ML20155F638

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Forwards Safety Evaluation for Mod 2285,Rev 0 Re Util App R Fire Protection
ML20155F638
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 10/05/1988
From: Gallagher J
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To: Butler W
Office of Nuclear Reactor Regulation
References
NUDOCS 8810130337
Download: ML20155F638 (22)


Text

___________ _ ____ -

. -o PHILADELPHIA ELECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHIA PA 19101 tats) eat sooi

oseni w. cattroncn October 5, 1988

,2 3 : %'::,% .

Docket Nos. 50-277 50-278 Mr. W. R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

Peach Bottom Atomic Power Statio.

Appendix R Pire Protection Modification

Reference:

Letter from J. W. Gallagher (PECo),

to W. R. Butler (NRC), dated October 16, 1987

Dear Mr. Butler:

My letter of October 16, 1987 forwarded safety evaluations to you to satisfy a request made during the July 30, 1987 meeting at Peach Bottom with your staff relative to fire protection modifications.

I The design of modification 2285 has since been completed and its safety evaluation is enclosed in order to fully satisfy the request of your staff. i The modification will assure minimum flow protection for the RHR postulated Appendix R fire.

pumps which are required to operate during a This modification will be implemented on Unit 3 during the current ploe replacement outage and on Unit 2 during the next refueling outage. As discussed in the July 30, 1987 meeting, temporary modification 2084 has been implemented on Unit 2 and assures conformance with the Appendix R requirements on Unit 2 until Modification 2285 is implemented.

0810130337 091005 00 PDR ADOCK05000{7 ff 9F 1

Mh. W. R. Butler, Director October 5, 1988 Page 2 If you have any questions or require additional information, please do not hesitate to contact us.

Very truly yours, Attachment cc: Addressee 1 White Plint North 11555 Rockville Pike Rockville, MD 20852 W. T. Russell, Administrator, Region 1, USNRC T. P. Johnson, USNRC Senior Resident Inspector T. E. Magette, State of Maryland J. Urban, Delmarva Power J. T. Boettger, Public Service Electric & Gas H. C. Schwemm, Atlantic Electric l

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  • 4 # ' NUCLUR Err.!NEEF lts' ATTACHMENT

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N2-1, 2301 Market Stree Safetv Evaluation for Mod 2285, Rev. O Peach Bottom APS Unit 3 Flie: Safety 2 (Mod 2285)

Doctype 565 I

SUBJECT:

This rrodification provides mlnitrun flov protection to PHR Pu o 3AP35 in the event of an Appendix R fire in Fire Area 13 North by Installing an alternate power supply to RHR Minlrun Flov Bypass Valve MO 3-10-16A. i 11 CONCLUS!Or t:

This rrodification affects safety-related coulpnent. It does

] involve an unreviewed safety cuestion. A change to the Techn!-

not a

This rrodification does in-cal volve Specifications safe shutdown is equipment, not required.however safe shutdown capability f

i in the event of a fire Is maintained. Neither a license amendment A sIgnifIcant hr.:a rds nor prior NRC approval Is required.

consideration is not involved, i l

!!! DISCUSSION: t As a result of the analysis of ssfe shutdown cacability in cor ollance with loCFR50, Appendix R, a rrodification to the power supply for RHR MinirnJm F1cw Bypass \'alve MO 3-10-16A is recuired.

This analysis shcvis that a fire In Fire Area 13 North (13N) could affect valve 0 era: Illty and ,eopard!:e mininum flow T"Ote: kn for- RHR Pep 3Ac35. )

i An Appendix R fire in Fire Area 13N reculres RHR Puro 3AP35 for suporession pool cooling, a0 proximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> into the fire scenaric, to r-alntain suppression pool temperature within RHR Pump NPSH limits. Normally, when the puro is running without a suf-ficient ciscnarge path, MO 3-10-16A opens on a high differential pressure slgnc1 to prevent puno damage. Load Center 30810, which feeds MO 3-10-16A via ICC 30536, is located in Fire Area 13N and could beccme de-energt:ed during an Aopendly R fire in this fire area. Minimun flov protection for Pump 3AP35 is lost when the puro starts autcrratically on valid signals with no power available to MD 3-10-16A. There r ay not be enough tire for an operator to i

recognl:e the situation and trip the pu o.

