ML20245J320

From kanterella
Revision as of 19:59, 14 February 2021 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Forwards 751003 Ltr Releasing Proprietary Drawings E-87, E-88 & L-89 Designed by General Atomic Co/Sargent & Lundy. W/890627 Release Ltr & Two Oversize Drawings
ML20245J320
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 10/03/1975
From: Walker R
PUBLIC SERVICE CO. OF COLORADO
To: Boyd R
Office of Nuclear Reactor Regulation
Shared Package
ML20245J316 List:
References
10753, NUDOCS 8906300267
Download: ML20245J320 (7)


Text

jut 1 27 '89 10:06 PAGE.02 )

6 e z y%'

"g.

- [hdslie Servke Company :f C.l.:.n.de

\  !

Octater 3, 1??5 g ptope vi;Yt.s ..ir>< j

,' , $ !. i' g- hl Vtyr a . %j jQ -a Director 5f Nuclear Reactor Regulation k-  ; '

D

'lt Divi". ion of Reactor Licensing \' 'S D .

U.S. Nuclear RecJ1atory Comission ' , 'A g

. ,E . ."

Attention: Mr. Roger 5. Boyd, Acting Director

Dear Mr. Boyd:

Docket No. 50-?67 s

Drawings submitted with my letter of September 5,1975.

and with a letter Frederic E. Swart to Robert Clark Division of .

Reactor Licensing, dated September 17, 1975, were marked

Proprietary " Attached is a co:V of a release of the pro-prietary assignment on Gereral Atomic Company /Sargeant and Lundy Drawings E-87 E-88 and L-89.

Yours very. truly, E .%* LL) .f&

  • R. F. Walker Vice President Engineering and Plamaingr RFW/mm n Attachment ,
s. 7,,r, 51 !J ?s' 4
.~ 'cs l ~.,;- .SIQ*

.1 Cc~ ~7 A ,pg

[. e i, M

(p) rEr '

\N < ;N('~'!$ "5 ',

OM292 ,

s.

I 8906300267 890615 l

{

PDR ADOCK 050002o7 PNV

^

F .6753 b

r-- ..

~

JUN 27 '89 10:06 PAGE,03

. f.',

T$. .),ff, E " .c ,

j, 1'

$K , . ., B $

. C. t Qt, s .c g . ei

./

,Ysl.-s7 .

.y

- - - -- ,a , . . .

. ,9 crt.rnu c n:::umn P.O. Box 426 Platrevi21e, Colorado 90651

[u".N786n.sensa m.:

tric auxoo October 3, 1975 Project 90-330 Ef HTCR Fort St. Vrain Unit 1

  • yCLP-949

. a i Mr. J. H. Reader, Resid2nt Engineer Fort St. Vrain Nuclear Generating Station 't Public Service Company of Colorado i P.O. Box 361 Flatteville, Colorado 80651 .

I

Subject:

Release of memoringa E-47, 88, a b .

89

.: Dooe Mr. Reeder: 3 Ve have reviewed Drsvings E-87, 88, 89 which indacate the cable tray system and conclude that they are not proprietary. These driatings can therefera be released to the U.S. Nuclear Regulatory Caumissier.. ,

Very truly yours,' ' < -'

7 4

$w John . Zanet h y.

traject passeer 7

,', Jaz/jee .

... es: J. M. h ase A. Mathan

.. i i

e 2 _3

'?

jd.c

. S

' 2 E

-e 1

l l

n mavue no m ou m com m "  ;

--w- ----

? $

[

(?

c,3

. WSW y g

?)

A p),

~(A& 04 r i f

12 y:

1-s A pw %

aan e jo f/-f de . -

_ 4 1

..____._________.______._____._______.__________--_-__J

e ) GjQ $ c r; 7 r r 7 e. "

/f

~Q A 1 cu w&

-ah e P4 m 72 A

y A&w@

Qa. ne ,

D fl-f Ae . _

w'* .Q

- 3 a

  • m_

FORT ST. VRAIN NUCLEAR GENERATING STdTION PubilC O$9fVIC9e PUBLIC SERVla2 COMPANY OF COLORADO CN/TCR/SCR/PC/TR <

No.EE-r#-m w A ,1 SAFETY EVALUATION PORC 8 3 4 JUN 141989 PAGE / of 4

\

All GOHY s

O CN QVSRALL C CN SUBMITTAL O SETPolNT CHANGE REPORT O TEST REQUEST O TEMPORARY CONFIGURATION REPORT O PROCEDURE CHANGE (FSAR) __ % OTHER CLASSIMCATM)N: ARE THE SYSTBMttl EQUtPMENT OR STRUCTURES INVOLVE 0,0R DOES THE ACTIVfTY AFFECT:

