ML20155K607

From kanterella
Jump to navigation Jump to search
Forwards Detailed Listing & Description & Relative Significance Grouping for Amends 69 & 70 of FSAR
ML20155K607
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 06/17/1988
From: Counsil W
TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
TXX-88501, NUDOCS 8806210300
Download: ML20155K607 (52)
v • d • e


Text

_ _ _ - _ _ - _ _ - _ .

a

==

F7 Log # TXX-88501 C.

~'~

C File-# 10010 Z Ref 10CFR2.102(a) 1UELECTRIC June 17, 1988 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Wcshington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 EVALUATION OF AMENDMENT 69 AND 70 CHANGES TO FINAL SAFETY ANALYSIS REPORT REF:

(1)(Letter from TV Elec':ric) dated Stewart May 17, 1988 D. Ebneter (NRC) to William G. Couns (2) TV Electric letter TXX-88467, dated June 1, 1988 Gentlemen:

In Reference (1), the NRC Staff requested that TV Electric identify portions of the FSAR which were previously evaluated and found acceptable in the Staff's Safety Evaluation Report (SER), or supplements thereto (SSERs), and for which the licensing basis was changed by FSAR amendments after Amendment

54. The NRC Staff indicated that the response should identify and summarize the nature of the FSAR changes since SSER No. 12 was issued. In addition, the Staff requested that TV Electric evaluate each FSAR change with respect to the overall safety of the facility and broadly categorize each change based on the safety significance determined by the evaluation.

In response to the NRC Staff's request, TV Elettric provided in Reference (2),

a detailed listing and description of every change to the FSAR, through Amendment 68, that caused that document to differ from the version reviewed and accepted by the NRC Staff through SSER No. 12. Further, all changes were placed in one of four groups based upon their relative significance. Attached is a similar listing, description, and relative significance grouping for l Amendments 69 and 70.

Again it should be emphasized that, prior to submittal of each FSAR change, TV

, Electric had reviewed the technical merits of such change and had concluded that all aspects of the change satisfied applicable NRC requirements. None of the changes has "safety significance" in the sense that it would create a potentially unsafe situation, i.e., a facility not in compliance with NRC requirements. The term "relative significance" as used in this review denotes l i

  1. 0 North Ouve Street LB81 Dallas. Texas 7H01

r

+

s w

3 1

T

- TXX-88501 e: June 17, 1988

' Page 2 of 2 only that the FSAR' changes - all of which are acceptable from a safety standpoint -- have been classified into groups, in increasing order of- .

possible importance of the change to the NRC-Staff. The classification, which-involved a number of subjective considerations, is intended only for purposes of aiding the Staff in planning and scheduling its review.

- This completes the information requested in Reference (1). Please let us know if we can provide any further information to facilitate the Staff's planning and scheduling of its review.

Very truly yours, W. G. Counsil By: /; 4h 1

. R'. ' D()Wal ke r Manager, Nuclear Licensing BSD/amb attachment c - Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3)

I

)

Attachment t3 TII-08501 7une 17, 19eS Page I cf 50 PJ Electric FSAR Change Review Infomation . Chapter 01 Pa'ge 1 SEE Croue Evaluation FSAR Amended Change Classification 13 umber Descriptica (Page Nu:nbering per An-70) 1.1 2 1.6-3-1,1 T1.6-1 [ Am-69](Sht. 186 Addition This change incorporates WCAP-10271 (through Supplement 2) and 6 -11112 Into Table 1.6-1 to ino.1cate their applicability to CPSES with regard to CPSES Technical Specifications. (88-145 t

_________.____6 __ _' '

d H

~

n o

i t

a 1

c i

f i

s

s e a g l l a C a P i e r g o n t a i h d C E 2) 0 3

8 9(

0 6

m A

2 0

e r

'2 r

e 3 t 1 p -

a 4 h

C 2 T

o t

01 7 s n

o n

o 6 i t

i r c t e e a p r m r r g o f

o n i

c n r l I e a b i w m r o

t u

N c

t r i e e g

d F e e

a )

P 9 r g ( 6 o n d - n a en mi h d o A m C ni [

et mp s R 3 e A Ai r 1 d S - i F R c 4 s As e S e 2 r TD TP n 4 o

i 2 t -

ar 1 ue lari 2

4 t u 1 EN 2 0

5 5

4 I

X T p o c 4 t 8 o 9 r t1 9M 'c i

C c ,fo r e t m7 h12 ce c l aee E t ng R 4 t ua J E AJP T S 2

4.34 Attachment to TZX-68501 J.ine 17, 1998 Fage 3 cf 50 T'J Electric FEAR Change Review Infszmation Chapter 03 Page: 1 _ l SIR Group fealuation FSAR Amended Change Classification Number Description f Page Numbering por An '0) 3.2.2 3 17A-10i%3.2.2 T17A-1 ( Am-69]tSht. 13) . . Addition '

Adds

  • Breakdown orifices
  • and Orifices" to the table listing cf components for the Auxiliary Feedwater Systen. These itens wre inadvertently omitted from the listing. (88-1641 3.2.2 4 3.2-027-3.2.2 T3.2-3 [ Am-69]ishts. 6,7) Additics:

Adds flow diagrams to the list of flow diagrams for the Fire Protection System. These diagrams have been redrawn incorporating outstanding design clup. (98-tS2) '

r____.__ . _ _ _ _ _ . _ __ _ __

1 I

Attactwent to '"ZX-88501 Jane 17, 1988 Page 4 of 50 TJ Electric FSAR Change 2.sview Information Chapter 03 Page: 2 SER Group ~ Evaluation FSAR Amended Change Classification tkaber Description (Page Numbering per An-70) 3.7.1 4 .7-65-3.7.1-N 3.73-4 [Am-64] Correction' Provides a change to allow the use of ASME Code Case N-411 danping valaes in an analysis of the primary system loop to determine seismic loads for the reactor cociant pump tie supports and the reactor vessel supports.. (See evaluation no. 3.7-009-3.7.1-N, Att. 2 of TIX-88467, page 71)

.(E8-147)

._.W

, , ; ,. ( D AttCchment to TII-66501 Jur.e 17, 1989 Page 5 of 50 TU 11ectric FSAR Change Review Infcrmation Chapter : C3 .Page 3 SER Croup Evaluation FSAR Amended ' Gange Classification Flumber Description (Page Numbering per Ae-70) 3.7.2 2 3.7-66-3.7.2 3.7B-42 [Am-69] Correction Provides a change to correct the statement discussing how structural failure of the Turbine BJ11 ding in the direction of the adjacent Category I structures is preventad. Internal bracing will prevent the Turbine Building from interacting with the adjacent Category I structures. t88-159) v 1

T.

I i

1

..-- , , -, , ,_ ., . , , . .., ,_. ~ . , , .

4 Attachment to 52-835C1 June 17, 1998 Page 4 of 50 TJ Electric FSAR Chan y Review Information Chapter 03 Page: 4 SER Croup Evaluation FSAR haended -Change Classification Nimber Description (Page fiumbering per An-70) 3.8.3 3 3.8-092-3.8.3 130-50 [An-69) Revision Revises the number of masonry walls in the Electrical and Control Building which were modified to prevent seismic interactions and the number which were evaluated to have acceptable seismic interactions. Also, adds one additional removable block enclosure ~

in the Safeguards Building which was evaluated and found to have acceptable seismic interactions. (88-245#

O l

1 1

1 I

l l

\

l

L  :%. ~;;-

.I Attachnect to T3I-69501 June 17, 1915 Page 7 of 53 .

.1 T'J Electri TSAR Change Review. In! creation Chapter 03 Fage: '5

{

EER Crot.p Evaluation FSAR Amended Change Classification N aber . Descriptia (Page Numberirq per An-70) 3.10 2 3.10-004-3.10 3.10N-3 and 3.10B-4 [ Am-69 ] Revision Details how Class 11 equi; ment located is a mild environment area wt11 be setsmically qualified. (80-281) 3.10 4 3.10-00 % 3.10 Sec. 3.10N [Am-69] Editorial This !.rction is being tssued in ccamp'2terized form.at.

o

Attacament to "ZX-80501 i June 17, 1968 Page 9 cf 50 T'J Electric FSAR Char.ge Review Infor: nation Chapter 03 Page: 6 SJ Croup E7aluation FSAR Amended Change Classif tcation Number Descriptior. (Fage Nu:nbering per An-70) 3.11 2 1AB-37-3.11 1A18)-7 [ Am-69] Update Beforences 10CTR50.49 statements of consideration for exception to Reg. Cuide 1.99 for Class 1E equipment located in a mild enrionment area. 180-281) 3.11 2 1AN-9-3.11 1A(N)-43 [Am-69] , .

Update Refl9ets current status of WCAP-8567, Revision 6-A, and references 10CFRSO.49 statements of considerati.on for .xception to Reg.

