||
) CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES l | ) CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES l | ||
/ i LIMITING CONDITION FOR OPERATION ) | / i LIMITING CONDITION FOR OPERATION ) | ||
L | L | ||
: l. 3.8.4 All containment penetration conductor overcurrent protective devices shall be OPERABLE. ; | : l. 3.8.4 All containment penetration conductor overcurrent protective devices shall be OPERABLE. ; | ||
| Line 629: | Line 610: | ||
n i | n i | ||
i | i TECHNICAL REQUIREMENT 4.1 (continued) j | ||
TECHNICAL REQUIREMENT 4.1 (continued) j | |||
._: c ! | ._: c ! | ||
-[ p TABLE 4.1.1 (Continued) ] | -[ p TABLE 4.1.1 (Continued) ] | ||
| Line 725: | Line 704: | ||
1 TECHNICAL REQUIREMENT 4.1 (continued) j | 1 TECHNICAL REQUIREMENT 4.1 (continued) j | ||
?f s j | ?f s j | ||
,( ) TABLE 4.1.1 (Continued) f CONTAINMENT PENETRATION CONDUCTOR , | ,( ) TABLE 4.1.1 (Continued) f CONTAINMENT PENETRATION CONDUCTOR , | ||
| Line 747: | Line 725: | ||
- January 15, 1990 | - January 15, 1990 | ||
y | y 1 | ||
TECHNICAL REQUIAWENT 4.1 (continugn l | |||
) IABLE 4.1.1-(Continued) s s CONTAINMENT PENETRATION CONDUCTOR r OVERCURRENT PROTECTIVE DEVICES l DEVICE NUMBER j AND LOCA M l l ; | ) IABLE 4.1.1-(Continued) s s CONTAINMENT PENETRATION CONDUCTOR r OVERCURRENT PROTECTIVE DEVICES l DEVICE NUMBER j AND LOCA M l l ; | ||
[ | [ | ||
| Line 768: | Line 745: | ||
XEC3 3 9, 10 FAL-12020 1 1 | XEC3 3 9, 10 FAL-12020 1 1 | ||
: 11. DRPI Data Cabinet Power Supplies : | : 11. DRPI Data Cabinet Power Supplies : | ||
: a. Primary Breakers 2 2 | : a. Primary Breakers 2 2 | ||
SOUARE D 2 PANELBOARD NO. CKT. NO. BREAKER TYPE 2 1014 1,2 FA 14050A 2 | SOUARE D 2 PANELBOARD NO. CKT. NO. BREAKER TYPE 2 1014 1,2 FA 14050A 2 | ||
| Line 782: | Line 758: | ||
''(._ | ''(._ | ||
s 4 ,/Lsu, 4.1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTION DEVICES ~ , | s 4 ,/Lsu, 4.1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTION DEVICES ~ , | ||
e | e The bases for OPERABILITY and surveillance of these devices arc | ||
The bases for OPERABILITY and surveillance of these devices arc | |||
,;' ; contained in the CPSES Technical Specifications. | ,;' ; contained in the CPSES Technical Specifications. | ||
5 All Class l1E motor operated valves' motor starters are provided with | 5 All Class l1E motor operated valves' motor starters are provided with | ||
| Line 812: | Line 786: | ||
m'r. ; | m'r. ; | ||
,s i e | ,s i e | ||
[ TECHN! CAL' REQUIREMENTS MANUAL. , | [ TECHN! CAL' REQUIREMENTS MANUAL. , | ||
b' ', EFFECTIVE PAGE LISTING P | b' ', EFFECTIVE PAGE LISTING P | ||
Revision as of 15:19, 17 February 2020
| ML20005G553 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 01/15/1990 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-90012, NUDOCS 9001190323 | |
| Download: ML20005G553 (34) | |
Text
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L """ 5 Lo # TXX-90012. Fi e1# 10010'
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Ref. # 10CFR50.36~
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[ nlELECTRIC January 15, 1990-
- ( . ,
- ;:(I W. J. Cahn ! . -
becurwe Vke President -
'U;S. Nuclear Regulatory Commission
- m. Attn:t Document Control Desk p
;h' Washington,fD.C.:20555 -
1 E; a ju LSUDJECT:, COMANCHE PEAK STEAM _ ELECTRIC STATION (CPSES) DOCKET NO. 50-445 V 3 .-TRANSMITTAL OF TECHNICAL REQUIREMENTS MANUAL, REVISION 2
'Y qGentlemen:
e
'TV. Electric, the lead applicant, acting for itself and the other applicants:
1
" t.'r LTexas' Munici al Power: Agency,' and Tex-La Electric Cooperative of Texas, Inc.,
E herewith-'su its Revision. 2-(enclosed) of the CPSES Technical- Requirements J
,, : Manual ~.
L W Encfosed are thsifollowing I documents:
; Technic'al Requirements Manual - 1 signed-(and sworn) original ',x ' Revision 2 and 37 copies A. page;by-page description of the changes is attached. The group number assigns a;1evel1 of significance for each change made to the Technical 1
It1 . Requirements Manual consistent with TU Electric's letter TXX-88467 of-E -JuneJ1,,1988. <Pages which'do not have technical changes but are included in 'f ,
- the' revisioni(because only editorial changes were made on these pages) are not .
discussed l.in'the attachment. L'
, Sincerely, m.
[' William J. Cahill, Jr. [ , y *
,WJH/grp
' Attachments.
. . Enclosure ci Mr. R. D. Martin, Region IV
. Resident Inspectors, CPSES (3)
;A8nusn88@
400 North Ohve Strert LB 81 Dallas, Texas 75201 m
p' '. ,,
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.. Attachment 1-to TXX-90012 : ,
j Page s1? of; 1: i
$4 1
- j
.\. 1 UNITED STATES OF AMERICA
'l NUCLEAR REGULATORY COMMISSION l
'jl!- , In.the Matter of- ) :
~ ) *
. Texas: Utilities Electric Company ) Docket No. 50-445
-) .
- (Comanche Peak Steam Electric )
- Station, Unit 1).-
) !