CLASSI hYES O NO ENGINEERED SAFEGUARD D YES S NO

$ APE SMUTDOWN @YES C NO PLANT PROTECTIVE SYSTEM C YES 3 NO SAFETY RELATED @ YES C NO SECURITY SYSTEM C YES E NO l REMARKS i V At U A TBON s Us.e Addelsort.nl Sticots 'If Requared

1. DOES THIS ACTIVITY AFFECT STRUCTURES. SYSTEMS, COMPONENTS EQUIPMENT, TESTS, EXPERIMENTS OR PROCEDURES DESCRI8ED IN THE FSAR OR TECH SPECS? %YEs O NO LIST THE APP'lCABLE ESCTIONE REVIEWED: NAd bre /e' a b /1 ** FA,4, I ' #A. 4,4 'i F/ f. 'f '. -

FP L 4 ' PP. L I *. Cf&r ffoR -J '. FActL- 9 7 fport.-.ib ', FPvA f lf

  • fAM'- /2 h gg_ g - - - <

/

~T;ala hru.' .L L CS 4, J . .L , 4,14 , +, / o. .T , 4, /0,'?

.( I? '1 L 1. 6, s'. /Ce lb ,, C. NO {T

2. DOES THE ACTIVITY REQUiME THAT CHANGEIS) BE MADE TO THE FSAR on TECH S EC? O YES fd N UST SECTIONE TO BE CHAP $fsED AND THE CHANGES TO DE MADE: '/~2 J A c Iv */w d > M L Af v1O J ea kr ms;ds,uol Ka beewa b:a a :s h +/,a tol/ca% :.%4,V pfA.5.1.I

% /a s CA 4. 3 - l A . FF 4. 5 - 4 A . FP, 4.1 -& A ', FP4.@ -D A . FA 4 . 3 -)/ A' . ' '

FatA *fL,-l j FP64 - N 8.4 s ll ,

3 OETERMINE WHETHER OR NOT THE ACTIVITY INVOLVED 15 AN UNREVIEWED SAFETY QUESTION UTILIZING THE FOLLOWING GUIDELINES:

(A) HAS THE PR08A8tLITY OF OCCURRENCE OR THE CONSEQUENCES OF AN ACCIDENT OR MALFUNCTION OF EQUlPMENT IMPORTANT 70 S AFETY PREVIOUSLY EVALUATED IN THE FSAR BEEN INCREASED?

O YES [NO STATE B ASl$ L 32# ATMCMfbi (5) HAS THE POS$18tLITY OF AN ACCIDENT OR MALFUNCT:ON OF A DiFFERENT TYPE THAN ANY EVALUATED PREVIOUSLY IN THE FSAR BEEN CREATED? O YES E NO STATE BASIS. f8f M TW C NE D -

(C) HAS THE MARGIN 0F SAFETY. AS DEFINED IN THE 8 A$l$ FOR ANY TECHNICAL SPECIFICATION OR IN THE FSAR BEEN REDUCED?

O YES E NO STATE B ASIS: -I81 A T N f # /I b ' __

00ES T I ACTMTY APPf.AR TO: INVOLVE AN UNREVIEWED SAFETY OUESTION O VES M:INo gy , / PPROVED M ; b,h,, * = ' I/ # I g

n , - -

__--__1rnram __

RAFETY ETALtfATIAN.701.II.PD. AA11 RET. I BASE 2 89 (

RAMGROUNk Thl Engineering Evaluation (EE) was written to address the adequacy of Bearing Water Pump P-2101-S to be used in place of P-2101 or P-2106 in Shutdown /Cooldown Train A while meeting the requirements of 10 CPR 50 Appendiz R criteria as further stipulated in the PSV Fire Protection Program Plan (PPPP),

M .

PSAR Section 9.12 refers to administrative procedures designed for fire prevention. Also, contained in the PPPP, Fire Protection Operability Requirements (Fp0R) exist to provide regulation for fire suppression and detection systems, systems for fire protection shutdown /cooldown of the reactor and mitigation.