Cuide 1.99 for Class IE aquipoent located in e alid environment '!

area. (88-291) 3.11 3 1AN-9-3.11 1A(N)-56 [Am-69] Revision Details how Class IE equipment located in a mild environment - l area will meet Reg. Gaide 1.100. (08-281)

+

l 1l1l A

n o

i .

t a

1 c

i f

i s

n o'

s i '

e a t g

a l a C c P i e f g i n r a a h l C C g s n w i e Ewo i v

2l e Alo ef2f

". r h f )

t et hi f t nn1

  • 55 5 o U g -

0 s i8 nd rs8 s od o (

iAf e

're t i . ntd h .

t d2 o igt e p e a dt nt h h niii C cad rm i Eua h1 d 9, w 3 s9d1

0) qt9 et 7

- :n,in 1oe vn n yU ert n A f h pr o iot pe i r tt a v t

a e

p n o d eetd a n

i r g dl nn ibdai e i n an ycad s f

n r bi ea e

npl1 t s w I

bn w opt et e m i ais u i e t t aqb ve a s l' e e

g ci r ,

R i r 6 a f eos6 e

g P ]idf a

( 9 ro wt n d 6 ac . n a en yde

- l h do ecI m C ni A I*

et [ s engune R mp A Ai 1doncm S r 3 iii A F R c - vtd s A s 2 ocrir S e reoh o FD 5PS wTf 4

2 n

i o 5 t 1 ar 2 u e 0 l b -

a a 2 v s

, Et h 5

'S 0

8 I

I T p o u 4 t3 o 80 r 95 c C t1 i n ,fo r e t c

tm7 1 9 e c l 4 aee t ng E

E 2 t ua J E AJP T S 5 i 1 l lll l, Illl' l l\ , l, 1lllll

}

Attschaent to T2% 09501 June 17, 1988 Page 10 of 50 W Electric FSAR Change Review Informatica Chapter s 05 Page: 2

, SER Croup Evalaation FSAR Amende$ Chage Classification Nuncer Description (Page Nu:nbering per M-70) 5.3.1 3 5.3-004-5.3.1 5. 3-11 [ Am-70 } Revision Changes the pressure vessel surveillance capsule withdrawal sct:edale to be consistent with the Westinghouse roccamendations'. AST1-E195-62, 10 CFR 50 App. L and CPSES toch spec or Tech Spec Introvement Progran (Item 2.2). (98-355)

SER/SSER IMPACT: - SER Subsection 5.3.1.2, Page 5-10, second paragraph, and SSER 1, Subsection 5.3.1.2, page 5-2, second paragraph, are not consistent as a result of this change.

Attachment to TZI-+33501 June 17, 19st a Fage 11 of 50 TU Electric FSAR Change Periew Isformation Chapter 05 Page: 3 SER Group Evaluat on FSAR Amended Change Classification Namber Description (Page Narbering per As-7))

5.4.2 2 5.4-0 32 -5.4.2 5.4-10 (Am-70} Update Provides an updated desrription of a dated discussion of plants with Inconel-600, which have operated with AW water treatment, and describes how this operatina; experience has been censidered at CPSES. t60-279) 5.4.2 4 5.4-031-5.4.2 5.4-16 [Am-70] Correction Deletes the words *and pitting type" from the description of the corrosion resistance of Irconel-600. Incor.el- 600 has only moderate resistance to pitting cerrosion in severe water chemistries.

(88-279) h

Attachment to T2:i:-60501 June 17, 19?8 Page 12 of 5C

'PJ Electric fSAR Change Review isformatica Chapter 06 Page: 1 SER Croup Evaluation FSAR Amended Change Classification Nt:moer Description iPage Numbering per As-70)

'3 6.2.1 1 6.2-150-6.2.1 Sec.6.2 [Am-69] Revision The analyses of IDCA and Main Steam Line Breaks (MS*.B) inside containment were re-performed using the Stone 6 Webs.ter IDCTIC computer code. These reanalyses were necessary because of errors discovered in the version of CONTEMPT-LT 26 used in the original containment analyses, resulting in the under-prediction of certain containment parameters. This condition was previously reported to the NBC in our letters TXI-6512 dated June 12, 1987, and TXI-08120 dated January 18, 1998. Since a new analysis was being perfonned, the most current information was used. This included r.sw information, such as the deletion of the Boron Injection Tank (BIT) and revised containment heat sink data based on current plant drawings and revised IDCA structural heat transfer coefficient.

The revised containment analysis resulted in an increased containment peak temperature for the MSLB case. All safety related equigment i required to be qualified for this condition were determined to be qualified to the higher temperature. Tables and Figures in this FSAR section have been revised to reflect the results of the revised containment analysis.

SER sections 6.2.1.1 and 6.2.1.2 reference the use of the CONTEMPT code for containment analyses along with the resu1*mt containment conditions. As result of this FSAR change the SER sections are no longer correct. (68-114) l 6.2.1 1 6.2-160-6.2.1 6.2-6 [Am-69] Revision The analyses performed by CCfffD8PT-LT/ MOD 22[1, 2, 3, 4] and CorffEMPT-LT/ POD 26 cmputer codes have been replaced by analyses using the IDCTIO cafe. (See discussion under evaluaticn number 6.2-150-6.2.1) 6.2.1 1 6.2-172-6.2.1 6.2-10 thru 6.2-22 [Am-69] Revision A new Section 6.2.1.1.3.11 bas been added to describe the analytic modeling of the IDCTIC emputer code. (See discussion under evaluation no. 6.2-150-6.2.1.)

6.2.1 2 6.2-153-6.2.1 6.2-4 [As-69] Revision j Of the steam line breaks analyzed, the FSAR is revised to present one ses11 double erased rupture at two power levels { 30% and 70%)

instead of the previous two small double ended ruptares at four power levels (102%,' 70%, 30% and het shutdown). The small ruptures presented were determined to envelope all the small rupture conditions previously presented. (88-114) 6.2.1 2 6.2- 155-6.2.1 6.2-4 [Am-69} Addition Provides description of a sensitivity study performed to determine the effects of varying con;ainment initial conditions on peak pressure and temperature for the DEPSC and 9.908 sq are foot

m%

q Attac+ rmt to TII-49501 June 17, 1908 Fage 13 of 50 TU Electric FSAR Change Review Inforsation Chapter 06 ' Page: 2 SER Group Evaluation FSAR Amended Change Classification Nanber Description (Page Nunbering per An-70) steam line tareaks. (89-114) 6.2.1 2 6.2-156-6.2.1 6.2-5 [Am-69} Revision The parameters that were provided as a function of time (i.e.,

previous itna numbers i thru 9 for the design basis I4CA case and 1 thru 5 for containment pressure transients for other analyzed IDCAs) have been revised, consolidated and rearranged consistent with the parameters suppliei by the IDCTIC code. The parameters to be included in FStJt figures have been identified for specific analyzed breaks. The following figures for the I4CA case, were daplicative of information contained in tables, were not used, or were not sufficiently useful to update, and thus the figures have been deleted: 1. Containment steam partial pressure (Figure 6.2.1-4) This figure was not sufficiently useful to update. 2.

Energy addition to containment (Figure 6.2.1-5) This information is already contained in the mass and energy release rates contained in Tables 6.2.1-3A, 6.2.1-3B, 6.2.1-3C, 6. 2.1-4, and 6.2.1-50.

3. Energy removal from containment (Figure 6.2.1-66 4. Energy distribution in Containment (Figure 6.2.1-7) 5. Energ/- removal trf spray f cm contairanent vapor region (Figure 6.2.1-0) The infomatic contained in Figures 6.2.1-4, 6.2.1-7 and 6.2.1-0 was duplicative of information containwi in Tables 6.2.1-50 and 6.2.1 50A. (88-114)

(See also evalaation no. 6.2-150-6.2.1) 6.2.1 2 6.2-163-6.2.1 6.2-8 (Am-69] Revision The assumption of a one-eighth inch air gap with thermal conductance of 1.6 Etu'hr-sq f t-F, has been replaced with a more realistic assumption for interf ace conductance of 10 Btu /hr-sq f t-F. This is a realistic and conservative assumption because; 1) the containment liner was used as a form for concrete pour during cor.tainment construction and therefore, for the most part, the liner is in S direct /close cantact with the concrete, and 2) during the times of interest for the IDCA and PCLB events, the containment is pressurized forcing the liner into closer contact with the concrete.

(80-114) 6.2.1 2 6.2-164-6.2.1 6.2-8 (Am-e9] Revision The paint heat conductances for steel and concrete painted suxtaces have been revised to be more realistic. (08-114) 6.2.1 2 6.2-166-6.2.1 6.2-8 [Am-e9] Revision The IDCTIC code uses the Tagami structural heat transfer coefficient f or 1DCA analysis and the Uchida coefficient for MSLB analysis.

The Uchida teet transfer coefficient was previously used for CPSES IDCA analyses. Because of the difference in the pipe break exit fluid conditions between IDCA and ELB scenarios and the differicg centairment saturstion conditions, the Tagm i heat transfer coefficient is more conservattre for IDCA analyses whereas

~~ ~~ ~ ~

I Attachment to TZI-80501 June 17,19'19 ^J Page 14 of 50 TJ Electric FSAR Change Review Information Chapter . 06 .Paget 3 EER Group Evaluation FSAP Amended Change Classification Number Description (Page fkabering per An-70p the Uchida coefficient is more appropriate for MSLB analyses.

(Sco also evaluation no. 6.2-150-6.2.1) (99-114) 6.2.1 2 6.2-169-6.2.1 6.2-9 (Am-69) .

Revision Revises maximum external differential pressure from .3.37 paid to 3.79 paid based on the conservative revtsion to the ir.itial containment pressure. (68-1141 6.2.1 2 6.2-173-6.2.1 6.2-10 thru 6.2-22 (Am-49] . Revision The Westinghouse mass and energy release rates for the post-reflood phase are modified as discussed in the Broken Icep and Ictact Loop Steam Generator analyses as a result of the lower containment pressure (p) computed by the LOCTIC code. In addition, the mass and enerq7 release rates have been modified to include core decay heat and safety injection flow. (88-114) 6.2.1 2 6.2-174-6.2.1 6.2-21 thru 6.2-22 (Am-69] Bevisica ECCS spillage is accounted for separately by the IDCTIC code since 1;; was not included in the Westinghouse WPIFIDCD calculation of mass and energy release for the reficod phase. (85-114) 6.2.1 2 6.2-191-6.2.1 6.2-54 [Am-69] Parision For the IGLB events the statement that cont nment spray actuation occurs within 60 seconds of containment pressure reaching 20 psig, has been replaced with an expanded description of the time it takes to achieve full containment spray flow. The two cases are, the full cbuble eaded rupture case and the partial double ended rupture / split break case. The primary difference between these cases is the energy release rate and the resultant speed at which containment pressure increases (and thus the speed at which the S and P signals are generatedt. The S signal initiates spray pump start (at approximately 5 psig) and the P signal initiates spray valve opening s at approximately 20 psigt. As a result of t.he relatively long time differential between S signal and P signal initiation for the partial rupture case, the time delays associated with pump start ( 1.e.,

diesel generator start, sequencing pump load to Class 1E bus, and pump acceleration) are satisfied prior to P signal initiation.

