ML20003C091

Forwards Revised Responses to NUREG-0737 Items,Per NRC Request for Addl Info.Includes Info Re Upgrade of Emergency Support Facilities,Control Room Design Review & Plant Shielding & Environ Qualification of Equipment

ML20003C091
Person / Time
Site:	Farley
Issue date:	02/23/1981
From:	Clayton F ALABAMA POWER CO.
To:	Schwencer A, Varga S Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.1, TASK-2.B.2, TASK-3.A.2.1, TASK-TM NUDOCS 8102260612
Download: ML20003C091 (9)

Text

,e ACCma r'Crgf Ccmpany 600 Norm 18tn street Post Ottice Box 2641 B.rmingham. Alaeama 35291 Telephone 205 250-1000 F. L. CLAYToN. JR.

m senior Vice President Alabama Power

!ne su*wn eec*nc smem February 23, 1981 Docket Nos. 50-348

• 50-364 , g -

s Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Comission 2 g Washington, D. C. 20555 3H ggg25 Jgg7 g .

Attention: Mr. S. A. Varga b Mr. A. T. Schwencer

'1,yb ' d . . &

FARLEY NUCLEAR PLANT UNITS 1 & 2 NUREG-0737 RESPONSE Gentlemen:

Based on discussions with HRC staff personnel during the week of FOruary 16, 1981, additional information was requested with regard to several NUREG-0737 items. Alabama Power Company submits the enclosed revised responses on each of these issues. These positions have been discussed with the NRC staff and are considered by Alabama l'ower Company to satisfy the staff's questions.

If you have any questions, please advise.

Yours very truly, d

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9- d M 'uv O L.& Clayton, mc h

Jr. x .

1 FLCjr/BDM:rt Enclosures c.

cc: Mr. R. A. Thomas .

Mr. G. F. Trowbridge Npsg '( $

Mr. L. L. Kintner (w/ enclosures) t# "p.% -

Mr. E. A. Reeves (w/ enclosures) g Mr. W. H. Bradford (w/ enclosures) o ,

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• S-f'f $1 3 81022606t% p

Mr. S. A. Varga Mr. A. T. Schwencer February 23, 1981 bc: Mr. W. O. Whitt Mr. R. P. Mcdonald Mr. H. O. Thrash (w/ enclosures)

Mr. O. D. Kingsley, Jr. (w/ enclosures)

Mr. W. G. Hairston, III (w/ enclosures)

Mr. J. A. Mooney (w/ enclosures)

Mr. K. W. McCracken w/ enclosures)

Mr. R. G. Berryhill w/ enclosures)

Mr. D. E. Mansfield w/ enclosures)

Mr. O. Batum (w/ enclosures)

Mr. J. R. Crane (w/ enclosures)

Mr. A. A. Vizzi w/ enclosures Mr. J. L. Vota w/ enclosures O

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

III.A.1.2 UPGRADE EMERGENCY SUPPORT FACILITIES 4

i Request l Provide a conceptual design of the data portion of NUREG-0696 by May 17, 1981. Comply with the EOF design and construction criteria described in

, the excerpt of NUREG-0696 provided by the NRC staff (Table III.A.1.2.1).

Response

Alabama Power Company will provide a conceptual design of the data system described in NUREG-0696 by May 17,1981. In addition, Alabama Power Company will comply with the design and construction criteria descri'.ed in the portion of NUREG-0696, Table III.A.1.2.1 that was provided to Alabama Power Company by the NRC staff.

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l I.D.1 CCNTROL ROOM DESIGN REVIEW Request Perform the long term review of the main control room in accordance with the requirements of NUREG-0700.

Response

Alabama Power Company will perform the detailed engineering evaluation of the main control room in accordance with the requirements of NUREG-0700.

This evaluation will commence with the issuance of NUREG-0700 by the NRC staff.

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'.,f II.B.2 DESIGti REVIEW OF PLAfiT SHIELDIfiG Al;D EllVIR0?tMETITAl. QUALIFICATI0ii 0F EQUIPMENT FOR SPACES / SYSTEMS WIch l'AY BE USED If! FOST-ACCIf.'EtiT ,

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OPERATIO!!S Previous Response ,

. . . / .