't This redlfication relocates MD 3-10-16A trotor control eculo-I ment from 400V MCC 30E36 to an auxiliary motor controller. Pover to the auxillary retor controller will be supplied fecm a kBOV autcr-a-l tic transfer swltch. Non-21 paver to the switch will be supolled from the present pcwer supply, MCC 30936 (Safeguard Chan-nel ZA). Tne auto-transfer sultch will operate on a several second tire delay after normal power is lost. Unit 2 MCC 20836,

- - , , - . . - - -~-j-,-,.,--m- , . - -

,-4,,--.m.-y_m, -

., ,- - , , -. &,_,_~y---.m--_ ,-ume ,p. c ..y.-. - .,e.- -y- - - . -.

which is e iallable during a fire in Fire Area 13N, will serve as the backup power supply to the switch. The time delay will prevent the auto-transfer switch f rom operating during the loss of one offsite source and consecuential transfer of affected 4kV busses to the other off-site source.  !

The auto-transfer swltch will be located in the E13 Emergency '

Auxiliary Switchgear Rocm. The aux 111ary r:utor controller will be located in the Unit 3 Rect re M-G Set Rocm. Both are safety-related and envirorynentally and seismically cuallfled as required.

The automatic transfer is accorrolished by a rnechanically-Interlocked, solenold-operated double throv switch. or This ensures backup.

only one of two possible switch positions - nonnal There is no off position. The auxillary trotor controller contains a manual bypass switch to permit bypassing the auto-transfer switch for testing purposes. In the normal position, the aux 111ary retor In the bypass controller is f ed f rom the auto-transfer switch.

position, the auxillary notor controller is fed directly f rom MCC 30836.

Existing control room valve controls, position Indication and i trotor thermal overload ennunciation are not changed by this rodification.

Additional control room annunciators are provided to alarm when the auto-transfer swltch operates, the auxillary retor controller door 15 opened or the manual bypass switch is in the bypass position.

There Is no significant net increase in load on the plant ,

electrical system as a result of this modification. Unit 2 MCC 20B36 has sufficient capacity to power ft 3-10-16A If recuired.

Electrical ! sol tion via circu't breakers is provided betweer. W normal and backup power sources and the auto-transfer switch.

The design of this modification meets the Intent of Standby Regulatory Gulde 1.6, "Independence Between Redundant Pover Sources and Between Their Olstribution Systems," and IEEE 308-1978, "IEEE Standard Criterla for Class IE Pover Syster.s for Nuclear Pover Generating Stations." Reg. Guide 1.6 and IEEE 308-1978 do not permit automatic transferring of loads between redundant standby Class 1E poner sources. For this modification, the norrral and backup pover supplies to the auto-transfer switch are not redundant since they originate frcm the same emergency diesel-generator.

During the normal and design basis accident operation of RHR d Ptmp 3AP35, MD 3-10-16A is ocwered frem its norrral 480V source and will function as designed previous to irrelementation of this r-od i f i cat i on. The autcr atic transfer to the Unit 2 backup source occurs on a tlrne delay after normal pover is lost and on the condition that backup pcwer is evallable. The time delay prevents s an auto-transf er unless a sustelned 1 css of normal ocwer is sensed by the switch circultry. The auto-transfer switch resets auto-r-atically when nortral pover is restored.

In the event of a fire in Fire Area 13N, mininum ficw protec-tion for RHR Pttnp 3AP35 could be delayed due to the auto-trar.sfer switch time delay. The maxinun delay would be 10 seconds.

This maxinun delay would occur if MO 3-10-16A received a signal to open and nonral 480V power to this valve is lost siruttaneously. Operating RHR Puno 3AP35 with no mininun flow protection for an additional 10 seconds over the '

present design would not result in excessive ptrrp/rrotor overheating.

Since this rrodification does not affect any radwaste system, the guldance provided In IE Circular 80-18 is not applicable.