Thus full spray flow can cccur within 39 seconds af ter containment pressure reaches 20 psig. For the full double ended rupture case P signal initiation occurs before pump start time delays are satisfied and thus full ficw is conservatively ass.sned to be achieved in 60 seconds af ter the 20 psig containment pressure is reached. (83-114) 6.2.1 2 6.2-199-6.2.1 TS.2.1-2 6 6.2.1-2A ( Am-M ] Revision These tables are revises to reflect the revised containsect analysis using the !ACTIC code. (See evaluation no. 6.2-150-4.2.11

- w e -- e-.-. y 9e . .- -.w .

_ .._ m . _

Attachment to TIX-36501 Jane 17, 1999 Page 15 cf 50

':"! Electric FSMt Change Periew Information Chapter : 06 Paget 4 SD Group *.4 .ation FSAR Amended Chege Cisssification Ntauer Description (Page Numbering per Am-70) lES-114) 6.2.1 2 6.2-190-6.2.1 '"6.2.1-3, 6.2.1-3A & 6.2.1 * *Am-69] h vision

'"hese Tables leplace previour olo 6.2.1-3. The new tables reflect ths revised contaissent analysis using the IDCTIC code.

asse evaluation under no. 6.2-150-6.2.1) 6.2.1 2 6.2-191-6.2.1 76.2.1-4 thro T6.2.1-6 (Am-69] Revision.

""hose tables are revised to reflect the revised contairment enalysis using the IDCTIC code. (See evaluation under no. 4.2-1*. Abs.2.1)88-114) 6.2.1 2 7.2-193-6.2.1 2 ""6.2.1-8 thru T6.2.1-10 [ An-69] Revision

%ese tables are revised to reflect the revised contairment analysis using the IDCTIC code. (See evaluation under no. 6.2-150-6 4.1) e85-114) 6.2.1 2 6.2-194-6.2.1 '"6.2.1-50 and -50A [ Art-69] hvision

""ables are re-ised to reflect the revised containment analysis using the IDCTIC code. (See discussion for evaluation no.

6.2-150-6.2.11 80-1141 6.2.1 2 6.2-195-6.2.1 F6.2.1-1 thru F6.2.1-3 [An-69] Revision Figures revised to refleet the revised containment analysis using the IDCTIC code. (See discussion under evaluation no. 6.2-150-6.2.1:

483-114) 6.2.1 2 6.2-198-6.2.1 F6.2.1-9 thre F6.2.1-16 ( Am-69] Revision These figures are revised to reflect the revised containment analysis using the IOCTIC codo. (See discussion under evaluation no. 6.2-150-6.2.1) (68-114) 6.2.1 2 6.2-200-6.2.1 F6.2.1-17 [Am-69] ' Revision This ficare is revised to reflect the revised contairment analysis using the IDCTIC code. (See discussion under evaluation no.

6.2-150-6.2.11 (88-114) 6.2.1 2 6.2-202-6.2.1 F6.2.1-20 [ Am-69] Revision

%is figure was revised to reflec the revised containment analysis using the IDCTIC code. (See discussion under evaluati'>n no.

6.2-150-6.2.1) (86-114) 6.2.1 3 6.2-158-6.2.1 6.2-6 [Am-69] Revision Figure 6.2.1-19, Containment Enernal Wall Temperature, and Figure 6.2.1-19, Contaisiment Internal Concrete Temperature, have been deleted. These parameters are included as part of the containment heat sink analysis, however, the figures were not sufficiently useful *.o update. (ee-114)

Attachment to T H -89501 Ane 17, 1996 Psge 16 of 50 TU Electric FSAP Change Eeview Infomation Chapter . 06 Page: 5 SER Croup Evaluatton FSAR Amended Change Classification NJRber DesCIlption (Page Numbering per An-70) 6.2.1 3 6.2-161-6.2.1 6.2-7 [ Am-69 ] Revision Dew point temperature is use instead of relative humidity. (80-1146 6.2.1 3 6.2-162-6.2.1 6.2-7 [ Am-69) Addition Service water temperature is added to Table 6.2.1-5. 188-114) 6.2.1 3 6.2-165-6.2.1 6.2-8 [Am-69] Revision The paragraph discussing mesh spacing far heat sinks is deleted.

A discussion of the IDCTIC metta$ ology for mesh spacing is presented in FSAR Section 6.2.1.1.3.11t See also evaluation no. 6.2-150-6.2.1).

(68-114) 6.2.1 3 6.2-168-6.2.1 6.2-9 [Am-69] Revision Revises containment initial pressure from 14.7 psia to a more m servative 14.2 psia. (88-1141 6.2.1 3 6.2-170-6.2.1 6.2-9 [ Am-69] Nvision Deletes the s+atement regarding percent margin. The revised computed external differenttal pressure is still well below the maximum design dif ferentist. A statemer.t as to percent margin is unnecessary.

168-114) 6.2.1 3 6.2-171-6.2.1 6.2-8 [Am-69] Revision Replaces the paragraph discussing the impact of Boron Injection Tank (BIT) renovat on the previous contairment MSLB analysis.

The revised contalmeent MSLB analysis considered the removal of the BIT. 188-114) 6.2.1 3 6.2-175-6.2.1 6.2-4 3 [ Am-69 ] Revision.

The discussicas of itans 7, 8, 9, 10 aM 11, Broken loop Steam Gerarato:s - Equilibrium Stage, Broten toop Steam Generators

- Depressurization Stage, Intact Loop Steam generator- Equilibrium Stage, Intact loop Stem Generator -Depressurization Phase, and Illustration of Method, have bcen deleted. These discussions have been modified and are discussed uMer new Section 6.2.1.1.3.11, 4

p. 6.2-18 through -21. (see evaluation no. 6.2-172-6.2.1) (86-114) 6.2.1 3 6.2-176-6.2.1 6.2-43 pa-69) Addition Provides reference to Tables 6.2.1-50 and 6.2.1-5GA for additional design bawis ICCA energy distributions. (88-114) 6.2.1 3 4.2-179-o.2.1 6.2-51 [ Am-69] Revisica j .'evises the volume of the Unisolatei feedline frcza 260 to 571 ca. f t. Althoogt it was not necessary to pcstulate a f ailure of the feedwater isolation valve, tha new volume inciades the thid between the isolation valve and the feedwater control valve.

y- - .--

e - - - - - .- . ,e -e .- w

. JI' Attachment to TIX-66501 Jane 17, 1988 Page 17 of 50 T'J Electric FSAR Change Heview Infarmation avter . 06 Fa ge: 6 SER Croup Evalu tion FSAR Amended Change Classification Number Description (Page Numbering per An-70)

Previously this volume was not included. This is a conservative assumption and still less than the volume of 800 cu. used in the analysis. (88-1146 6.2.1 3 6.2-164-6.2.1 6.2-60 thru 6 9 [Am-69] EJrision Deletes refe m. A associate <x with the CattrIMP.* code and replaces than with references related to the !.DCTIC cafe, heat transfer information, and bcron injection tank restial. Also afds new references 9 through 14 rotated to Safety Evaluation Repcrts issued to plants which used tha IDCTIC code for coctainment analysis. (88-114)

6. .^ .1 3 6.2-186-6.2.1 6.2-74 (Am-C9] Revision I Coletes reference to Figures 6.2.1-7 and 6.2.1-3 and replaces them with Table: 6.2.1-50 and 6.2.1-50A for ir.tegrated enerqy coatsnt of the contai.nment. (SS-114) 6.2.1 3 6. -192-6.2.1 T6.2.1-7 [ Aca-69] devisten

'diis table is deleted. The mesh spacing for heat sint is performed within the LOCTIC coden. (This is consistent with evaluation number 6.2-165-6.2.1) (68-114) 6.2 -19 6-6.2 .1 hrigion 6.2.1 F6.2.1-4 [Am-69]

This figure has beea deleted because it was not suff'ciently useful to update. (See discussion under evaluation no. 6.2-156-6.2.1)

(SS '.14) 6.2.1 3 6.2 -19 7-6.2. 1 F6.2.1-5 thru F6.2.1-0 [An-69] Revision These figures are deleted since they tre duplicative of infornation contained in tables. (See discussion under evaluation no. 6.2-156-6.2.1) (80-114) 6.2.1 3 6.2-199-6.2.1 F6.2.1.16A [Am-69] Revision This figure is deleted be:ause it was not sufficiently useful to update. (See also evalaation no. G.2-150-6.2.1) #E8-114) 6.2.L 3 6.2-201-6.2.1 F6.2.1-18 and F6.2.1-19 [ Am-M ] Revisica These figures were deleted because they were not stificiently tseful to update. (See alao the discussion under evaluation no.

6.2-158-6.2.1) (68-114) 6.2.1 4 6.2-151-6.2.1 6.2-3 [Am-69) Cle-ification Adds the words "minimum Cantainment Spray Syster. . 35) operation" to tw11cate that one out of & con Minment spray crains Ln operation is the minimum CSS operatirg condition. (68-114)

Clarifle m 6.2.1 4 6.2-152-6.2.1 6.2-4 (Am-69] .