j r AFFIDAVIT y , William ~J."Cahill,- Jr. being. duly sworn, hereby deposes and says that he is Executive Vice President,. Nuclear of TU Electric, the-lead Applicant' herein; that!he is duly authorized to sign and file with the Nuclear Regulatory r Commission this: revision to its Application and supporting documentation for--
- .0perating License for the captioned facility; that he is familiar with the-content thereof; and that the matters set forth therein are true and correct- r to the: best of his' knowledge, information and belief. ,
r
/Aa / ,
0 - - William J. Cahif4, Jr. Executive Vice Presid i
- l g
+
STATE;0FLTEXAS ). COUNTY 0F SOMERVELL
- Subscribed and sworn to before me, a Notary Public, on this 12TH day of j
= JANUARY ,.1990. '
PATR' CIA WILSON jmy Notary Public
/v[5 i' m w*wa was o %,i March 16,1993 h.;t--
-1 d
1 1 ___L-. __m__ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ ,
tAttachment to TXX*90012
.Page 1 Cf.6. CPSES TRM REVISION 2
"- DETAILED DESCRIPTION is TIBI' Page ins.. amended) ACmut pescription j,'
~~
01 4 Update the description of the Administrative Control Process for the Technical Requirements Manual. Update: NEO procedures are now being issued by individual [ departments as sitewide procedures. TRM Change Request Number: TR89 008.1 : SER/SSER Impact: No l I 0 1' 4 Update the description of the Administrative Control i Process for the Technical Requirements Manual. r Update: ' t,larify that the TRM is evaluated per 10CFR50.59 which includes a written safety evaluation, when required. TRM Change Request Number: TR89 008.2 i: SER/SSER Impact: No i p L 01,2 4 Update the description of the Administrative Control i Process for the Technical Requirements Manual. , L Update: ' Change the tense from future to present to accurately reflect the status of the Administrative Control i Process, j
- - TRM Change Request Number
- TR89 008.3 l SEA /SSER Impact: No ,
[ Tabic 2.1.1 4 See Sheet No(s):page 2 05 Corrects the leak testing requirements for the valves i associated with items 43 and 44 to be consistent with h FSAR Table 6.2.4-2. l Correction: + These valves (S! to hot leg loops 1. 2. 3 and 4) were l previously indicated as Type C tested (either air test i or water test per Note 3 in FSAR Table 6.2.4 2). Per the justification provided in Note 12 of FSAR Table 6.2.4 2 these valves are no longer required to be tested. j TRM Change Request Number: TR-89 007 I Related SER Section: 6.2.5: SSER6 6.2.3 CER/SSER 1mpact: No ' l Table 2.1.1 4 See Sheet No(s):page 2 05 ; i Corrects the leak testing requirements for the valves ~ associated with item 45 to be consistent with FSAR Table 6.2.4-2. Correction: These val <es (S! to cold leg loops 1. 2. 3 and 4) were l
. ~ _ _ __ _ _. _ _
Attachment to TXXo90012 Page 2 of 6 CPSES TRM REVISION 2 DETAILED DESCRIPTION
- x. ;
, ; TAM, Page (as amended) Groun Descristi_gn previously to be Type C tested (either with air or with k water Jer Note 3 in FSAR Table 6.2.4 2). Per the !
justification provided in Note 13 of FSAR Table 6.2.4 2 i these valves are no longer required to be tested. TRM Change Request Number: TR 89 007 3 Related SER Section: 6.2.5: SSER6 6.2.3 i SER/SSER 1mpact: No Table 2.1.1 4 See Sheet No(s):page 2-14 0 i
' Corrects the leak testing requirements for the valves :
associated with items 35 and 36 to be consistent with [ FSAR Table 6.2.4 2. Corrections ! These valves (RHR to cold leg loops 1, 2, 3 and 4) were previously not Type C tested per Note 4 in FSAR Table 6.2.4-2. These valves are now all Type C tested.. either with air or, in the event that a water seal can-be demonstrated to exist post accident for at least 30' days, a Type C water test is performed at a water . pressure not less than 1.1 Pa per Note 3 of FSAR Table 6.2.4 2. l TRM Change Request Number: TR 89 007 Related SER Section: 6. 2.> 5 : SSER6 6.2.3 SER/SSER Impact: No Table 2.1.1 4 See Sheet No(s):page 2 15 Corrections.
- Corrects the leak testing requirements for the valve associated with items 54 and 55 to be consistent with Note 3 in FSAP. Table 6.2.4-2.
TRM Change Request Number: TR 89 007 Related SER Section: 6.2.5 SSER6 6.2.3 ' SER/SSER 1mpact: No Table 2.1.1 4 See Sheet No(s):page 2 15 Correction: Corrects the leak testing requirements for the valves ' associated with item 63 to be consistent with Note 3 in < FSAR Table 6.2.4-2. TRM Change Request Number: TR 89 007 Related SER Section: 6.2.5: SSER6 r,,2,3 SER/SSER Impact: No ,
. Table 2.1.1 4 See Sheet No(s):page 2-17 and 2-18 Correction:
Corrects the leak testing requirements for the valve associated with items 54 and 55 to be consistent with . Note 3 in FSAR Table 6.2.4 2.
y Attachment to TXX*90012 CPSES TRM REVISION 2 jy3 Page 3 of 6 DETA! LED DESCRIPT!0N' !
.TRM Page . .
(as amended) Group Description ' TRM Change Request Number: TR 89 007 Related SER Section: 6.2.5: SSER6 6.2.3 SER/SSER Impact: No Table 2.1.1 4 See Sheet No(s):page 2 24 . Editorials. Adds Note 4 to cross reference the applicable Technical Specification Sp.'veillance Requirement which includes Note 3 of FSAR Table 6.2.4-2. TRM Change Request Number: TR 89 007 p Related SER Section: 6.2.5; SSER6 6.2.3 - SER/SSER 1mpact: No 3 12, 13 2 Adds requirement for feedwater isolation valve to be greater than or equal to 90 degrees F in Modes 1, 2 and 3. i Revision: A technical requirement has been added to ensure that , the temperature of the feedwater isolation valves is greater than or equal to 90 degrees F in Modes 1, 2
- and 3. Main feedwater isolation valve temperature will-be determined once per 12 hours in Modes 2 and 3 (process fluid temperature ensures that the valve
,~
temperature is greater than 90 degrees F in Mode 1). This ensures that the valve body temperature will be i high enough to satisfy fracture toughness requirements for the valve body and neck of the feedwater isolation valves. P This change is consistent with Amendment 70 to the FSAR and has been evaluated under the TU Electric 10CFRSO.59 procedure per TXX 89718. dated September 28, 1989. TRM Change Request Number: TR 89 010 i Related SER Section: 10.3.3 , SER/SSER Imptet: Yes The NRC is in the process of reviewing the design as described in FSAR Amendment 78. Table 4.1.1 3 See Sheet No(s):4-09 HCC 1EB1 2 compartment 12H breaker is now G.E. type THED.
- Revision: 5 In accordance with approved design chanca. HCC IEB1 2 compartment 12H breaker is changed from G.E. type THFK to THED to account for cable sizing. '
TRH Change Request Number: TR 90 01.2 Related SER Section: 8.4.1 SER/SSER Impact: No
' Attachment to TXX*90012 CPSES TRM REVISION 2 ',
-P898 4 'I 0~ DETAILED DESCRIPTION !
?