The plant as described in the UFSAR is being changed by this nodi ficat ion. Appropriate Single Line Dlagrams will be uodated to reflect the new design. Sections 4.8, 6.4, 6.5, 7.4, 8.4 and 8.5 were reviewed to make this determination. Chapter 5 and Table A-3 l of the PBAPS Fire Protection Program (FPP) have been reviewed and will also be revised, r

IV 10CFR50.59 CKt6'GES, TESTS, Ato EXPERIMENTS:

1. This codification does not involve an unreviewed safety cues-tion because of the following: i a) The probability of occurrence or the consequences of an accident or rralfunction of eculpment important to safety previously evaluated in the safety analysis report Is not increased. The present valve operator con-trols, Indication, anc 480V pcwer supply for RHR Mininun Flow Bypass Valve MO 3-10-16 A are traintained.

MO 3-10-16A operates as p. eviously designed to 9Povide mininun flow protection for RHR Pu o 3AP35 during normal operation or design basis events. This rnodification adds a backup power source to this valve for an Appendix R fire, b) The possibility for an accide.nt or tralfunction of a different type than any evaluated previously in the safety analysis report is not created. RHR Minimtin Flow Bypass Valve FC 3-10-16 operates as previously designed. This nodification ensures minittun flow protection for RHR Pum 3AP35 during a loss of normal 480V power to PC 3-10-16A due to a fire in Fire Area 13N. PC 3-10-16A will norTnally be powered f rcm its present source. On a sustained loss of norms 1 4E0V power, an auto-transfer switch will operate and

- _ _ = - _ _ .. . _ , _ _ .. - - - - . _ _ _ _ _ _ . . _ - _ _ _ _ . _.

.u- \

\

l supply pcwer to MO 3-10-16A f rcm a Unit 2 backup source.

The E-1 diesel-generator feeds both the normal and backup power sources to the auto-transfer switch. This deslgn meets NRC Reg. Guide 1.6 and IEEE 308-1978 criterla.

The auto-transfer switch, auxiliary rmtor controller which controls MO 3-10-16A, and associated cable rerouting .

are designed and constructed in accordance with criteria I appilcable to safety-related and Appendix R safe shutdown systems. The cable routing associated with the backup source is designed and constructed in accordance with Appendix R safe shutdown criteria. >

c) This rrodification does not reduce the margin of safety as defined In the basis for any Technical Specification.  ;

The RHR system initletion and operability recul rements as described in Sections 3.5 and 4.5 are unchanged by '

this modification. The operabl11ty of MO 3-10-16A is maintained to provide miniram flow protection for RHR Pum 3AP35 In the event of a fire in Fire Area 13N. ,

2. No changes to the Technical Specifications are reaut red based on the review of Sections 3.5 and 4.5.

i V 10CFR50.92 SIGNIFICANT HAZARDS DETEPPINATION*

A license a: endment is not reautred; therefore, this section is not applicable.

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VI APPROVALS:

Prepared By: . v DATE: h'U 'N Qesponsible Engineer)

Pfni/1$,E/,:h. DATE: h.lN2l$;'}

Reviewed By:

( D1 '. ndepe ent 'P',eviewer)

' DATE: I

/ '

l (Le'()Divisio Seef M9t/ Branch Head

~

DATE: 6 !2. 8 (Non-Lead Div. Respoisible Engineer)

< em fWu DATE: 0!P 2 H (NonM.eaf Div. Independent Revi r)  !

DATE: c, )s ele 9'

' 'M d M ' '

Obn ' Lead Divi_. lor / ection/ Branch Head) d(  ! DATE: 7 1!Ii3 (Nuclear GlEnvironmental Section Head) / /. j JDK: sic 1 sc10587m!30 2

(

Copy to: DISTP. CODE EESE-1 t s

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. UCCAR CHANGE CONTRO.

, . v;-I~77; t/E3 Fes:P. Ecst:m At:mic Power Station

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PAGE3

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.. *

  • PEAPS PPP >

HPCI- Pump Turbine Exhaust  ;

PS2-23-97B HPCI Pump Turbine Steam Press PS2-23-6BA l HPCI Pump Turbine Steam Press PS2-23-6SB HPCI Pump Turbine Steam Press PS2-23-6SC >

I HPCI Pump Turbine Steam Press PS2-23-6BD TE-5941A HPCI Steam Leak Detection HPCI Steam Leak Detection

)1 TE-5941B TE-5941C HPCI Steam Leak Detection fN

[N " j "."\

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i HPCI Steam Leak Detection -

/ W.  ?. >

i, TE-5941D -

o i I t /

.__HP.CI_1.1..teraa.