Expands the discussion of the initial cocittlons of the ECCS .

and CSS operation for various break analyses. t 6 114) u v

J h 70 caci. ment to TXI-80501

.~ 17, 1985 o g la of 50 TU 21ectric FSUI Change Review Infor.mation Chapter C6 Page: 7 SER Croup Evaluation F3AR Ar W ed ' Change Classification Number ' Desc*1ption (Page Numbering per An-70) _

6.2.1 4 6.2-1.54-6.2.1 6.2-4 [Am-69]' Editorial Rert e ar previous Tabla 6.2.1-2 which cc uidered LOCA and MSLS together, with two tables sa new Tatle S.Z.1-2 which cons.'.ders m1y I4CA and a new Table 6.2.1-2A whid consi#rs only MT3.

(88-114)

(Evaluate witt. numbet- 6.2-15 0-6.2. 1) 6.2.1 4 6.2-151-6.2.1 6.2-5 {Am-69] Clarification Containment "vapor" is revised to read containment "atmosphere".

(68-114) 6.2.1 4 6.2-159-6.2.1 6.2-6 (Am-69) Clarification Adds description of conditions for the antlysis of containment pressure temperature respewes. (88-114) 6.2.1 4 6.2-167 F.2.1 6.2-0 [Am-69] Edit.3 rial Rmrises figure number for the IDCA heat transfer coefficient as a function of time fra: Figure 6.2.1-9 to 6.2.1-13. ( 68.-U S )

6.2.1 4 6.2-177-6.2.1 6.2-44 (Am-69] Clarification Adds "RCS hot log" to clarify the location cf the temperature referred te. (88-114]

6.2.1 4 6.2-178-6.2.1 6.2-45 [Ju-611} A E tion Adds reference for the L7C code. (68-114) 6.2.1 4 6.2-182-6.2.1 6.2-54 [Am-69] Clarificatiou The words "among the steam breaks analyzad" are deleted. These worde imply thst there ray be es unanalyzed break which is more limiting. (60-114) 6.2.1 4 6.2-183-6.2.1 6.2-54 [Am-69] Editorial Revises the reference to WCAP-8022 .or tio ar?s cnd energy release data. (89-114)

I Attachment to 'ECC-69501 j June 17, 1989 Page 19 of 50 "U Electric FSAR Change Paview Information Chapter 06 Page: S SER Croup TvaL2ation FSAR Amended Change Classification Number Description (Page Numbering per An-70) ,

6.2.2 3 6.2-187-6.2.2 6.2-75 [Am-69] Revision Tbe overall thernal afficiency of spray droplets in cooling the centainment is revised from 1.0 to 0.99. This is a so o conservctive assumpt.on tha.1 was used previously..(86-114) 6.2.2 4 6.2-185-6.2.2 6.2-73 [Am-69] .

Correction Deletes the statemect which says that no credit is taken for cooling by the ECOS. The cooling ef fects of the ECCS (i.e. , PJht heat exchangers) are taken in account during the recir::ulation  ;

phase. It is unnecessary to state that credit is not taken during <

the injection phase. (88-114) j I

l

  • 1 . . .
n. .. -

~ .

Atta-hunt to TU -SCSO1 Jane 17, 1968 Page 20 of 50 TJ Electric FSAR Change Review Inforz::ation (tapter 06 Page: 9 SER Group Evaluation FSAR Amended Change Classification Number Necription (Page Numbering per Am-70) 6.2.0 4 5. 2-188-6.2. 3-E - 6.2-93 [Am-1)] Correction Adds tt:e valve arrangements 1, 6 and 29 for contairmient penetrations that have been provided with thermal relief valver as shown in FSAR Fig. 6.2.4-1 sheets 1, 2 and 8. These configurations were inadvertently not included in Amendment 66. (See eva*uation number 6.2-29-6.2.3-E, Att. 2 of TII-88467, page 161). (89-184) l

~

3_ ,

'~ 3

_- 2 -

-:'. -)

. . . ~

Attachment to TII-68501

- ne 17, 19E8 Page 21 of 50 TU Electric FSAR Change Review Information Chapter : 06 Page: 10 SER - Group ~ Evaluation FSAR A:nended Change Classification Number Description iPage Numbering per An-70}

6.3.3 3 6.5-030-6.3.3 6.5-29 [Am-70] Correction-Corrects the method used to assure the design flowrates of the chemical eductors and spray nozzles. Ncte: ' These devices are

  • performance tested
  • not "calibrated". (83-356) 6.3.3 4 6.2-160-6.3.3 6.2-52 [Am-69] Clarification Adds *5 sec* which was previotAly Gritted. (68-114) i n

s b

Attacament to *21-48501 June 17, 1988-Page 22 of 50 TJ Electric- FSAR Change Review Informatica Chapter ! 06- Page: 11 SER Croup Evaluation FSAR Amended Change Classification Number Description (Page Numbering per Aa-TO) 6.4 4 6.4-030-6.4 6.4-8 [Am-69] Clarification Mds the word "unprotected

  • to clarify that during accident conditions general area radiation level which would result in a maximum exposure to 75 ran of beta to utprotected skin is acceptable -

provided that special protective clothing and eye protection is worn.

f i-a u

Attachment to T'CI-68501

' June 17, 1988 Page 23 of 50

  • t; Electric FSAR Change Review Infcrmation Chapter.- 07 Page: 1 SER Croesp Evaluation FSAR Amended Change Classification fiumoer Description (Page Numbering per Am-70 7.1.2 2 7.1-33-7.1.2 T7.1-2.2 thru T7.1-2.7 [Am-70] Addition Discusses applicability of Regulatory Guides 1.45, 1.87, 1.100 and 1.105 and IEEE Stds. 2 3, 344, and 384 to the "Process and Effluent Radiation Monitors
  • of Table 7.1- 2.6 due to design developunent that has resulted in upgrading some monitors and adding others that are Category I. As a result, safety-related criteria are being identified as being applicable. 188-146) 7.1.2 3 7.1-18-7.1.2 T7.1-1 and 77.1-2.2 thru T7.1-2.7 [Am-70] Addition Adds GDC-30, 63 and 64 to the listing of applicable criteria.

These CDC's were discussed in the specific sections of the FSAR, but were not reflected in this table. This change brings the table into agreement with other sec+1ons of the FSAR. (68-146) ,

7.1.2 3 7.1-20-7.1.2 T7.1-2.3 (Am-70) Addition l Adda GDC-44 and 46 to "Control Roa Conditioning

  • reqeirements j because the GDC applies to sfstems s transfer heat frm safety a systerms to an ultimate heat sink and . 4 Control Room Air Conditioning j 1

system performs that function. (88-146) 7.1.2 3 7.1-21-7.1.2 T7.1-2.3 [Am-70] Addition l Adds CDC-40 to "Caponent Cooling Water" and "ESE Ventilation" because the GDC applies to associated cooling systems which include CCW and ESF Ventilation (room coolers). (88-146) l 7.1. 2 3 7.1-22-7.1.2 T7.1-2.3 [Am-70] Addition Adds GDC-46 to "ESF Ventilation" and "Service Water Intake Structure HVAC* because the GDC applies to these systems. (88-146) 7.1.2 3 7.1-23-7.1.2 T7.1-2.6 (Am-70] Addition Mds GDC-30 for

  • Reactor Coolant Pressure Boundary (BCPB) Leak Detection" and "Interlocks RCS Pressure Control" to cover the GDC applicable to instrumentation and controls for Reactor Coolant pressure boundary functions. (68-146) 7.1. 2 3 7.1-24-7.1.2 T7.1-2.6 [Am-70) Addition Adds CDC-63 for "Process and EFF Radiation Monitors" and GDC-64 for "Accident tbnitors" and ' Process and EFF Radiation Monitors" to cover the CDCs applicable to these instrumentation and controls.

(98-146) 7.1.2 3 7.1-25-7.1.2 T7.1-2.6 [Am-70] Addition Adds GDC-4 and 5 to "Process and EFF Radiation Monitors" because of the design change that upgrades the control room intake radiation monitor from non< lass 15 to Class 1E and redundant. (68-116) 7.1.2 3 7.1-26-7.1.2 T7.1-2.6 (Am-70] Addition Adds CDC-34 to "RhR Inclation valves" to cover design provisions to assure the PRR system remains func-icnal. (90-146)

Attach:nent to T;:I-385C1 June 17, 1988 Page 24 of 50 TU Electric FSAR Change Review Infornation Chapter 07 Page: 2 SER Croup Evaluation FSAR Amended Change Classification Naher Description (Page Numbering ner Am-70) 7.1.2 3 7.1-27-7.1.2 T7.1-2.6 [Am-70] Addition Adds CDC-35 and 37 to "Accumulator M07s* since these are integral ECCS canponents including their instrumentation and controls.