O TIM Page (as amended) Group Descrintion Table 4.1.1 3 See Sheet No(s):4 14- i Group C Pressurizer Heaters protection changed from , panel. incoming breaker and feeder breakers to two feeder breakers in series. Revision: ' The containment penetration conductor overcurrent ! protection devices for the Group C Pressurizer Heaters ' is changed from the panel incoming breaker and feeder. t breakers to two feeder breakers in series. The G.E. Type THED breaker was installed in series with the - existing feeder breaker. This change is consistent with.and follows up Amendment 75 to the FSAR which has been reviewed by the NRC. - , TRM Change Request Number: TR 90 01.3 Related.SER Section: 8.4.1 ; SER/SSER lapact: No Table 4.1.1 3 See Sheet No(s):4 15 Containment electrical penetration primary protection for the containment motor space heaters fed from 480V - switchgear is changed to a fuse. ' Revisions- l Fuses have been installed in place of breakers for the primary protection for the containment motor space . heaters fed from 480V switchgear to better coordinate , with the penetration thermal characteristics.. Backup protection remains circuit breakers. This change is ' consistent with Amendment 78 to the FSAR (Section 8.3). : TRM Change Request Number: TR 90 01.1 ' Related SER Section: 8.4.1 SER/SSER Impact: Yes The fuse provides an acceptable.means of circuit protection. This circuit was not described in the original SER, however, this does change material reviewed by the NRC-for the draft SSER. Table 4.1.1 3 See Sheet No(s):4-16 Panelboard 1E01-1 Circuit No. 17 now uses a fuse for backup containment penetration overcurrent protection. Revision: Per approved design change. Panelboard IE01-1 Circuit No. 17 now uses a fuse for backup containment penetra-tion overcurrent protection. Sinc'e the surveillance only applies to breakers this item is deleted from the table. This is consistent with the protection discuss-ed in the FSAR and reviewed for the SSER. TRM Change Request Number: TR 90 01.4 Related SER Section: 8.4.1 SER/SSER Impact: No
' }
-Attachment to TXX-90012 Page 5 of 6 CPSES TRM REVISION 2' .
DETA! LED DESCRIPTION [ t l o ; TIgl Page ! (as amended) Group Descrintion l- Table 4.1.1 3 See Sheet No(s):4 17 l ; i Containment electrical penetration protection for the ~ l Fire Protection / Detection System and Containment Door l Position Limit Switches has been changed from a breaker ' to'a-fuse and therefore is deleted from the surveill- t ance. Revisions n Since the breakers for these two applications were not
- readily accessible for performance of this surveillance- '
' fuses were installed to provide the required protective + function. The surveillance only applies to breakers, . so these two items are deleted from Table 4.1.1 since : they no longer employ breakers for their protective r i devices. This change is consistent with Amendment 78 + to the FSAR (Section 8.3). . TRM Change Request Number: TR 89 009 ; Related SER Section: 8.4.1 4 SER/SSER Impact: Yes ! The fuse provides an acceptable means of circuit , protection and this circuit was not described in the original SER, however, this does change material i
}
reviewed by the NRC in previous FSAR Amendments for the draft SER. Table 4.1,1 3 See Sheet No(s):4 17 , Pane 1 boards IEC1 Circuit No. 4 and IEC2 Circuit No. 4 , now use fuses for backup containment penetration over-l current protection. Revision:
~
Per approved design changes, Pane 1 boards 1EC1 Circuit ' No. 4 and 1EC2 Circuit No. 4 now use fuses for backup containment penetration overcurrent protection. Since ! the surveillance only applies to breakers these items , are deleted from the table. This is consistent with , the protection discussed in the FSAR and reviewed for the SSER. I TRM Change Request Number: TR 90 01.5 Related SER Section: 8.4.1 SER/SSER impact: No . Table 4.1.1 3 See Sheet No(s):4-17 ORPI Data Cabinet Power Supplies now use breakers for primary protection. Revision:
- The containment penetration conductor overcurrent protection devices for the DRPI Data Cabinet Power Supplies now use the main panel circuit breakers for backup protection and feeder breakers for primary protection (instead of fuses). This is consistent with and follows up Amendment 68 to the FSAR which has been reviewed by the NRC.
(" ', ". ,, ..
. .. .\
Jj7 l Attachment to:TXXo90012 CPSES TRN. REVISION 2 E M' 0 'I O DETA! LED DESCRIPTION- 1
, i ,
]
w l TM Page .i (as amended) Stegg Descripti g l q, TRM Change Request Number: TR-90 01.6 I Related SER Section: 8.4.1 ; SER/SSER Impact: No
).
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I i j i t' 'i- CPSES/TRM l t
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COMANCHE PEAK STEAM ELECTRIC STATION I ' TECHNICAL REQUIREMENTS MANUAL i INSTRUCTION SHEET l
- i. l 1
The following instructional information and check list is being furnished to 1 help insert Revision 2 into the Comanche Peak Steam Electric Station TRM, A description of.this revision is provided in TXX 90012. dated January 15, 1990. Discard the old sheets and insert the new sheets, as listed below. Keep these
~
instruction sheets in the front of the Effective Page Listing to serve as a . o record of changes. Insert the Effective Page Listing at the end of the l Technical Requirements Manual. l l Remove' Insert
> t.
4 01 01 02 02 2-5 25 2 14 2-14 2 15 2-15 2-17 2-17 : m 2 18 2-18 l 2-24 2-24
. (V) 3-5 35
... 3-12 '
.. 3 13 4-2 4-2 4-3 4-3 4-4 4-4 49 4-9 4 12 4 12 4 14 thru 4-14 thru 4-19 (Both) 4 18
-- EPL 1
- EPL-2 Page 1 of 1
? h, , TECHNICAL REQUIREMENTS MANUAL
, ' ^ 'v. TABLE OF CONTENTS
\) TECHNICAL REQUIREMENT NUMBER SYSTEM / TITLE (Related Tech Spec if required) 1.0 Administrative Controls 1.1 (3/4.3.1) Reactor Trip Response Time t
-1
[ll: 1.2 (3/4.3.2) ESF Actuation _ Response Time !? i 1.3 Moveable Incore Detection System g 1.4 Seismic Instruments 1.6 Loose Parts Detection System 2.1 (3/4.6.3) Containment Isolation Valves 3.1 (3/4.7.9) Snubbers 3.2 Station Service Water System 3.3 Feedwater Isolation Valve
, _; Temperature
\~ / 4.1 (3/4.8.4) Containment. Penetration '1 Conductor Overcurrent l Protection Devices '
^l l
2 t L i COMANCHE PEAK - UNIT 1 i January 15. 1990
t TECHNICAL REQUIREMENTS MANUAL
'( v ) (TRM)
Description of the Administrative Control Process INTRODUCTION CPSES.has relocated certain information from the Technical 2 L Specifications to a separate controlled document based on the NUMARC Technical Specification Improvement Program, the Westinghouse Owners Group MERITS Program, and the Commission's Interim Policy Statement for improvement of Technical Specifications for nuclear power plants ! (52 FR 3788_ of February 6,1987). This information is new contained in a separate document to be called the CPSES Technica Requirements Manual (TRM). The following is a description of the administrative program for control, distribution, updating, and amending the information contained in the TRM. DOCUMENT CONTROL The TRM is considered a licensing basis document and as such, overall 2 control of the document is addressed by the site wide procedures for licensing document control.
,. . DOCUMENT DISTRIBUTION
(_-) The TRM is considered a controlled document and distribution is controlled by the Nuclear Licensing Department. Licensing specifies 2 (by copy number) the proper distribution for the TRM. Distribution 3"cludes those personnel / locations which receive the CPSES Technical
!;ecifications as well as any other groups which need access to the information contained in the TRM.