Rd. NO 1-10 % A n:be Lys Control._Sta_t. .on_b b d C"i

- 3 0C0 4EX . . .. "

i L r%t S CHN 3%9 ~

(c) ~Pos Writec F: e in A?e'a l

(1) Ignitien of electrical cabling in cable trays (an l

unlikelv c::urren:e in the absen:e cf a f tre source l' external :: the cabling since it is cf the self-ex inguishing :ype).

2 and 3 - P.HP pumps, HPC: pumps M-0< 850 (2) Lube oil from UnitsEre:irculating pump M-G sets, recir:ulatin t lube cil pumps, P.CIC pumps either leaking on : h tin; c.

! with subsequen- 1;..ition cf the oil or an over ea i

the pumps causing ignitien of the cil.

(3) Char: 0al filters in -he SGTS air p;enur.

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f (4) Spent :harcoal filters in filter ro0m 235. Orage area I

(5) 1;nition Of tras* ' -Se radwaste trash s:  ;

from an external source. l (6) I;nition cf paper in the radwaste con rcl roe- f ro- an I f ex ernal seur:e.

f 71 , gg 3 g;ggy, 7ir,Suppres,icn (d) Consequence 1 smoke,;enerated by a firealarm will a..u.:iatien a::!vate smoke dete ,

,;je -ause anUP:n audible-visual 1.. thecf an alarm f rem an f re:eip I"a ;. ;" e*7 a

n .r e , ::::',

  • he are9 the fire brigade will be dispatch'ed *:Tnl

[7'"8 .sh ,.he . ire.

_g~ g'p;P, rc0.s will a
:ivate smoke the ftre alarm de:e::er's whien I
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e-v.sual alar- annuncia:1cn at

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Emcrg ney Switchgear Room 267 E.3.25 Fire Arec 33: (Elev. 135'-0*).

Area (a)

Structural and Architectural Design Teatures ofEatinc Fire Construction 2-hr Cor. crete r.asonry units 3-hr Walls: N -

2-hr E - Reinforced concrete 2-hr 5 - Concrete masonry units W - Concrete tasonry units 3-br floor: Reinforced concrete 3-br Ceiling: Reinforced concrete Daer cent.ecting to fire area 32 / 7"'\ .

Accer : boer cont.ecting to fire area 50 A:s LLk6 Us.t 3 ,___;

Related Components in Tire Area

f. h ) Pb 4 c.

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iT. wegency Auxiliary Switchgear i / J 4 I vew Ec. uu.dtr sam -,--

8

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- . 40'.or Control'C_enti ~r /

  • , . . s ar c,;

( c ' Pe si u.a - ;ikely c t he le- t.

'5 r ';:: cal cabling in cable tray, (an unthe ). a sence c

.a '#-er cable'is cf the sel!-extinguishing type ot,ur. . .

I OESIP ,

> Suppression (d) Conseque.. o of T're with Active Fi:

a fire vill activateannun:iation smoke detectors at 0f the The Sroke generated byill :Tuse an audible-visual Upon alarre:e!7 ,

sh'en s '. . . ce fi-9 annuncia:c :n the ta.n :en:r:1 recr.the plant fire brigade n the control root, En3 .lbr: to er.tinguish the fire.

dispatcheu (ei Effect of Fire on Safe Shutdown associated vito Cables Tire area 33 centains cables and equipmentand C fer Units 2 and 3 shutdevn rethods su;7:r:

A, 3,shutd;vn re:hed 3 :: f:

required ::

are encapsulated oy a 3-hcar-rated fire barrier c , encapsulated, cables that are n0:

be taken to recover anv functions Equipment asso:!a:ed with shutdown method that eculd be lest.C loc 3 :: lo:ated ken componen:

this fire area either have a redundantoutside 7neref:re,the fire area or to recever any fun::!cns that could be lost.