PPOR-16 provides operability guidance for Fire Protection Shutdown /Cooldown Trains A and B. P-2101 and P-2106 are utilized in Train A to provide a bearing water supply to the heilum circulator used during shutdown /cooldown. The criteria used for shutdown /cooldown train equipment involves proper separation /segregt. tion between equipment and cabling of different trains as specified in 10 CPR 50 Appendiz R, as applicable to PSV per the FPPP.

P 2101 and P-2106 have been deter nined to meet this criteria. However, i while P-2101-S meets proper equipecent separation criteria,its cabling does '

l not. Per the requirements of Fp0R 16, it can be shown that with l compensatory measures taken as specified in the attached EE, P-2101-5 may  ;

be used to satisfy the operability requirements of Train A upon P-2101 or P- l 2106 becoming inoperable.

1 l

l o _- _ - - - - - - - - - - - - - - - - - -- - a

RARETT ETALIIATISEJAR EE-FB-AAi4 RET _ E BARR 1 of d The EB proposes that Train A be considered operable using P-2101-S in combination with P-2101 or P-2106, as applicable, with the stipulation that a continuous fire watch be stationed in Reactor Building Level I between Columns 4 and 5 and Walls j and K (where proper cable separation is not met per the FPPP), in conjunction with operable area fire detection and ,

suppression per applicable Technical Specification definitions or adequate compensatory measures instituted per the " ACTION" Items of the applicable ,

PPOR. With the area of inadequate separation being continually monitored in conjunction with operable area fire detection and suppression, or " ACTION" Items satisfied per the applicable FPOR, an equivalent degree of protection as required per Appendiz R will be provided since the fire watch will be able to immediately detect and suppress a fire and prevent rendering both trains inoperable. Train A may be considered operable in this configuration. -

For P-2101-S to be relied on for Train A operability, the fire watch must be stationed and maintain communication with the Control Room, otherwise P-2101-5 must be considered inoperable for Fire Protection i Shutdown /Cooldown purposes and the " ACTION" Items of FPOR-16 must be satisfied. Additionally P-2101-S shall be. declared inoperable and the  :

" ACTION" Items of PPOR-16 must be satisfied if any of the following requirements cannot be met: ,

l (1) Fire Detectors XD-45350, XD-45351, and XD-45353 shall be operable or the " ACTION" Items of PPOR-12 must be satisfied; (2) Hose Stations RH1-J5 and RH1-K3 shall be operable or the " ACTION" Items of PPOR-9 must be satisfied (Technical Specifications LCO 4.10.7 also governs); ,

(3) Fire Extinguishers R1-J3-1, R1-E2-1, and RI-J4-1 shall be operable or the " ACTION" Items of PPOR-7 must be satisfied:

(4) Automatic Wet Pipe Sprinkler Systems over the System 91 pumps shall be operable or the " ACTION" Items of FPOR-5 must be satisfied (Technical Specifications LCO 4.10.5 also governs);

(5) Fire Water Pumps. Headers, and Mains must be maintained operable per the requirements of FPOR-10, FPOR-11, and Technical Specifications LCO 4.2.6.

1 SAFETT RTALDATIGE FGE RI-WW-8511 REY. R '

l '

EASLd_fE d.

JA SEE 3.A. j i

I 2.C The Technica1 Specifications listed in Question 1. above govern operation and surveillance of fire suppression systems, and circulator operability for safe shutdown cooling. While LCO 4.2.2 requires normal bearing water to be in i service as part of circulator operability criteria, thle activity does not address  !

or affect that requirement. This activity addresses the requirements of i PPOR-16 and other requirements of the FPPP, and has no impact on any Technical Specification.

i BT, ', $ 'f tI d APPROVED - J M N ~ Ole 4//MM d

I ~. ' ,

i v i - i 1

OVERSIZE  !

DOCUMENT PAGE PULLED SEE APERTURE CARDS- .

NUMBER OF OVERSIZE PAGES FILMED ON APERTURE CARDS-  ;

l APERTURE CARD /HARD COW AVAILABLE FROM RECORDS AND REPORTS MANAGEMENT BRANCH l

_ - - _ _ _ _ _ - _ - _ _ _ _ _