CHANGES / DELETIONS TO THE TRM Changes to the TRM are controlled by the procedure on licensing 2 document change control. This procedure addresses the administrative requirements necessary to change / amend CPSES licensing documents (e g., Fire Protection Report. Offsite Dose Calculation Manual, etc.). For changes to the TRM. the procedure requires initiation of a !' Licensing Document Change Request (LDCR). The LDCR is the mechanism whereby changes are tracked to ensure that appropriate reviews, approvals, and signatures are obtained. TRM changes are evaluated per 2 4 10CFR50.59. TRM changes require a review by SORC and the approval of the Vice President, Nuclear Operations.
.lJ COMANCHE PEAK - UNIT 1 0-1 Revision 2 January 15, 1990
i l
.E1 ANT CHANGES THAT-MAY EFFECT THE TRM
.( )
. Changes made at CPSES have the potential to affect (or be affected by) 2 che TRM. These include items such as design modifications, procedure changes..other licensing document changes,.etc. The TRM has been ;
identified as a-CPSES licensing basis document by the.10CFR50.59 Program. The 10CFR50.59 Program is based on the latest NUMARC 2 Guidelines for 50.59 evaluations. This. program requires that the TRM' i be considered in a manner similar to the FSAR when screening changes : to determine if an unreviewed safety question might.be involved, ! DISTRIBUTION OF TRM CHANGES / DELETIONS , l Changes to the TRM will be issued on a replacement page basis to controlled document holders promptly following approval of the change. , _ REPORT OF TRM- CHANGES / DELETIONS 10 THE NRC Changes to the TRM will be reported to the NRC annually as part of the SAR update. Related safety evaluations will be reported as part of the 50.59 annual report. Proposed'TRM changes that are determined to constitute an unreviewed safety question (as defined by 10CFR50.59(a)(2)) will either not be made'or will be submitted to the NRC for prior review and approval. [ \. O COMANCHE PEAK - UNIT 1 0-2 Revision 2 January 15. 1990
o-TECHNICAL REQUIREMENT 2.1 (continued) (s ) . TABLE 2.1.1 (Continued)
,/ -
CONTAINMENT ISOLATION VALVES MAXIMUM , ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST
-VALVE NO. REFERENCE NO.* LINE OR SERVICE (Seconds) REQUIREMENTS
- 1. Phase "A" Isolation Valves (Continued) 1-8881 43 Si to RC System 10 N.A. 2 Hot Loops #2 & '
#3 Test Line 1-8824 44 SI to RC System 10 N.A. 2 Hot Leg Loops #1 &
#4 Test Line 1 8823 45 SI to RC System 10 N.A. 2 Cold Leg Loops #1, 3
#2 #3 & #4 Test Line 1 8100 51 Seal Water Return 10 C and Excess Letdown ,
is 1 8112 51 Seal Water Return 10 C and Excess Letdown 1-7136 52 RCOT Heat Exchanger 10 C to Waste Hold Up Tank LCV-1003 52 RCDT Heat Exchanger 10 C to Waste Hold Up Tank L 1HV-5365 60 Demineralized Water 5 C : Supply 1HV 5366 60 Demineralized Water 5 C
- . Supply l
L IHV-5157 61 Containment Sump 5 C l Pump Discharge 1-l 1HV-5158 61 Containment 5 C Sump Pump
<' 1HV-3487 62 Instrument Air 5 C to Containment O
U COMANCHE PEAK - UNIT 1 2-5 REVISION 2 JANUARY 15, 1990
g i p l I f' TECHNICAL REQUIREMENT 2.1 (continued) 7 ) ( ) TABLE 2.1.1 (Continued) ! x_/ < CONTAINMENT ISOLATION VALVES 1 MAXIMUM ISOLATION NOTES AND ) FSAR TABLE TIME LEAK TEST -l VALVE NO. REFERENCE NO.* LINE OR SERVICE (Seconds) REQUIREMENTS .j
- 5. Power-Operated Isolation Valves (Continued) i 1HV 2494A 26a Auxiliary Feedwater' N.A. N.A.
to Steam Generator
#4 1HV-24948 26a Auxiliary Feedwater N.A. N.A.
to Steam Generator i
#4 1 8701B 33 RHR From Hot Leg N.A. C Loop #4 1-8701A 34 RHR From Hot Leg N.A. C l Loop #1 ;
1 8809A 35 RHR to Cold Leg N.A. Note 4 2
. /)^N
- j. \. Loops #1 and #2 1-8809B 36 RHR to Cold Leg N.A. Note 4 2 ,
Loops #3 and #4 1 8801A 42 Safety injection N.A. N.A. to Cold Leg Loops
#1. #2. #3. and #4 1-8801B 42 Safety Injection N.A. N.A.
to Cold Leg Loops
#1. #2. #3. and #4 1-8802A 43 SI Injection to N.A. N.A.
RCS Hot Leg Loops
#2 and #3 1 8802B 44 01 Injection to N.A. N.A.
RCS Hot Leg Loops
#1 and #4 1-8835 45 SI Injection to N.A. N.A.
RCS Cold Leg Loops
#1. #2. #3. and #4 4
/~'N .
COMANCHE PEAK - UNIT 1 2-14 REVISION 2 JANUARY 15. 1990
i s }1 [ 6: TECHNICAL REQUIREMENT 2.1._fcontingadl
, T' j-) ) TABLE 2.1.1 (Continggd1 i
CONTAINMENT ISOLATION VALVES MAXINOM ISOLATION NOTES AND FSAR. TABLE TIME LEAK TEST . VALVE NO. REFERENCE NO.* LINE OR SERVICE LSeconds) REQUIREMENTS
- 5. Power Operated Isolation Valves (Continued) 1 8351A 47 Seal Injection to N.A. N.A.
RC Pump (Loop #1) 1-8351B 48 Seal Injection to N.A. N.A. RC Pump (Loop #2) t 1 8351C 49 Seal Injection to N.A. N.A. ' RC Pump (Loop #3) 1 83510 50 Seal Injection to N.A. N.A. .l RC Pump.(Loop #4) > IHV 4777 54 Containment Spray N.A. Note 4 2 s 7 s to Spray Header ' 1 0 (Train B)
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1HV 4776 55 Containment Spray N.A. Note 4 2 to Spray Header (Train A) ; 1-8840 63 RHR to Hot Leg N.A. Note 4 l2 , Loops f2 and #3 1 1-8811A 125 Containment N.A. N.A. , Re: ire. Sump to RHR Pumps (Train A' . 1-8811B 126 Containment N.A. N.A. Recire Sump to RHR Pumps (Train B) l 1HV-4782 127 Containment N.A. N.A. Recirc. to Spray Pumps (Train A) , 1HV-4783 128 Containment N.A. N.A. Recirc. to Spray j/~') Pumps (Train B) '
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COMANCHE PEAK UNIT 1 2-15 REVISION 2 JANUARY 15. 1990
I i i i \ f ' TECHNICAL REQUIREMENT 2.1 (continued) ! -( y_ TABLE 2.1.1 (Conti_0_y341 i '\ j' i CONTAINMENT ISOLATION VALVES l MAXIMUM ! ISOLATION NOTES AND , FSAR TABLE TIME LEAK TEST yALVE NO. . REFERENCE NO.* LINE OR SERVICE (Seconds) REQUIREMENTS { I
- 6. Check Valves (Continued) l l
151 8819B 45 SI to RC System N.A. N.A. l Cold Leg Loop #2 151 8819C~ 45 Si to RC System N.A. N.A. Cold Leg Loop #3 151 8819D 45 SI to RC System N . A ., N.A. Cold Leg loop #4 1-8381 46 Charging Line to N.A. C Regenerative Heat .I Exchanger ! 1CS 8368A 47 Seal Injection to H.A. N.A. l
,es RC Pump (Loop #1) 10S 83688 48 Seal Injection to N.A. N.A.