F.e v . O, 9/!f 5.3-95

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  • . . PEAPE TPP

$+ (Page 8 of 46) i

TABLE A-3 (Cont'd) l i
Hot Cold Tire Shutdown Shutdoq Area Methods Equipment Component Description __ _

i Number _ -

3C

, 12 Core spray pump D 2A,2E,2C,2D Unit 2 3DP37 HPSW pump D 47 3A,33,3C,3D Unit 3  ;

3DP42 -

i I

2 3A t 30E32 RCIC barometric condenser i 2

35,3D 1 HPCI auxiliary lube oil l 30P26 - - - '

pump 2 3A RCIC vacuum pump l 30P46 j 2 3A RCIC condensate pump l 30P48 33,3D  ;

d.i ttt 2 r

' a.A -> '3 053 7 HPCI turbine 1s m

,U^^

, . . 3. .

t m i

---up. ~~ikh.-5.3C (b .% . , . ,

) I.i'sc~es:

5 [( ~'-[.dd'._Yi i. N, ~E(,4to V 4C_"c7 ".2 e ,

9

...,...,a,--

~

.E

e. Un;;;

nP3n unit intertie valve 3A,35,3C,3D

, ~i oic..a 2A,23,2C,2D Uni- 2

47 2, n.<... 3 HPSW unit intertie valve .A
, 3.=. , r-o.-

i 5163

-- U . .1 - 3 2 -

t DPI3-?0-179 P.HF/HPSW dif f erential l pressure indicator Unit 1 10 3D DP'3-10-179 RHP/HPSW dif f erential 4

y. essure rans.itter l 2$ 2A i

PCO-13-51

?.CIC fl0w 000t;0119: .

f .:. .. = - , . --

f

.T-~. ..t.a.:

.. . . . .r st.

. - + .... .........e.

...... 9

*$ 3A 1

"C3-13-91 P. IC flow :entr:11er 25 33 i

l

C3-23-10S HPCI flow contr:11er *A,*3,2','? U~!" -

l "5 .

i.A.,.s=,te Uni- 3

(-

f  ?**-10-132A H?SW flow indi: ster .-

4 2$ 2A,;E,20,0? .-

U..

n !, ". i.

u.... .

HPSW flow indicater 3A,,.,, .a . ,as

! TI:-10*1323 a .

')

?.e V . O, I/IS 1

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_ . - - - - . . , ~ - . _ - _ . - . ---,_.-nnn-,--.n -- . , . , , , _ - - . , , . , . . , _ . . _ ___ _nr,_ , ._v,_~,,. , , - . ,,p,..-,

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(lage if' cf 44)

A3' E A .3 ( Con t ' d )

Hot Cold '

s Fire Shutdown Shu t o c>wn Eculpment Area Methods _

Nu.ber Cx.conent Descriotion Unit 2 2A,23,2C,2D  :

o 460V ac motor control 39 3A,35,3C,3D Unit 3 HCC20359 2A,23,2C,2D Unit 23 center

] l 37 3A,25,3C,3D Uni e

MCC20360 480V ac noter control center Unit 2 j 2A,23,2C,2D 460V ac meter control 2

3A,3B,3C,3D Unit 3 I HCC30336 center Unit 2 i 2A,25,2C,2D j 420V ae rnoter control 13N 3A,3E,3C,3D Un!* 3 HCC3'0337 ,

center 2A,25,2C,2D Unit 2 4

135 3A,23,3C,3D Uni' 3 J

l MCC30338 450V ac mo2er control ,

center .n n.... .

i j gg ..r, , .. ,3as .

n ,. t

?

4 e. rd. a meter gen.;gt. g.,:.,se.,tm . - V... .

'l v*ata=se a

C,- .,,

.n ..

\ '
i. t. .a,.-,.s,-- ,. 3.-

i n. .

, . ' .

  • X, u"*--*---s -s=ce ,e.

9.A, 80 meter Con'a.o. g,e. , ,. =. . , 3 . e. , g --% . . .

. -:4 .! .,\ wenter n.. .. ., ..

l

? / _ U . .t 3,\ S. .g

..,.=,w.,.%

.6 .- ..

v.... ...

.4&OV a m: ,,0; cong o1 1s te e n f :. =.J -e s , 1. m.

e

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t

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t O c,. n s.g *- , ,.s,t\ w.eMt~

t-

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-- f o , t = , t. ~ , t m ". ..

5-% *

> - ~- . ,.

w.-.r-- - :. = 6 : T3TrMWva:ve-- -

m t.n s -

, w...- --

!v ,,y, ~ -

,s.,. .

f

..n

. , . = , 3. r. , 3. ,. t 1 .. Sluice gate

v. a. a.

s.A,s.=,se.,.im . - r. . 4...t .

l "v.~'dl.e n.. .. ,. .- -

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n . . . . , .

t.