(60-146) 7.1.2 3 7.1-28-7.1.2 T7.1-2.3 [Am-70] Adattion Adds the "UPS Ventilation" to ESF Suppert and Hot Standby Support to reflect the additica <.,f the system to the design in earlier FSAR Amendments. (80-146) 7.1.2 3 7.1-29-7.1.2 T7.1-2.4 [ Am-70] Correction Adds the "EFF Ventilation" to Hot Standby suppcrt. This appears to have been an oversight in the original table. 4Ba-146) 7.1.2 3 7.1-30-7.1.2 T7.1-2.5 [Am-70] Correction Deletes the ESF status monitoring column which has been incorporated into accident monitoring. (30-146) 7.1.2 4 7.1-19-7.1.2 T7.1-2.2 thru T7.1-2.7 [Am-70] Editorial Table 7.1-2 was refor:natted and reissued as Tables 7.1-2.2 through 7.1-2.7 to improve readability. q08-146) 7.1.2 4 7.1-31-7.1.2 T7.1-2.5 [Am-70] Clarification Adds a note to "SSII* to reference the section where it is discussed in more detail. (96-146) 7.1.2 4 7.1-32-7.1.2 T7.1-2.5 [Am-70] Clarification Deletes the "Post" from "Post Accident Monitors

  • to reflect post-TMI changes. (88-146)

Attach:nent to TIX-695C1 June 17, 1963 Page 25 of 50 TU Electric FSAR Change Review Infcrmatlan Chapter C7 Page: 3 i

SER Croup Evaluation FSAR Amended Change Classification Number Description (Page Numbering per Am-70) 7.2 2 4-014-7.2 4.3-10 [Aa-70] Update Berlects that the A*#S rule, 10 CFR 50.62, provides the design requiranents for the CPSES AMSAC equipmer't. (06-329) 7.2 2 7.7-1-7.2 T7.7-1 [Aa-70] Addition Generic I4tter 85-06 requires all Westinghouse near tena operating licensees to establish quality assurance requirements for the non-sa{ety related AIWS equipment which will meet 10CFR50.62 paragraph (c)(1) requirements. The additicc of the AMSAC C-20 interlock to this Table reflects this design change. (88-277) 7.2 2 7.0-1-7.2 7.8-1 thru 7.8-14 [Am-70] Addition 10CFR20,62 (ATWS rule) entitled "Pequirements for reduction of Risk from Anticipated Transtects Without Scram ( ATWS) Events for Light-Water-Cooled Nuclear Power Plants,' requires all PW facilities to have equipment ATWS Mitigation System Actuation Circuitry (AMSAC)) that is diverse / independent fra the existing reactor trip system that will automatically initiate a turbine trip and the auxiliary feed <ater system following an anticipated operational occurrence without a reactor trip. In addition, Generic Letter 85-06 was issued to provide QA guidance for the ton-safety related ATWS equipment. This Section of the FSAR is being addad to describe CPSES's empliance with the ATWS rule and the Generic Letter. (98-277) 7.2 2 7.8-2-7.2 F7.8-1 [Am-70] Addition Adds the AMSAC Actuation Logic System diagram to indL. ate the system logic from input to output. (88-277) 7.2 2 14.1-46-7.2 423-45 [Aa-70] Update The Q423.20 and R423.20 sections have been updated to cross reference the CPSES's summary test program for ATWS (Sections 7.8 and 14.1).

Prior to this update, the ef fects of ATWS were not described in the FSAR. (88-309) 7.2 3 17A-101-7.2 T17A-1 (Shts. 38 and 47) [Am-70] Addition Generic Letter 85-06 requires all Westinghouse Near Term Operating Licensees to establish quality assurance requireenents for the non-safety rebcod AIWS equipna.at which will meet 10 CFR 50.62 paragraph (c)t 1) requirements. The addition of the AMSAC equipnent to this table satisfies the above requirements. (98-270)

J

7.

Attachment to ""CI-a8501 June 17, 1988 Page 26 of 50 TU Electric ' FSAR Change Review Information Chapter - 07 Page: 4 SER Group Evaluation FSAR Amended Change Classificction Number Description (Fage Numbering per Am-70) .j 7.5.2 2 7.5-92-7.5.2 T032.110-1 [ Am-69] t Sht 3) Correction Changes "WR" to "NR*. 188-144) 7.5.2 2 7.5-103-7.5.2 T032.113-4 [Am-69](Sht. 1) Cctrection At CPSES, we do not display ICS Soluble Boron Concentration parameters in the control room. Instead portable instruments are used to obtain this information. (88-144) 7.5.2 2 7.5-104-7.5.2 TG32.110-4 [Am-69](Sht. 3) Correction For consistency throughout this table, delete the phrase "cf usable volume." (88-144) 7.5.2 3 7.5-76-7.5.2 7.5-13 [Am-69] Correction All types D and E variables are not included under Category 2 variables. Containment Radiation Level iHigh Range) is an El variable which is the exception. (88-144) 7.5.2 3 7.5-77-7.5.2 7.5-16 [Am-69] Correction Adds a statement to address the information processing and display interf ace criteria for Category 3 variables. Like Category 2, as minimum, Category 3 instrumentation at CPSES is processed for display on demand. This is consistent with existing Table 7.5-1. (88-144) 7.5.2 3 7.5-79-7.5.2 7.5-21 [Am-69] Correction Safety Chilled water was unintentionally cunitted from the Type D variables list and is now being added. (80-144) 7.5.2 3 7.5-82-7.5.2 T7.5-7 [Am-69](Sht. 1) Addition Adds the new tag ntunber, PT-437, for the third pressure transmitter for the RCS Pressure (WRI. This third channel was added to meet .I the Reg. Guide 1.97, Rev. 2 requirements for diversity for Catagory 1 variables. (88-144)

7. 5. 2 g 3 7.5-89-7.5.2 T7.5-7 [Am-69)(Sht.'20). Addition The accident monitoring variable "Station Service Water Pump Status" was unintentionally omitted from a previous amenchent and is now being added. (08-144) 7.5.2 3 7.5-90-7.5.2 T032.110-1 [Am-69]tSht. 2) .

Addition Adds the new tag number, PT-437, for the third pressure transnitter for the RCS Pressure (WR). This third channel was added to meet the Reg. Guide 1.97, Bev. 2 requirements for diversity for Category i variables. (88-144) 7.5.2 3 7.5-93-7.5.2 TO32.110-1 [Am-69)(Sht. 4) Correction Under Accident Sampling, the upper range for "Dissolved Oxygen

  • and the measured parameter "Ga::ma Spectrut* were unintentionally

Attachment to M -69501 '

June 17, 1958.

Papa 27 cf 5C

'TU Electric FSAR Change Review Information Chapter - 07 'Page: 5 SER Grcup E7aluation FSAR Amended Change Classification Naber Description (Page Numoering per Am-70) omitted from the text in a preytous FSAR amendment and are now being added. (88-144) 7.5.2 3 7.5-105-7.5.2 T032.110-4 [Am-69](Sht. 4) Correction Reflects the correct tem:perature range for the Containment Atmospheric Temperature variablo. t 88-144) 7.5.2 4 7.5-75-7.5.2 7.5-5 [Am-69] Clarification Clarifiss that the key variables are the required information for which backup variables acnitor. (88-144) 7.5.2 4 7.5-73-7.5.2 7.5-18 [Am-69] Clarification Clarifies that the monitored variable for Auxiliary Feedsater Flow is to each steam generator. (88-144) 7.5.2 4 7.5-80-7.5.2 7.5-23 [Am-69] Clarificat ion The word "perfera" is more technically ennet ' nan the word "provide

  • for this application. In general, we speak of equipment performing its intended function as oppcsed to equiptent providing its inteaded f unctiocts. (88-144) 7.5.2 4 7.5-81-7.5.2 T7.5-2, T'.5-3 [Am-69](Sht 2) Clarification Clarifies that the monitored variable for Auxiliary Feedsater Flow is to each steam generator. (88-144) 7.5.2 4 7.5-83-7.5.2 T7.5-7 [Am-69](Sht. B&9) Correction Reflects the correct tag numbers for the ECOS valves. (88-144) 7.5.2 4 7.5-84-7.5.2 T7.5-7 [Am-69](Sht. 14) Correctic-i Reflects the correct tag numbers for the UPS Ventilation monitors.

(88-144) 7.5.2 4 7.5-85-7.5.2 T7.5-7 [Am-69](Sht. 14) Correction Reflects the correct bus identification fcr the 110-130 VAC trasses.

(88-144) 7.5.2 4 7.5-06-7.5.2 T7.5-7 (Am-69](Sht. 15) Correction Reflects the correct tag numbers for the Wind Speed monitoring instrumentation. (88-144) 7.5.2 4 7.5-67-7.5.2 T7.5-7 [Am-69](Sht. 16) Correction Reflects the correct tag numbers for the Wind Direction monitoring icatrumentation. (88-144) 7.5.2 4 7.5-80-7.5.2 T7.5-7 [Am-69](Sht. 17) Correction Reflectr the correct tag numbers for the High lerel Builoactive Ligaid tank Invol instrumentation. 189-144) 7.5.2 4 7.5-91-7.5.2 TC32.110-1 [ Am-69 ] t Sht . 2) Correction Changes the sensor locrtion to reference the ccrrect fiqare.

(88-144)

Attachment to TII-08501 June 17, 1998 Page 28 of 50 TU Electric FSAR Change Review Information Chapter e 07 Page: 6 SER Croup Evaluation FSAR Amended Change Classification Number Description (Page Numbering per Am-70)

References Figure 7.1-3 as the correct figure that shows the senser location for RCS Subcooling.

7.5.2 4 7.5-94-7.5.2 TO32.110-1 { Am-69](Sht. 5) Editorial Changes "al" to "mR*. (89-144) 7.5.2 4 7.5-95-7.5.2 T032.110-1 [Am-69](Sht. 13) Correction Reflects the correct tag numbers for the High Invol Radioactive Liquid Tank Imvel instrumentation. (83-144) 7.5.2 4 7.5-96-7.5.2 T032.110-1 [ Am-69](Sht. 14) Correction Reflects the correct bus identification for the 110- 130 VAC busses. (88-144) 7.5.2 4 7.5-97-7.5.2 T032.110-1 [ Am-69](Sht. 17) Correction Reflects the correct tag numbers for the Wind Speed monitoring instrumentation. (88-144) 7.5.2 4 7.5-98-7.5.2 T032.110-1 [ Am-69](Sht. 17) .