RC Pump (Loop #2) ICS-8368C 49 Seal Injection to N.A. N.A. RC Pump (Loop #3) ICS-8368D 50 Seal Injection to N.A. N.A. RC Pump (Loop #4) 10S 8180 51 Seal Water Return N.A. C and Excess Letdown 101-145 54 Containment Spray N.A. Note 4 2 to Spray Header (Tr. B) l lM 00HANCHE PEAK - UNIT 1 2 17 REVISION 2 JANUARY 15, 1990 ;
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b p ; l TECHNICAL REQUIREMENT 2.1 (continued) I
!. j TABLE 2.1.1 (Conti%'tsl l CONTAINMENT ISOLATION VALVES L
MAXINUM ISOLATION NOTES AND FSAR TABLE TIME LEAK TEST VALVE NO. REFERENCE NO.* LINE OR SERVICE (Seconds) RE0VIREMENTS j L i
]
- 6. Check Valves (Continued) 1-ICT-142 55 Containment Spray N.A. Note 4 2 l to Spray Header J (Tr. A) ,
1 101 030 62 Instrument Air N.A. C ] to Containment ; 1-8841A 63 RHR to Hot Leg N.A. N.A. , Loop #2 l l 1 8841B 63 RHR to Hot Leg N.A. N.A. Loop #3 J 151-8968 104 N2 Supply to N.A. C l ,r] Accumulators ICA 016 113 Service Air to N.A. C l Containment 100-629 117 CC Return From N.A. C RCP's Motors 100 713 118 CC Supply to RCP's N.A. C Motors + 100 831 119 CC Return From N.A. C RCP's Thermal Barrier 1CH 024 120 Chilled Water N.A. C Supply to Contain- , ment Coolers
/3 COMANCHE PEAK UNIT 1 2-18 REVISION 2 JANUARY 15. 1990
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[. TECHNICAL REQUIREMENT 2.1 (continued) l t Ixs .-) ' TABLE 2.1.1 (Continued) 1 i ' TABLE NOTATIONS 1 l
- Identification code for containment penetration and associated i'
. isolation valves in FSAR Tables 6.2.4 1, 6.2.4-2, and 6.2.4-3.
# May be' opened on an intermittent basis under administrative 1
[ control. 1 g The table does not list local vent, drain and test connections as they j L ere a special class of containment isolation valves and are locked i closed and capped to meet containment isolation criteria when located p. within the penetration boundary. Note 1: All four MSIV bypass valves are locked closed in Mode 1. ) During Mode 2, 3..and 4 one MSIV bypass valve may be opened ! provided the other three.MSIV bypass valves are locked closed and their associated MSIVs are closed. ) i Note 2: These valves require steam to be tested and are thus not .j required to be tested until the plant is in MODE 3. , I Note =3: These valves are included for table completeness, the
. requirements of Specification 3.6.3 do not apply. Instead, i , f) the requirements of Specification 3.7.1.1, 3.7.1.5 and j V- 3.7.1.6 apply for main steam safety valves, mainsteam .j isolation valves, and feedwater isolation valves. -1 respectively. ,
Note 4: These valves are leak tested in accordance with Technical 2 1 Specification Surveillance Requirement 4.6.1.2. BASES 1 2.1 CONTAINMENT ISOLATION VALVES 1 The OPERABILITY of the containment isolation valves ensures that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment and is consistent with the requirements of General Design Criteria 54 through 57 of 10CFR50, Appendix A. Containment isolation within the time limits specified for those isolation valves designed to close automatically ensures
. that the release of radioactive material to the environment will be consistent with the assumptions used in the analyses for a LOCA.
l l O v COMANCHE PEAK - UNIT 1 2-24 REVISION 2 JANUARY 15, 1990
[ i-o o , , TECHNICAL REQUIREMENT 3.1 (continuagl I
+.s
)' SNUBBERS 1
IESTS/ INSPECTIONS (Continued) I L e. Functional Tests During the first refueling shutdown and at least once per 18 3 months thereafter during shutdown, a representative sample of 1 snubbers of each type shall be tested using one of the following ; sample plans. The sample plan for each type shall be selected !L prior to the test period and cannot be changed during the test
- l. period. The NRC Regional Administrator shall be notified in l writing _of;the sample plan selected for each snubber type prior to q the test period or the sample plan used in the prior test period ,
shall be implemented: l
- 1) At least 10% of the total of each type of snubber shall be 1 functionally tested either in place or in a bench test. For j each snubber of a type that does not meet the functional test ]
acceptance criteria of Test / Inspection TR3.lf, an additional ; 10% of that type of snubber shall be functionally tested until no more failures are found or until all snubbers of that type have been functionally tested; or j g i 2) A representative sample of each type of snubber shall be L functionally tested in accordance with Figure 3.1 1. "C" is the total number of snubbers of a type found not meeting the acceptance requirements of Test / Inspection TR3.lf. The 1 cumulative number of snubbers of a type tested is denoted by "N". At the end of each day's testing, the new values of "N" and "C" (previous day's total plus current day's increments) i shall be plotted on Figure 3.1-1. If at any time the point plotted falls in the " Reject" region, all snubbers of that - type shall be functionally tested. If at any time.the point plotted falls in the " Accept" region, testing of snubbers of ' that. type may be terminated. When the point plotted lies in ' the " Continue Testing" region, additional snubbers of that type shall be tested until the point falls in the " Accept" - region or the " Reject" region, or all the snubbers of that type have been tested; or COMANCHE PEAK - UNIT 1 3-5 ' January 15, 1990
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& t 7
IECENICAL REQUIREMENT 3.3 ; r-
, y ;. $j FEE 0 WATER ISOLATION VALVE TEMPERATURE I r
[ OPERABILITY CRITERIA Each main feedwater isolation valve shall be greater than or j 3.3 equal to 900F. p APPLICABILITY: MODES 1. 2 and 3. , COMPENSATORY MEASURES: i With one or more main feedwater isolation valves less than 900F:
- a. Reduce the main feedwater pressure to less than or equal to ;
=
675 psig within 30 minutes or be in HOT STANDBY within the next E hours and in HOT SHUTDOWN within the following 6 hours. ! L'
- b. Perform an engineering evaluation to determine the effect of l the overpressure on the structural integrity of the main i
/J feedwater isolation valve (s). Determine that the main ' feedwater isolation valve (s) remains acceptable for continued j operations prior to increasing main feedwater pressure above 675 psig. j g H TESTS / INSPECTIONS j TR3.3- The main feedwater isolation valves shall be determined to be ' greater than or equal to 900F at least once per 12 hours while in MODES 2 or 3. Readings shall be taken using the following instruments: 1-TI-2152-1, 1 TI-2152 2, 1-TI-2152 3 and 1-TI-2152 4. If any of these instruments are inoperable, a surface pyrometer may be used to determine valve temperature, t
- ,f~O COMANCHE PEAK - UNIT 1 3-12 Revision 2 January 15, 1990
n t I s ! [[
.TECHN.lCAL REQUIREMENT 3'3 (Continued)