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H.., . .5 a

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n ,0

,a- . . . . .

4 n,. .

e5 . t.

i 1 u.

'"~~a=

..... Slui:e gate i

. A,t=,.te.,.so s

j .

. ., n.. .. ,. .. e.

, ,e 7,. , .e : , . . . . -

y w a.

  • 9* t ', ', ..E2m n

4000 i ** .. er* f e vgly, 9. .

t. A , s =- , t. a .

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.. . t. l 1

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J

. t' a

.6,.

a- ,.r.,--

a

.- '.' 8 *.. 9 I 4

4 "v. # ~ .d ', ,' '

N E S'n' d!Scharge valve  !

J

.g gay  !

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I 1 w e n:

r I .e.. . ., se.. ,

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==,,--,.--rn.~~,,,p-p.- -w----,- ~,-.--

sy y ,w r ncge-e r-- -nyy.,,mmm,,n,,, m ,- w n g e- ,, e m m,,m_,.m.,,-mp.,mwe,,. ~~~---+-w----r~n

ALARA REVIEW CHECKLIST, REV. d l

3 Responsible Eng. [ O. Ve 3 a -

l S:ation hM P.$

Unit i l Mod i 2.2.9 [ n 4\br.nc1, f4_u- S .n[ 4 8e HO H 0-( l Il Mod

Description:

l.. is located in high Non-radicactive equipmen: that

1. areas) increases worker To lessen radia:!cn environmen:c ("het" exposure during operation and maintenance.having high reliability see and
nts exposure only equipment low maintenance /calibra:Acn requirements shou.d beDo in these areas.

locate non-radicac:ive equipmen: in "hot" areas?

l No Y Yes l If Yes . Erylain _

l l- -

l areas in non-:adi ca:-ive

<-. aceme..- ef "ge:" equip::.e..:

I -.

in : eases ::ke: exp:sure f:: a *. '. 4 :- i v i -cap i eu:s e:1::ied sy s . ::-ru:

Shielding and p;cvisions :: Does pn the area.

.eakage can ::inimize exp:sure and centa: ina:ic ..in n:n-:adicactive this cesign 10: ate "ne:" equipmen-a:eas?

l N: Y_ Yes _

i :f Yes. D:: *. s i . _

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- ~.

;.= . . . . .

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(crud) in pi;;ing ,

3. Deposition cf activation products !cr all plant  ;

i systen;s results in increased exposureThe f ollowing design consideratio workers.

minimi:e crud de; ssition. i 1 a. eliminate low spots by sloping all horizontal runs '

l .

eliminate elbows b.

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c. use burt welds instead of socket welds 9

l provide flush and drain connections for equipa,ent

d. i and piping runs l promote
e. eliminate activationthe (e.g. useStellite of materials contains thatCobalt unich is t the mest significant activation product).  :

Does this design f ail to incorporate tne above ,

considerations in radioactive systems? ,

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No X Yes - t i l i

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I, sr.i eld .ng 'ry

4. Does the design change perranent ;. .a n t l l

' adding penetrations er cutou s in the snie*. ding? i 4

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N: Yes _

l 2

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5. N high : mal ventilation radiation areasflow in is item order non-radioactive areasof Does thistodesign minimizealter thethese spread airborne contaminants.

flow paths?

l No Y Yes j :f Yes, Exclain _

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6. W::ker exp sure during routine maintenance in high '

considered:

se it can P cvide flanged nne::icns en equipment a.

be ::ved := clean areas fe: maintenance.

b. Iquiptert/ materia; *.aydewn areas sneuid be provided l

cc side Of the ni;. rad areas.

l p'.a:f:::s vs.

e:e::i:n Of

c. ns:a.a:icn of permanen 5 . 3,.4 2.,... . . . , .

emp::ary shielding.

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d. 7:: vide fe: :ne e:e :icn cf h: ea t.. .; ai
e. Investiga:e :ne ;;;ximi y ::
nne::icns.

Does :he design fail :: 1,.:: p::a e the ab:ve  !

- cen s id e r a:i ct.s ?