Correction Reflects the correct tag numbers for the Wind Direction monitoring instrumentation. (88-144) 7.5.2 4 7.5-39-7.5.2 T032.110-1 [Am-69](S t. 18) .

Correction Under Accident Samplings, the upper range for ' Dissolved Orfgen" and the measured parameter "Gamma Spectrum: were unintentionally omitted from the text in a previous FSAR amendment and are now being added. (88-144) 7.5.2 4 7.5-100-?.5.2 T032.110-2 {Am-69] Correction Reflects the correct tag numbers for the ECCS valves. (800-144) 7.5.2 4 7.5-101-7.5.2 T032.110-2 [Am-69](3ht. 6) Correction Reflects the correct tag cumbers for the Main Feedwater Isolation valm Status. (88-144) 7.5.2 4 7.5-102-7.5.2 T032.110-2 [Am-69](Sht. 11) Correction Reflects the correct tag numbers for the UPS Ventilation monitors.

(88-144)

Attcchment to TZZ-89's01 June 17, 1999 Fage 29 of 50 TJ Elec ric FSAR Change Review Information Chapter : 09 Page: 1 SER Croup Evaluation FSAR Amended Change Classification NJmber Description (Page Numbering per An-70) 6.3.1 3 8.3-131-8.3.1 8.3-13 [Am-69] Revision Clarifies what is meant as a "bus fault

  • and reflects design change to allow the diesel generator circuit breaker to close autcznatically in the event of a single line to ground fault coincident with a safety injection sigial. The ground f ault currett is minimal

.nd will have no adverse effect on the continued operation of the diesel generator. The desip change increases the availability of the diesel gecerator during the desiga accident. (88-160) 8.3.1 3 a.3-135-8.3.1 8.3 21 [Am-69] Correction Corrects description of diesel generator *non-DBA* trips to reflect the design basis documsatation and as-built plant. Corrections to items "c" thru "m* Lavolve updated names.clature. The Engine / Turbo

( high vibration trip is split into two separate items. Three trip.

are added: Lef t or right bank tuzto low oil pressure, generator j overexcitation, and generator neutral ground overcurrent. (89-161) J.

Correction I B. 3.1 4 8.3-132-8.3.1 T8.3-1A [Am-70](Sht. 3)

Corrects description of isolation transformers to "TXEC 3 & 4*,

since they are not solely used for the Technical Support Center and the transformei equipment number is more specific. (88-294)

.Atta h==nt to T31-83501 June 17, 1983 Page 30 of 50

'IU Electric FSAR Change Review Information Chapter - 09 '.Page: '2 SER Croup Evaluation FSAR Amended Change Classifiration Number Description (Page Numbering per An-70) -

8.4.5 8.3-1.3-6.4.5-E~ 8.3-51 [Am-70] Revision Adds current transformers to the list of acceptable isolation devices for isolation between Class 1E primary circuits and ncn-Class IE secondary circuits based on testing. (88-357) 8.4.5 3 8.3-134-8.4.5-E 8.3-95 [Am-70] Addition Adds reference to the test report that supports the use cf current transformers as isolation devices. (88-357)

J Attachment, to TZX-68501 June 17, 1988-Page 31 of 50 TU Electric FSAR Change Review Information Chapter = 09 Page: 1 SER Croup- Evalaation FSAR Amended Change Classification Number Description iPage Numbering per An-70) 9.2.1 2 9.2-085-9.2.1. 9.2-2 (Am-69] Revision Revises the Station Service Water Systaa outlet temperature to 133 der;rees F instead cf 120 degrew F based on the recent system calculattons. (88-153) 9.2.1 9.2-066-9.2.1 9.2-4 [Am-69] Clarification Clarifies the existing sentence to say that only component c,m., ling -

water beat exchangers uses a cleanliness f actor of 80% and other heat exchangers served by Station Service Water allow some fouling.

(88-154) 9.2.1 4 9.2-007-9.2.1 9.2-4 [Am-69] Clarification Clarifies t at the reservoir water is corrosive based on stability and saturation index twhich includes scale-ferming tendencies at low indexl. (88-118) 9.2.1 4 9.2-0E8-9.2.1 9.2-5 [Am-69] Clarification Clarifies the system opera-ton under normal unit shutdown made that two trains are used fcr normal cooldown of each unit. (68-153) 9.2.1 4 9.2-089-9.2.1 9.2-6 (Am-69] Correction Revises to include the recirculation phase operation of Station Service Water and to be consistent with the third paragraph of Section 9.2.1.2.4. (88-118)

I

,I)< 1 n

o i

t a

c 2 i f

i s

s e a n g l o a C i P t a c g e n r a r h o C C e

l pss mdi adh sat md .

e nm t ae s t yms 9 sey 0 gs t s nyd r

e i

l pw sT, 3 t

p mce aCh3 a s t -

h e e

._ C th

- nt o rn e f df .

i o" t 0 c As 7 cs" m

ap on u

n A t oie o sL ah i r o rt t e pd t a p r o m t af t r

o g

n nuo ag e k

r a

i r

e

]l 9 of 6 oaot esa p b - cs i

w e

N m

u m

A rn

[ ood l

o a.

v t nrt e e g

7 c an R 1 aeue a - eh gt e P 2 rt er g ( f e c

a d

en 9"*caav sd h d o dh r a C

R ni et mp ntf a ha e

t A Ai 5 es "r n S r 1 t eoe F R c - el t As S e FD

2. l o eot o.

9Dct 2

2 n

i o 9 t

ar ue l b 6 am vu 2

1 EN 9 0

5 0

8 I

Z T p o t. 3

- e o S r c G i

m p o

. f r t

a72 c h1 3 e c l 2 aee E t ng M 2 t ua U E A' P T S 9 ll:Il, lt ll lIi!l i

Attachment to T n-89501

' June 17, 19H Fage 33 of 50 TU Electric FSAR Change Review Information Chapter + C9 .Page: 3 SER Croup Evaluation FSAR Amended Chenge Classification Number Description (Page Nunbering per As-70s 9.3.1 2 9.3-037-9.3.1-U 9.3-3 thru 9.b13 [ Am-69 ] ' Bevision The Instrument Air System (IAS) design has been changed to incorporate rotary air canpressors as an additional system capacity is warranted. This change in design includes the rotary air compressors and their various components. Also, the component description, systen operation, instrunectation and pcwor supply sections have been changed to reflect this system design change.

(88-128)

SER Impact:

) As a result of this change, the SEP Section 9.3.1, pages 9-15 and 9-16, paragraphs 1 and 2, need to be revised to reflect the current ,

design of Instrument Air System which adds additional compressor caoacity to the system.

i 9.3.1 3 9.3-040-9.3.1 9.3-8 [Am-69] Revision Deletes the "Pressurizer PORV's" as these PCR7's are supplied by nitrogen accumulators. (88-1286 9.3.* 3 9.3-041-9.3.1-U T9.3-1 [ Am-69] Revision Adds the Rotary Air Comprecor packages and associated equipment

data and revises the exis' ing data in the table for Beciprocating g Air Compressors and assoc -ted equipment, (See Evaluation no.

.i 9.3-037-9.3.1-U) (89-126 j

j 9. 3.1 1 9. 3-C 42-9. 3.1 3 .3-3 [Am-69] Sevision Deletes Pressurizer POBV from the table as it is supplied by nitrogen instead of Air, ISes also 9.3-C40-9.3.1) .

(88-128) 9.3 1 4 9.3-036-9.3.1 9.3-2 [Am-69] Editorial

, Corrects a typographical error. Changes "31.3* to ANSI B31.1.

(80-128) 9.3.1 4 9.3-039-9.3.1 9.3-6 [Am-69} Clarification Changes ft3, min to Actual ft3/ min (ACFM). (68-128) t

< 9.3.1 4 9.3-039-9.3.1 9.3-6 [Am-69] Editorial Corrects the typographical error. Changes "21.3" to ANSI B31.1 and daletes Petroleum Refinery Piping. (88-128 I

ill)I' 1I n

o i

t a

c 4 i f

i n s o s i e: a t g l a a C c P i e

g f

i n r a a h l C C s

% wn 0

5l i oo' et tb a l a

d u d nc 9 eal 0 n a i) C a2 t 1 d r

e n- e i4 s' t a i p m9 v a e h seR C il b n yao tT

) i d 0 d ee 7 i es r

- ms u4 b a

n A h i

o r mos,n t e oin a

s p ot o

rai r g rt o n l ei opd f i I

n r e

ron o t

b nf c w m oo y e

t N u c sc r een e F

e e g hd t o g' e P a

t mre g ( } al m n d 0h ae a en 7 t mrg h d o -

C ni et A msoneni)

R mp [i r2 A Ai f gu1 S r 9i nd3 F R c - ri -

A s S e FD 4.

9Cd5 lar%8 u08

(

1 4

n i

o 9 t 0 ar 1 ue l b 1

an 4 v :u 1 EN 9 0

5 8

3-2 2

T p

. o u 4

_ t80 o

- 8 5 r

- 9 c C t1 f i n r e ,o t m7 4 c h1 3 e c l 1 aep t n E

R 4 _

t aa E AJP J'T S 9 llll1' iI !!!