( ) BASES c v ( 1 l 3.3 FEEDWATER ISOLATION VALVE TEMPERATURE ] p Supplemental impact testing performed on portions of representative l samples of the valve' body. neck and bonnet of the feedwater isolation valves (FIV's) yielded results which were not in accordance with the r ASME code requirements for fracture toughness for material (NC 2300) j L based on a minimum service temperature of 400F. The results of the ; supplemental testing are discussed in Engineering Report ER DBE ME- J 045. In addition a fracture mechanics analysis is detailed in Calculation 16345 ME(B) 274 R/1 " Resistance of Feedwater Valves to q Brittle Fracture". As indicated in the engineering report, the fracture toughness requirements are satisfied with a metal temperature of 900F for the valve body and neck, therefore, these portions will be maintained above this temperature prior to full pressurization of the valves. ; The valve bonnet fracture toughness has been demonstrated by the I fracture analysis calculation in conjunction with a Volumetric Non-Destructive Exam which determined that there are no significant ! material flaws which could lead to fracture propagation. > As a result of the conclusions drawn in Engineering Report ER DBE ME-045, it is necessary that minimum temperature limitations be imposed j (4V)_ upon Feedwater Isolation Valves IHV-2134, 2135, -2136 and 2137, As stated in DBE ME 203 Section 4.3.7 " Operator interface requirements", the feedwater isolation valves must be verified to be above 900F 1 prior to entering MODE 3. RCS T cvg ,>. 3500F. This corresponds to a pressurization at the valve of approximately 140-150 psig. The 4 maximum pressurization during cold conditions (valve temperature l
< 900F) should be limited to no more than 20% of the valve hydrostatic test pressure (3375 psig x 20% - 675 psig) which exceeds the. condensate pump dead head discharge pressure (Ref. ER-DBE ME-045).
During plant start up, it is possible to cold pressurize the valves from the condensate pumps / feed pumps or from back pressurization from I the Steam Generators. Imposing the MODE 3 limitation will prevent the back pressurization from the generators, 1 Cold pressurization from the condensate pumps is normally prevented due to the manual isolation valves upstream of each FIV being closed j anytime the feedwater headers are pressurized during long cycle condensate full flow flushing operation or condensate pump minimum flow operation. Steam turbine driven feed pumps are started during HDDE 2 when sufficient steam is available for pump operation. Pressurization of the FIV from the Main Feed Pumps will therefore occur only after
/ MODE 3 with the metal temperature of the FIV's being at or above
(]) 900F. COMANCHE PEAK - UNIT 1 3-13 Revision 2 January 15, 1990
m j i
)
I )l/A.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES ! l
) CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES l
/ i LIMITING CONDITION FOR OPERATION )
L
- l. 3.8.4 All containment penetration conductor overcurrent protective devices shall be OPERABLE. ;
I APPLICABIllH: MODES 1. 2, 3, and 4. ACllE: I l With one or more of the containment penetration conductor overcurrent protective device (s) inoperable: j
- a. Restore the protective device to OPERABLE status or:
- 1. Deenergize the circuit (s) by racking out, locking open, or l removing the inoperable protective device ADA !
tripping / removing the associated protective device within ) 72 hours, declare the affected system or component 1 inoperable, and verify the inoperable protective device racked out, locked open, or removed at least once per 31 1 days thereafter; the provisions of Specification 3.0.4 ere ! not applicable to overcurrent protective devices in i O circuits which have their associated protective device () tripped / removed and their inoperable protective device j racked out, locked open, or removed; or I 1
- 2. Deenergize the circuit (s) by tripping / removing the associated protective device At racking out, locking open. l or removing the inoperable protective device within 72 hours, declare the affecud system or component inoperable, and verify h i associated protective device to be tripped / removed or p inoperable protective device racked out, locked open, or removed at least once per 7 days thereafter; the provisions of Specification 3.0.4 are not applicable to overcurrent devices in circuits which have their associated protective device tripped / removed or their inoperable protective device racked out, locked !
open, or removed; or
- b. Be in at least HOT STANDBY within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. -
p. t V COMANCHE PEAK - UNIT 1 4-2 January 15, 1990 l l
If o g ] e ; { \ l
', IL{CTRICAL EQUIPMENT PROTECTIVE DEVICES
/ T
! SURVEILLANCE REQUIREMENTS !
i 4.8.4 The containment penetration conductor overcurrent protective i devices shall be demonstrated OPERABLE:
- a. At least once per 18 months:
- 1. By verifying that the medium voltage 6.9 kV and low voltage 480V switchgear circuit breakers are OPERABLE by selecting, on a rotating basis, at least 10% of the circuit breakers of each current rating and performing the following: ,
1 a) A CHANNEL CALIBRATION of the associated protective relays, i b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and associated circuit breakers and control circuits function as designed, and , c) For each circuit breaker found inoperable during these i functional tests, one or an additional representative sample of at least 10% of all the circuit breakers of the inoperable type shall also be functionally tested until no
<~'s more failures are found or all circuit breakers of that type have been functionally tested;
() ,
- 2. By selecting and functionally testing a representative sample of at least 10% of each type of 480V molded case >
circuit breakers and lower voltage circuit breakers. Circuit breakers selected for functional testing shall be selected on a rotating basis, Testing of these circuit breakers shall consist of injecting a current with a value
- equal to 300% of the pickup of the long time delay trip ;
element and 150% of the pickup of the short time delay trip ' element, and verifying that the circuit breaker operates within the time delay band width for that current specified by the manufacturer. The instantaneous element shall be tested by injecting a current equal to 120% of the pickup value of the element and verifying that the circuit breaker trips instantaneously with no intentional time delay. Hol w) case circuit breaker testing shall also follow this proteture except that generally no more than two trip elements, time delay and instantaneous, will be involved. COMANCHE PEAK - UNIT 1 43 January 15, 1990
i k I ELECTRICAL EQUIPMENT PROTECTIVE DEVICES j 1 I _) EURVEILLANCE REQUIREMENTS (Continued) i k' -
- The instantaneous element for molded case circuit breakers I L shall be tested by injecting a current for a frame size of j 250 amps or less with tolerances of +40%, 25% and a frame ]
, size of 400 amps or greater of 125% and verifying that the j circuit breaker trips instantaneously with no apparent i time delay. Circuit breakers found inoperable'during i i, functional testing shall be restored to OPERABLE status l prior to resuming operation. For each circuit breaker ;
found inoperable during these functional tests, an I additional representative sample of a least 10% of all the j circuit breakers of the inoperable type shall also be I functionally tested until no more failures are found or q all circuit breakers of that type have been functionally l tested; and
- b. At least once per 60 months by subjecting each circuit breaker to an inspection and preventive maintenance in accordance with I procedures prepared in conjunction with its manufacturer's l recommendations.