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Branch for Any ite.sm n.arked Yes must be referred to the Nuclea:

cc: p;e:ier. Of See: ion :1.

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b. D . (b.t, . Date . 2". ' -

l Prepared by:

(J f//f NY j Tseviewed by: 7[ 7d fb Date j ::. *ecuiremer.:s/resciutions of 1:er.s 1-6 marked Yes.

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FIRE PROTECTION REVIEW CHECKLIST, REV. b l Responsible eng. M 0 . %tmo m Station __ Unit i 3 MOD i N I. Mod

Description:

hdecuk Le Swb w b No 5-t(7-l(cA

1. New penetrations through rated fire barriers are being created. Existing penetrations require removal or (See r modification (not including cable penetrations).

Architectural Fire Barrier Dwg.)

No X Yes  !

r Description, location ,

1

2. New equipment represents an incrcase in the combustible l loading to the site. Items to be considered are lubricants, fuels, combustible gases, bulk gas storage, '

insulation, plastics, etc.

No Yes N i r

List quantity, nature, and location of combustibles,q. [

(,t-sv.') cNu  :

- AO Men ef e. . Met # o h. P at , e M.( CA obb c, A l t

,, n A. ws 3., .. m i< i s r%. . ,L., sut.L..- '

bu ( m isN

' rsc,osvt

.i . Relocation or addition of any safety related l I

equipment / component / cabling.

No Yes Y a  !

Description Oc M (As c.ucc.v/ wa 3.go.qhALe x,.\\ k h u A d b4 "

i Mct m o um L.~ M.t-sa ca.g kr MM -* ~ M ,

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' .+53 mout .ev a_ 3, agte- m n . s ars _ , w e e, 3 ~ -- i

4. % na t4 U "

Sw %.  % I

4. Relocation or addition of any safety related l

equipment / components / cabling identified as safe shutdown in the FPER and circuit and raceway schedules.

No Yes Y l

Description Seo Ma "3 e.h. . * % d\.\ i, .s . a Mw cn \.

C i 1

ke e -s Mrt t06% ,,, . o -n>.k. ,.3 t d. A h ow 4

n\t u nuk i o e ca.m e 6 Mc wt0-n A V . n.,

4ku n.da - ires f u. ss.'4 A .

EXHIBIT 3.3-VI 4/86 (Page 1 of 2)

5. Will the codificction interforo with tho offoetivonoss suchof as existing fire detection and suppression equipment; require modification to sprinkler piping, Is thereor block a or suppression sprinkler head or fire detector?

detection equipment within one foot of new equipmentWill access to detection:

installed for this modification?

suppression; fire dampers be compromised?

No M Yes Description Prepared by: h l ~. _Date b 5'M Reviewed by: M  !-f _ Da,te f////96

! Any items marked Yes must be referred to the Buildings Facilities Branch for compl'etion of Section II. ,

I. Requirements / resolutions of items 1, 2, 3, or 5 mar,ked Yes. L ?.L tl T . 5 r uL 9 cc, e oc.e.o Nod me_ Anc+1 f Qc c- T? 8b ou i d e%-r h4 .w sdee ec,e l 0 0 C- s. Nw 9eeger_ncv Ar Maues.

op -r sA W e.e_ ,

Prepared by: N _ Date G//7/bN (B . F . Branch)

Reviewed by: [bb Date -

(c I

II 600 (F. 7). Branch) '

Raquirements/ resolutions of item 4 marked Yes. JS6Fhd[cP/ / 4 M4Ju07G~$r W, v ]l.

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Prepared by
_ (O d 'Mf / Date 8[9hf C .g g p + .

(E.E.' Div . )

Reviewed by: Nb b. Date 3b

tt

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(E.E. Diiv.)

Approved by: (( Date d!/7 [_

(Supv. Engr. BFB) / /

J

ct E-I-C Industrial MPE 4

EPE Station Superintendent DAC (Doctype = 197)

Q .Q oC WO EXHIBIT 3.3-VI 4/86 (? age 2 of 2)

)

4

I

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No. FP M a O_h)

  • Fact 11ttes Branch FPRC Evaluation Form Rev. 1 3'% -I to Fire Area / Zone  ? - SR Mod. 2186 Elev. ,_Lfi' Station VOxs-6 Resp FB Eng PDF >

Date 6 / 4 /w.