):I1iIl, n

o

- i t

a c

5 i f

i s

s e

g a l l

a C a P i e r g o n t a i h d C E g

n i

l o

o c

m e

t 9 s 0 7 S

s g

r n e i t n p e a i h t C i d

t) o4 C6

0) 0 7 r -

i9 A8 n

c h S 1

i r P .

t e U r a p o n:

r g er h r

/

f o n i

t e n r rg I e on b f i w m t e u sf i N ea v nr e e g id R ]l a t e P 0 nc g ( 7 i e n d - ar h

a en d o mrr Ado C ni [ c et mp e

R 5 h o A Ai r 1 t t S -

F R c As S e

4. sld i 9d o FD FA c 5

4 t

o 9 i -

t 2 ar 1 ue 1 l b -

amu v

4 1 EN 9 0

5 e

E X

Z T p o- u 4 t80 o 95 r t1f 9

i c G n r e ,o t m7 5 c h13 e c l 5 aee E t ng t ua J R 4 E

AJP T S 9 l Il\\t [ i :lll!ll l l rI lllr . l,

+ S f

Attachment to TII48531 Jane 17, 1988 Page 16 of 50 TU E1xtric TSAR Change Review Informatica Chapter . 09 Page: 6 SER Cro'ap Eva14a, ton FSAR Amended Change Classification .

Number Descriptica iPage humbering per Am .'O) 9.4.6 1- 9.4-111-9.4.6 F9.4-12 [Aa-70] Bevision Revises the figure to reflece a:e following changes as per as-built:

'1. Adds thersel relief valves en sarety-related chilled water recirculation pump discharge lines for the overpressure protection of the systen. (88-068)

2. Misc. technical changes such as relocation of lines, valves and pipe breaks, and additicn of flanges and vent valves. (88-056)

I l

l

- -. .. .. a

Attach: Dent to TC-685C1 Jane 17, 1993 Page 37 of 50 "U Electric FSAR Char.ge Review Information Chapter C9 Page: 1 SF.R Group Evaluat;cn F3AR Amended Change Classification r; umber Deu:ription (Page Nur.berug per Am-701 9.5.1 3 14.2-43-9.5.1 T14.2-2 [Am-70](Sht. O and SA) Correction Prcytdes description of tort methods fcr new f ue water supply l

system. References Fire Protection Repon instwad of Technical l

Specifications for acceptance criteria. Organt;;ational title update. (88-235) l l

At tact.:iont to TII-68501 June 17, 1999 Page 30 of 50 TU Electric' FSAR Change Review Information Chapter 09 Page: 6 SER Croup Evaluation FSAR Amended Change Classification f; umber Description (Page Numbering per An-706 9.5.3 3 9.5-250-9.5.3-0 9.5-138 [Am-69] Revision Deletes AC Essential Lighting System from verification during the periodic diesel loading test. The AC Essential Lignting System has been reclassified as non41asa 1E. As already stated in FSAR Section 9.5.3.2.4, "The AC essential lighting is used on a day-to-day basis to provide apart of the ordinary operational lighting.

Therefore, periodic tests are not required." During diesel generator

) seqaence loading, AC essential lighting panels are a base load dependent on feeder breaker alignment prior to diesel generator sequence loading. Breaker aligruent actually verifies onsite standby AC power being available to the AC Essential Lighting Syste, not the periodic diesel loading test. - (68-167)

I l

1 l

Attac.*tnect to C -48501 Jane 17, 1900 Page .39 of 50 TJ Electric F3AR Changs Pe71ew Infarnation Chapter 09 Page: 9 SER Croup Evaluation FSAR Amended Change Classification Nur.ber Description (Page Numbering per Am-70) 9.5.4 2 9.5-251-9.5.4-V 9.5-139 [Am-70] Revision Deletes *30% diesel generator set efficiency

  • and replaces it with "Fuel Consumption based on test data". No basis can be identified for the assumptim used for 30% diesel generator set officiency.

Actual basis is the test data, which is increased by 3450 gallons to permit periodic testing of diesel generator. (88-311) 9.5.4 3 9.5-252-9.5.4-V 9.5-142 [Am-70] Revision Changes "1% add for fuel-oil storage tank capacity" to 3450 gallon margin based on test data. This permits periodic testing of the diesel generator. (08-311) 9.5.4 3 9.5-253-9.5.4 9.5-143 [Am-70] Revision Add tech spec requirements for diesei generator fuel oil in addition to the requirements cf ASIM D 975. (88-311) 9.5.4 3 9.5-254-9.5.4-V 9.5-144 [Am-70) Revision Changes the reference from *IEEE 338-1971* to *NFC R.C. 1.137*

for the fuel oil storage espacity of seven days of operation of the diesel generator at rated load. (98-311) 9.5.4 3 9.5-255-9.5.4-V 9.5-144 [Am-70] Revision Changes the ~15% margin

  • ts *3450 gallons margin" to allow for periodic testing of the diesel generator. (See also evaluation no. 9.5-252-9.5.4-V). (80-311) 9.5.4 3 9.5-256-9.5.4-V T9.5-11 [Am-70] Revision Changes the 'in margin
  • to "3450 gallons margin
  • to allow for periodic testing of the diesel generator. (See also evaluation no. 9. 5-252-9. 5. 4-V) (88-3111

AttCrlunent to TXI-88501 Jane 17, 1988 Page 40 of 50 TU Electric FSAR Change Review Infazination Chapter : 10 Page: 1 SER Group Evaluation FSAR Amended Change Classification Number rescription iPage Numbering per Am-70) 10.3.1 2 10.3-032-10.3.1-N 10.3-3 [Am-70] Revision MSIV actuators are designed to ASME B&PV Code Section VIII in lieu cf ASME B&PV Code Section III as per ASME Code Section III subarticles NA-1120 & NA-1130 468-055) 10.3.1 3 10.3-035-10.3.1-N T10.3-4 [Am-70] Revision Bevises the MSIV actuator design to ASME B&PV Code,Section VIII, in lieu of ASME III as per ASME III subarticles MA-1120 and NA-1130.

(See also evaluation no. 10.3-032-10.3.1-N). (88-055)

Note: SER Section 10.3.1, page 10-4, para 2 states that, "MSIV actuators are designed to Quality Group B". The M31V actuators are designed to ASME B&PV Code Section VIII.

10.3.1 4 10.3-033-10.3.1 10.3-6 [Ae-69] Clarification Clarifies the capability to operate the Power-related relief valves during safe shutdown earthquake coincident with loss of offsite power. (89-111) 10.3.1 4 10.3-034-10.3.1-A T10. 3-3 [ Am-69 ] Correction Corrected the lower limit for natural cooldawn from 125 psia to 100 psia. This change was inadvertently left out in Amendment 66.

(See evaluation no. 10.3-006-10.3 1-A, Att. 2 of TXX-88467, page 345)

(88-111) i I

l I

' l1 l1l' y

_ n

_ o i

t a

c i

2 f

i m r r

s 2 p l a t a~

c n

& C

_ P o i

_ e g

i f

_ s i n i r a v a h e 1 C R C e

rr s ue st t

r sa a

. ew t s

rd

- pe e o ef t g u ry a ar ~

h a a 0 ci p 1 sl n ii u s

- dx p) u 7 r - a r4 e w e2 t

p on l e t -

a8 a v w8 h ei d(

C hr) e td2 e .

3 f s

~

~

)

", or2 - ys i

0 t t 8 ra 7 a o8 ab

- h m( i m t l n n A h . i g i

o r ecn t ag xi us t e aei ae a p c s d m g i re e r dod h m o n nf g

t e f . i i t n r d n t s ay I e oei b tdt h s w m i s t e ru evi yF W i

v t cox nre f A e e ep i R g a ] nyo t n

] ah re eg P 9 el 9l t

( 6 snd 6 c n

me oes d - - n h

a en d o Ah ea moo At C ni [ t rb ( d et mp a ee A

R Ai 9 6 e s s ", 8 gs 8 na S

T R c r

4 sms i rp 4 h ab As S e ram cer 0 el u 0 FD 1 P ap 1 A a 9 9 4 4 0 0 n 1 1 i

o - -

1 0 t 9 9 ar u 0 0 4

ae l 4 v  ;

0 0 1 E; 1 1 0

5 8

4 X

Z T p o u 2 4 t80 o 85 r t1 g 9

i c G n r e ,o t n7 1 c h1 4 e 9 9 c l ta re. eg E P.

4 4 t ua U E 0 0 AJP I S 1 1 lr i l ,l!! , , I1l lill l lt r1ll

P Attad.mont to T.*0t-60501

! June 17, 1983 Page 40 of 50 W Electric FSAR Change Review Infomation Chapter s 13 Page: 1 SER Croup Evaluation FSAR Amended Change Classification Number Description iPage Nuzbering per Am-70) 13.6 3 1AB-26-13,6 1A(B)-7 (Am-69] .

Eerision CPSES com: plies with the criteria ct Reg. Guide 1.17 by tmplementing the criteria of AflSI/AIG 3.3-1982 which supersedes APEI !!18.17-1973 (08-156) i 4

1 i

i i

'l 4 ,

1

-l

l lll' 1 1I11I ll!\l 3

n o

i t

a 1

c i

f i

s s

te g

a l

a C n P o eg i

t n ' i a d h d C A g

n i

t s

e t

l a

4 n 1 o i

t a

r r e p e

t p o a e h r C p e

h t

0) 7 e9) t 0 n: a3 n A c-o i8 i r 3) d8 t e 6 n(

a p i _

d m

r o

g n

non.

at e f i t I

n r e

2

.l ep b b s w m sa e u t t e i N h h r S st n e g

(i R ]ht or a

e g

P C f

( 7 o n d - t s a en m t h d e ACn C ni [ e R

et mp 2 Gm J e A Ai - t r S r 2 i F R c su A s 4 d q S e 1 d e FD TA r n 4 o 1 i -

t 7 es ar 4 ue -

l b 2 am vu 4 1 EN 1 0

5 0

0 m p o 2 3 t80 o 6 5 r 9

t1 f i c G n

e ,o r

t m7 3 c h1 4 e c l aee t ng E

R t ua U E 4 AJP T S 1 l, ll 1lll 1tIfll ll !!l;1l1llllillll !l

llllll 14 1Ii T

Yw w

n o

i t

a c -

1 i f

i s

s e a n g l o a C i P t e

g ce n r a r h o C" C 4

8 2

_ 5 1

_ M d

n a

5 3 1

. 5)

_ . . 8. 7 22 r -

_ e 5 S t

p .