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N, COMANCHE PEAK - UNIT 1 4-4 January 15, 1990
n i i TECHNICAL REQUIREMENT 4.1 (continued) j
._: c ! -[ p TABLE 4.1.1 (Continued) ]
CONTAINMENT PENETRATION CONDUCTOR j OVERCURRENT PROTECTIVE DEVICES l DEVICE NUMBER- i
- ~ AND LOCATION j i
- 3. 480 from Motor Control Centers (Continued) 1 i :
MCC IEB1-2 G.E. ! COMPT. NO. BKR. TYPE SYSTEM POWERED h 4G THED Motor Operated Valve 1 TV 4691 < [ 4M THED Motor Operated Valve 1-TV 4693 l 3F THED Containment Drain Tank Pump 03 ; 9H THED Reactor Cavity Sump Pump-01 i i_ 9M THED Reactor Cavity Sump Pump-02 l !J 7H THED Containment Sump #1 Pump-01 7M THED Containment Sump #1 Pump 02 , 6H 1HED RCP #11 Motor Space Heater-01 1 6M THED RCP #13 Motor Space Heater 03 88 THED Incore Detector Drive "A" j 80 THED Incore Detector Drive "B" 1 7B THED Incore Detector Drive "F" 3B THED Stud Tensioner Hoist Outlet-01
. p% - -1' 70 THED Hydraulie Deck Lift 01 1 4D THED Reactor Coolant Pump Motor .i Hoist Receptacle 42 ]
BH THED AC Pipe Penetration Cooling l Unit 01 8M THED RC Pipe Penetration Cooling j Unit 02 ' SH THED RCP #11011 Lif t Pump-01 l SM THED RCP #13 011 Lif t Pump 03 " 10B THED Preaccess Filter Train Package . Receptacle 17 SB THED Containment Ltg. XFMR 14 (PNL C3) 10F THED S.G. Wet Layup Cire. Pump 01 I (CPI CFAPRP-01) 12M THED S.G. Wet Layup Cire. Pump 03 (CPI-CFAPRP 03) 12H THED Containment Ltg. XFMR-28 (PNL C11 & C12) l2 i o COMANCHE PEAK - UNIT 1 49 Revision 2 January 15. 1990
ir l TECHNICAL RE0VIREMENT 4.1 (continued) TABLE 4.1.1 (Continued) {) CONTAINMENT PENETRATION CONDUCTOR : OVERCURRENT PROTECTIVE DEVICES DEVICE NUMBER 3 AND LOCATION .
- 3. 480VAC from Motor Control Centers (Continued) ]
MCC IEB3-2 G.E. COMPT. NO2 BKR. TYPE SYSTEM POWERED 8RF THED JB-IS-1005, Altern. Feed to Motor Operated Valve 1-8702A IG THED Motor Operated Valve 1-8112 , 9G THED Motor Operated Valve 1-8701A 9M THED Motor Operated Valve 1-8701B 5M THED Motor Operated Valve 1-8000A SG THED Motor Operated Valve 1-HV-6074 4G THED Motor Operated Valve 1-HV 6076 4M THED* Motor Operated Valve 1-HV-6078 Motor Operated Valve 1-HV-4696 2G THED 2M THED Motor Operated Valve 1-HV-4701 3G THE0* Motor Operated Valve 1-HV-5541 O 3M THED* Motor Operated Valve 1-HV-5543 :
!]' IM THED Motor Operated Valve 1-HV-6083 '
6F THED Motor Operated Valve 1-HV-8808A 6M THED Motor Operated Valve 1-HV-8808C 7M THED Containment Ltg. XFMR-18 (PNL SCI & SC3) 8M THED Neutron Detector Well Fan-09 7F THFK Electric H2 Recombiner Power Supply PNL-01 8RM THED Motor Operated Valve 1-HV-4075C 9RF THED Motor Operated Valve 1-HV-4782 ' 9RM THED Motor Operated Valve 1-8811A ' Primary protection is provided by Gould Tronic TR5 fusible switch with 3.2A fuse. yy V COMANCHE PEAK - L' NIT 1 4-12 January 15, 1990
I' I L! I TECHNICAL REQUIREMENT 4.1 (continued) l r
> ,\
5 Y /' - TABLE 4.1.1 (Continued) CONTAINMENT PENETRATION CONDUCTOR i OVERCURRENT PROTECTIVE DEVICES j DEVICE NUMBER SYSTEM AND LOCATION POWERED l
- 4. 4BOVAC From Panelboards For Pressurizer .
Pressurizer Heaters Heaters , (1) groups A, B, & D
- a. Primary Breakers - General Electric Type TJJ Thermal ,
Magnetic breakers. ; Breaker No. & Location Ckt. Nos. 2 thru 4 of Pane 1 boards IEB2-2, IEB3-2, IEB4 1, IEB4 2 and Ckt. Nos. ; 2 thru 5 of Pane 1 boards 1EB2-1 and IEB3-1.
- b. Backup Breakers General Electric Type THJS with longtime and insts, solid state trip ,
/~'T devices with 400 Amp, sensor.
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Breaker No. & Location Okt. No I of Pane 1 boards ' IEB2-1, IEB2-2, 1EB3-1, IEB3 2, 1EB4-1 and IEB4 2. I (2) group C
- a. Primary Breakers - General Electric Type THED breakers.
Breaker No, and Location - For both IEB1-1 & IEB1 2 are located at Ckt. Nos. 2 thru 4.
- b. Backup Breakers - General Electric Type TJJ Thermal Magnetic breakers.
Breaker No, and Location - Okt. Nos. 2 thru 4 of 2 Switchboards IEB1-1 & IEB1 2. 5, 120V Space Heater Circuits Containment from 4BOV Switchgears Recirc. ran and CRDH Vent. f-~3 Fan Motor Space ( ) Heaters
'%J C0HANCHE PEAK UNIT 1 4 14 Revision 2 January 15, 1990
. TECHNICAL REQUIREMENT 4.1 (continued) l i
- u
[~\ TABLE 4.1'.1 (Continued) CONTAINMENT PENETRATION CONDUCTOR , OVERCURRENT PROTECTIVE DEVICES l [
- 5. 120V Space Heater Circuits from 480V Switchgears (Continued) l
)
- a. Primary Devices - N/A (Fuse) 2 c
- b. Backup Breakers 2 j i
BKR. LOCATION WESTINGHOUSE 1
& NUMBER BKR. TYPE ]
1 Swgr. 1EB1, EB1010 l Cubicle 3A. ) CP1 VAFNAV 01 i Space Heater Bkr. 'j i Swgr. IEB2, EB1010 Cubicle 3A, l~ CP1-VAFNAV-02 Space Heater Bkr. Swgr. 1EB3, EB1010
.n)
Cubicle 9A, CPI VAFNAV-03
'i O Space Heater Dkr. ;
Swgr. 1EB4, EB1010 Cubicle 9A, CPI-VAFNAV-04 Space Heater Bkr. P Swgr. 1EB3, EB1010 . Cubicle 8A, CPI-VAFNCB 01 Space Heater Bkr. Swgr. 1EB4, EB1010 Cubicle 8A, CPI VAFNCB-02 , Space Heater Bkr. O COMANCHE PEAK - UNIT 1 4-15 Revision 2 January 15, 1990
1 TECHNICAL REQUIREMENT 4.1 (continued) j
?f s j ,( ) TABLE 4.1.1 (Continued) f CONTAINMENT PENETRATION CONDUCTOR ,
OVERCURRENT PROTECTIVE DEVICES DEVICE NUMBER SYSTEM ; (- AND LOCATION POWERED l
- 6. 125V DC Control Power Various ]
a, Primary Devices - N/A (Fuse)
- b. Backup Breakers !