Items Checked Yes:

1.1. (1) If PBAPS, require seals to be Installed per pg Spec M-610 (2) If LGS, require seala to be installed per Spec M-629 j

1.2 (1) Will increased loading inpact on a ccrrbustible free zone .M.E g,% 6-W be.e. Si 4 a) PBAPS - 1. FPP Set!:n: S.O -

2. FPP Sections 5.3.e
3. FPP F.lgures 5.3.f b) LGS -FPER Sections 5.4.e

- - . . -, .... . . ._ _. .__ c) _3 f 3 t,_3 2 .1~. a ' &~ b i nc l ude ' any - I t ems ma r ked y e s , ' - - ~- ' ~ ~ " ~ ~ ~ ~

infcrm the responsible engineer that this is not acceptable without additional analysis by Electrical Engineering or fireproofing the hazard.

d) Calculate quantity of cerroustibles to be added in units consistent with those given in the FPP for PBAPS or the FPER for LGS. Aw t u% ein e u , a A* e -

r c.ee ww 3 w.:, a oc % A. r .n um ee ato

' Nuts sw A+ e e.sc soe c r o 45 A m (.- n o +%D --

w vaAA a '. , __

(2) Will increased ccrrbustibles be added to an area containing safety-related eculpment/ cables wtilch is NC not protected by automatic cetection?

!! yes, add detection, recuest an exer otton pelor to approval of work or relocate ccmbustibles.

Nsecr w cv % io rict. .s er a f t. ,.'e a. 2 -st<.

, t. M 4 ~~ ~ f Lo .

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+

(3) Will increased ccnbustibles cause ccmbustible ,

loading to be in excess of a requested exemption PC for PBAPS - refer to FPP Sections 5.3.f's (se c. 3 7. . % .e() [

If yes, determine if increased loading defeats the l Intent of the exenotion request. If no, Inform if the yes, r NRC in accordance with established mechanism, i request an exanption prior to start of work.  !

l (4) Will the loading be added to an area in which there ,

is unprotected structural steel? ,

I 6

a) Refer to PLC Structural Steel Su1 mary  !

Calc tk. PIA Yes I Go to 1.1.4.b i

te

/ ,

I Go to 1.2.5 I

b) Determine if increase is greater or eaual i to 10% of the ortoinal_ fixed loading the cale --

[

- - . . _ - . .. . ._. . . . . . j 3. ba s e d on - - ~ ~ ~ --- -

i l

1. If no, go to 1.1.4.d -
2. If yes, go to Structural Steel calc f and re-perform analysis. After completing analysis, go to 1.2.4.c j t

c) Did the Increased loading cause steel to fall? l I

1. 1i no, go to 1.2.4.0 ,

r

2. If yes, determine corrective action and l inform responsible engineer to go to I 1.2.4.d i I

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(d) Update analysis: If loading is greater than 10%, add an additional 10% or the total arTount of increased loading which causes the steel to fall, which ever is less. If (original 10f) t so that the next calculation will be based on the original 10% less any subsequent nods which have added ccnbustibic nuterial to the area.

(5) Does increased loading represent an unevaluated hazard to safety-related coulpmnt?

V a) tb, go to 1.2.6 Gu A7 .O .D b) Yes, go to 1.2.5.c .

1 I c) Determine if there is any adverse Inpact l and any additional fire protection enhancements rcQulred.

f l

1 f (6) Af ter satisf actorily resolving items 1.2.1 through !.2.5 on this evaluation form and items !.3 and I.5 on the FPRC, forward this evaluation and the FPRC to the respcnsible Facilltles Branch engineer for the FPP for PBAPS or the 1 FPER for LGS to revise the appilcable sections of the

- - - ~ -- ~ - respective rescets arreculred by this- evaluation.-- l (7) Sections of FPP or FPER reviewed.

Q?Ccd 4 4 ta Cic rwk 6. L1 4 6. h ? 5 (D i s cs c, - b

(!) !s en LDON (LGS) or a UFCCF (PBADS) required to MD specifically address Fire Protection? .

Eesocrstbility for ccs clettn; (if apollcable).

(9) Ccmmnts:

r

- _4

, ' ,,*. ' ' , ,1, (10)

Conclusion:

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