1 Ct

_ a s

_ h a .

C c6 i 6 t

ct

_ on

0) Se n 7

- f d n

m on A e o l m i r l A t e a a p s m g 1di r 9 n o n 6- ad e f i n r m2 t I e A e w

e b

m u

[

1

8. el i N 3 2. d

- - 5 y e e g

2 1 l R t a 5 nn e

g P 1 oe

( i t n d ut r a en rce h d o h ev C ni t Sd at np a 3 Ai 9 f n 2 oi

. r -

F R c 2 t e A s rr S e 5 ae FD 1 P w 6

3 5

n 1 o

i 0 t 3

_ ar 0 u e -

l b 2 am vu 5 i

_ 1 Ef 1

_ 0 5

8

_ 6 U

T. - p c u 4 t30 o 95 r 9 c C t 1f i n ,o r e t m74 c h1 4 e 5 c l aee E 3 t ng R t u a U E 5 AJP T S 1

n i

o t

a r

2 t f

i s

s e a g l a C P

e g

e t

n a a dp h

C U e

h t _

g n

i n

5 r) e?

c7 n2 o-c9

r. s(

8 t

p e a

h c.

r s. w C et r r.

f ee e m

0) r r.

7

- - d ch m n n A ang o r i n i t e p

os a i e m td r g a f

o n i ]

me r s

- r 3 ou n

I e 7 f o b - nh w mig e m A n i J [li t

v at e e 2 r. s R g a 8

- toe W e

g P t i 5 id n d 1 d n a en d a h do a C n? d. .

e et a sl R mp eu A A 1

- id r S 'r.

F F c v3 A s C. oW S e 5 rT FD 1 PA 9

3 5

n 1 o -

i 1 t 0 a r C u e -

l b 5 aa vw E H 5

1 1

p o u t c c-r

-- 5 5

- mm

+

t wa A w' c

v o

- , , . __ h R - L _ W h? L [

A r*M

< V. .L

~.

,/ ;

Attachment to T"Ja el June 17 1988 Page 46 cf 50 TJ Electra. FSAR Change Review Information Chapter 15 Page: 3 SEP c rep Evaluation FSAR Amended Change Classification Nmter Description (Page Numbering per Aa-70!

15.4.4 . 2 15.6-050-15.4.4-M 15.6-6 thru15.6-19 [Am-7C] Re*ision Provides accident description, analysis methods, and analysis results for the revised :lesign basis steam generator tube rupture analysis. (See also evaluation no. 15.0-00*-15.4.4-Mi REF: RXE-88-101.

(88-149) 25.4.4 2 15.6-052-15.4.4-M T15.6-1 [Am-70](Sht. 1) Addition Adds sequence of event,- for revised design for the basis steam generator tube rupture analysis. (See also evaluation numbt'r 15.6-050-15.4.4-M)

(88-149) 15 4 4 2 15.6-053-15.4.4-M T15.6-2 (An-70] Revision Modifies to reflect design basis for the steam generator tube '

rupture analysis. Also deletes the realistic casa". (83-149) 15.4.4 3 15. C-033- 15. 4. 4-H 15.0-24 and 15.0-25 {Aa-70] Additiu Adds description of RE"RANO2, the emputer code used for the SC':9 analysis. Ref: PIE 58-101 (68-149) 13.4.4 3 15. C-005-15 . 4. 4-M T15.0-2 (Am-70](Sht 5) Update

'Jpdates to reflect revismo design basis for the steau geserator tube rupture analysis. (88-149) 15.4.4 3 15 J 4 7-15.4.4-M T15.0-4 [Am-70](Sht. 1) Mdition Adds Note a and limiting trip point for low pressurizer pressure to reflect r-vised design basis for the steam ger.arator tube rupture analysis. (G8-149)

15. 4.4 3 15.0-000-15.4.4-M T15.0-6 (Am-70](Sht 5) Revision Modifies to reflect revised design insis for the steam generator tube rupture analysis. (09-149) 15.4.4 3 15.0-009-1).4.4-M F15.0-24 { An-70] Revision Modifies to reflect revisad design baats for the staan generator tube rupture analysis. (88-149) 15.4.4 3 15.6-055-15.4.4-M F15.6-3 thru F15.6-3C [Am-70] Revision Modifies to retlect revised design basis for the steam geaerator tube rupture analysis. (see evaluation no. 15. 6-050-15. 4. 4-M) . (98-149) 15.4.4 4 15.0-002-15.4.4-M 15.0-10 [Am-70] Editorial Modifies to be consistent w *h SCTR assumptions. (60-149) 15.4.4 4 15.0-004-15.4.4-N 15.0-27 [ Am-70] Addition Adds reference for RETRANO2, the c m puter code used for the SGTR analysis. (00-149)

l lj

~

~

q s

E

~

n o

i t

a 4 i c D f 4 i

s s

e:

g a

l a " n n P o o e i i a.

g t t t n i i s.

a d d d, h d d C A A  :

4 e

b r u o

t t

a r r o e t a

a 6 r g e t

m e a g e

t m 5 s 9) a 1 4 e e 1 t

  • h - s t 9 r 8 e e r ( h t

p c .

t f

a 1 r h s 0 o C i s

1 f

a 8 i

s b 6

- s

0) n E a 7 g I b

- i R n s n n A e , g .

o d ) s i i r i s t e p d9 s e a e4 y d m g s1 l r i - a d f

o i

n v8 e6 n

a e) s9 n r ra i4 I e R v1 b t . T e-w e m u

cs C r6 ei S 6 i N l s t (

v e

f y r c e g el o e .

R a

ra f l s

] n ] ]f i e P 0 oa 0 e 0 es g ( 7 t 7 c 7 r y n d - e - n - l a en m1, r u

me moa h

C d o ni et A

( tet p A r

[ e f

(Ats na R mp 3- ou 6 e 3 ee A Ai 4 r - i r S r - f u F R c G. se Nr s 4

it A s 5 db 6. d 5d p S e 1d u 5 d 1 ou FD tat 1A TMr M M M 4 4 4 4 4 4 5 5 5 n 1 1 1 o - - -

i 6 1 4 t 0 5 5 a r 0 0 ue 3- - -

0 6 6

'a. bm vu 5 5 5 1 EN 1 A 1 0

5 3

8 I

Z T p o c 4 4 4 t 80 o 3 5 r 9 c C t.r 1 f n e ,o t a77

- c t1 4 e 4 4 4 c l aee E 4 4 4 t ng R t ua U E 5 5 5 AJP T S 1 1 1 7,

y f f i , Ii lIl il

7],

Attach:nont to TZX-68501 June 17, 1998 - -

Page 43 cf 50 TJ Electric FSAR Change Pv71ew Information Ch.spter 17 Page: 1 SER Group Oraluation FSAR Amended Change Classification Naber Description (Page thanbering per ha-70) ,.

17.2 3 1AB-38-17.2 IAqB}-16 [AM-70] Bevision CP3ES* position on Beg 21 story Guide 1.39 is upd.sted to provide a ' site wide criteria for Housekeeping control for design, constructicn and operational phase activities. Previously our comritment applied to operational phase activities only. (36-290) 1 1

1

_ _ _ . 4

e ,

f I

Atttet:mont to Tri-Ge501 June 17, 1988 Page 49 of 50

~

~ TC Electric FSAR Change Review Information Chapter 17 'Page: 2-SIR - Croup Evaluation FSAR Amended Change Classification N eber Description (Page Naabering per An-70) 17.3 2 17.2-C40-17.3 17.2-33 [Am-69} Revisto:2 Change provides a calibration program flexibility by allowing the use of an alternate accuracy criteria for the 4:1 accuracy ratio. This criteria will be used when the 4:1 accuracy ratio is not reasonably achiev41e. During such times, Joceentation is required to ensure that the assumptions used in the setpoint methodologies for the cailtration error are not violated, or that .new setpoints are established. This documentation will ensure that.the accepted safety related margins are not reduced. (87-237)

17. 1 4 17.2-041-17.3 17.2-3 4 [ Am-o9 ] Clarification Change the wording to more clearly adiress that replacement of items during performance of normal maintenance activities is accomplished by scrapping the old iten and replacing with an acceptable iten. tkmconfo.aing items are marked and segregated, when required, in acecrdance with station procedures. Changes

, the wording from "Station phres required marking and segregation j of nonconforming items and also require .. ." to "Marking and segregation of ncn e forming iteac, when required, are addressed in station procedures. In addition, station yocedures requde

..." (87-463) m

F- Attachment to TII-88501 Jane 17, 1939 Page 53 of 50 TJ Electric FSAR Change Feview Information Chapter ? 22 Page: 1 SER Croup EvrItation FSAR Amended Change Classification Number Description (Fage hring per An-70) 22.2 3 TMI-0 44-22. 2 I.C.9 [ha-70) Addition Allows the independect verification of safety related components, being removed from and restored to service, to be a completed by a licensed operator or an auxiliary operator quelified in that specific area. This change permits better utilization of available manpower while maintaining assurance of proper sy ;em status afforded by an independent verification. Previously the 'j FSAR had not identified who should perfom the independent

  • verification but plac procedures and SSEB-1 had identified licensed ..

operators. (80-169) l l

t t

l

-ts k

t

)

I f

i i

r k

i

-I 5

v-- e s ,,w w- -w = e , . - - , , - - - .- iwy w w r r- . 1 -. . - ----a-.--- .+, - - - - - - -- -. . - , , e

Retrieved from "https://kanterella.com/w/index.php?title=ML20155K607&oldid=3042555"