i.. ] I GENERAL ELECTRIC l PANELBOARD NO, CKT. NO. BREAKER TYPE j XED1-1 1,6 TED ! XE02 1 1.3.6 TED XD2-3 8 TED 1 1ED2-1 14,17 TED 1ED1 1 14 TED 2 l 102 3 7,10 TED 1D2 2 9 TED )
,- IED2 2 12 TED )
( IED3 1 5 TED l V). IE01 2 7,8 TED FB(hestinghouse) TBX WPX1LP 01 Main (LBK3) 1 7, 120V AC Control Power from Isolation XFMR TXEC3 & TXEC4 1
- a. Primary Devices N/A (Fuse) I
- b. Backup Breaker - Square D Type 01L located in 1 Miscellaneous Signal Control Cabinet 1 8, 120V AC Power for Personnel and Emergency Airlocks
- a. Primary Devices N/A (Fuse)
- b. Backup Breakers GENERAL ELECTRIC PANELBOARD NO. CKT. NO. BREAKER TYPE XEC2 34 TED XECl-2 2 TED
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COMANCHE PEAK - UNIT 1 4 16 Revision 2
- January 15, 1990
y 1 TECHNICAL REQUIAWENT 4.1 (continugn l
) IABLE 4.1.1-(Continued) s s CONTAINMENT PENETRATION CONDUCTOR r OVERCURRENT PROTECTIVE DEVICES l DEVICE NUMBER j AND LOCA M l l ;
[ t-9, 118V AC Control Power ; l a. Primary Devices N/A (Fuse) , p , !~ b. Backup Dreakers GENERAL ELECTRIC l F' PANELBOARD NO. CKT. NO. BREAKER TYPE- j
- r. 102 22 TED !
1 1PCI 10,13 TED IPC4 6,10 TED ; 1EC1 7 TED 2 i 1EC2 7 TED ~2 [ IEC5 8 TED- j IEC6- 3,8 TED ; I;_s\ 1 i
.V 10. Emergency Evacuation System Warning Lights Power )
- a. Primary Devices N/A (Fuse) I
- b. Backup Breakers !
SOUARE D
.PANELBOARD NO. CKT. NO. BREAKER TYPE P
XEC3 3 9, 10 FAL-12020 1 1
- 11. DRPI Data Cabinet Power Supplies :
- a. Primary Breakers 2 2
SOUARE D 2 PANELBOARD NO. CKT. NO. BREAKER TYPE 2 1014 1,2 FA 14050A 2
- b. Backup Breakers SOUARE D PANELBOARD NO. CKT. NL BREAKER TYPE
((j^N 1C14 Main Pni. Bkrs. FA-14070A 2 2 COMANCHE PEAK - UNIT 1 4-17 Revision 2 January 15, 1990
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BASES
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s 4 ,/Lsu, 4.1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTION DEVICES ~ , e The bases for OPERABILITY and surveillance of these devices arc ,;' ; contained in the CPSES Technical Specifications. 5 All Class l1E motor operated valves' motor starters are provided with
. thermal'_ overload protection which is permanently bypassed and provides an alarm function only at Comanche Peak Steam Electric Station.
Therefore, there are'no OPERABILITY or Surveillance Requirements for j these devices, since they'will not prevent safety related valves from i Le performing their function (refer to Regulatory Guide 1.106. " Thermal : 1)s .0verload Protection for Electric Motors on Motor Operated Valves," ! Revision 1, March 1977).
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[ TECHN! CAL' REQUIREMENTS MANUAL. , b' ', EFFECTIVE PAGE LISTING P N , i-.. ! Q' Ny . . .1.1 January'15; 1990 , ;
.) kd : Oi l-Revision 2' 3 F^ '
O*2 Revision 2 { i:? - Sec.-1 Original' :!
- , ~1 11 -July _21, 1989 !
1-21 July 21, 1989 123- Revision 1 F 'l July 21, 1989 [[ 51-5 July 21, 1989 ,1 16 July 21, 1989 h 17' July 21, 1989 .; .
'l-8: July 21 -1989 [
t : 1'- 9 July 21. 1989 1 10: July 21, 1989 ! S 1-11 July 21, 1989. 1-12 July 21,~1989- 4 1 13 July 21, 1989' , 1-14 July'21, 1989
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1-15 July 21, 1989 1-16 July 21, 1989 h g,,-i. 1-17 Revision 1
): 1-18 Revision 1 l' '
1-19 July 21, 1989 '. 1-20 July 21, 1989 1 July!21, 1989 1 22 July 21, 1989
.Sec 2. Original 2-1 July 21, 1989 2-2: July 21, 1989-2-3 July 21, 1989 ,
. 2-4 July 21, 1989
-- 2-5 Revision 2 2-6: July 21, 1989 2-7 July 21.-1989 j 2-8 July 21, 1989 -
~'2-9 July 21, 1989 2-10 July 21, 1989
' P. - 11 July 21, 1989 2 12 July 21, 1989 2-13 July 21, 1989 i 2-14 Revision 2
- / T 2-15 Revision 2
$N 2-16 July 21, 1989 7lll EPL-1 . w, .. . - . .- . . , - - -.
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, TECHNICAL' REQUIREMENTS MANUAL .
, EFFECTIVE PAGE: LISTING (Continued) i g g( . _
i ,{ 2-17 Revision 2-l
).
E J 2 18 Revision'2- > 2 19. July 21, 1989 2-20 July 4 21,:1989' 2-21' July 21,~1989 2 22 July 21, 1989-2-23, July 21 1989 l: 2 -Revision 2' ; L Sec. 3 Original 4' :31 July 21, 1989 3 2c July 21, 1989-33 July 21, 1989 3-4 July 21, 1989 35 January 15,l1990 36 July 21, 1989' l m: 3-7 July 21, 1989 . L L 3 8.. July 21, 1989 39 July 21, 1989 13 10 July 21, 1989 lt 3 July 21,.1989 j r]-- 3-12 Revision 2 ! i) 3-13 Sec. 4 Revision 2 Original 4-1 July 21, 1989 4 January 15,.1990 4-3: January 15, 1990 l 44 January 15, 1990 4-5 July 21, 1989 4 July 21, 1989
.47 July 21, 1989 4-8 Revision 1 l 4-9 Revision 2 l 4 10 July 21, 1989
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4-11 July 21, 1989 12 January 15, 1990 ; 4-13 July 21, 1989 l1, 4-14 Revision 2 1 15- Revision 2 4-16 Revision 2 4 17 Revision 2 I' - - 4 January 15, 1990
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