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By letters of June 20', 1980 and August 1,1980, for Unit 2 and October 24,1979, November 21,1979, December 31,1979, March 14,1980, and May 5,1980 for Unit 1 ,'

Alabama Power Co=pany documented cc:r:nitments and actions taken for the Farley fiuclear u . Plant related to this item. . -

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' Ei.. Clarification Response ' . .l; . . -'

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'J fy_;,?'f A design review for the Faricy Plant - Units 1 and 2 was conducted by

• ' . Bechtel Power Corporation, using the TID source terms and the 10 CFR 20 and

. . GDC19, ,0-64 6 of Appendix. A to 10. CFR 50, dose criteria. *

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-' ' ..This shielding design review' considered se'veral classifications'of systems which included recirculation systems,. systems which are extensions of the

.. containment atmosphere, portions of the. liquid sampling syste:a, and portions of - -

tha letdown system.

,. The liquid and gaseous radwaste systems were not included in these analyses. '

- Tha gaseous system-was eliminated since the reactor Vessel head vent would be .

. , -used for degassing cperations rather than the VCT. The leak reduction program innituted at Farley Nuclear Plant, and venting of the reactor by the reactor -

- vessel head vent and/or PORVs rather than the letdown system and VCT, minimized " '

. ..'tha need for the liquid. waste processing system and therefore it was not

. considered. The high activity radioactive lab and counting roca for the aff.e.cted

. unit was not included among those:ardas where access.is' considered vitil.after an ~

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s M. accident since for tVio unitf operatioh these areas 'in'ttie:uniiffe.ctdd.6 nit'ni]] be - - -

t'- . -;

T. ..util.ized'.fcr.

.. , post-accident analyse.s. . . . . .

Access areas with their corresponding post-accident. occupancy time fof Un'iti- .

, -js ;..:,1 and 2 are.1isted.celow: r ,. . . . :. -

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od

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. ,'.:. . .:-l. . . .  ; . ' . Area

.,

.0ccupancy Per,.. ,

_,.y .r ..

t Control Room

24 hr/ day  : ..

kf'.: : .s.. .

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,' Health Physics Area 24 hr/ day,' -

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. 24 hr/ day'

Primary Acces.s Point . ,..i-Passageway to Unit 2 1 hr/ day ,

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Ihr/ day

. ' Hallway 409 , ,

e Electrical Penetration Rooms ** - 1 hr (approximately 1 hr.

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-: afteraccident) considered.

. ** Design change to climinate occupancy requirement is bei Zone maps will be updated as necessary.

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Unit 1 .

.- .- . Area .

Occupancy Period Hallway 322 (Outside Sample Room) *** 1 hr/ day f-

Gas Analysis Room ***. .

. I hr/ day '

~

, Cable Spre.ading Room . ,

1/2 hr.* .

.p . .

. . Filter Rooms

.2hi/ day *

? Switchgear Rocms (Eley.121') -

1/2 hr.*

• i -.

.. ',~

.' Hot Shutdown Panel -

~24 hr/ day * ,..' .

s. -

D .. *.

.

• CCH Pump Room

.- a 1/2 hr.* . '

!g;;..  : :. ' ,. . .  :. . -

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.

..l:.*

• _. ,. '.:. Corridor 161 ' i.1/2'hr.*

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1/2 hr.* . . . .

6. ' .- . . RHR Heat Exchanger Room . .

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.  ;  :.. . : . : ~.

'Staimay No.1 Transit to elevations at l- -

west side of aux. b1dg.

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. .. Stairwa'y No. 2 ***.

, Transit to elevations .

77'/83' . .

Transit to elevations.at '

';.' Stairway.No.&,

.. .  : . north and east sides of .

?

. . aux. b1dg. .

• Infrequent-brief. access to these areas may be required pos't-accident. ' - -

m. *** Complete evaluation of these areas is based on resolution of shielding

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, , . ' '.i j,). , , .: ,.' associated with the electrical penetration rooms.

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......u..... . Unit 2

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, ' :.. . :. . .; . . Area ' . *

.- Occupancy Period

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24 hr/ day'-

y@. f-. - *:. :? .' . . , . ;. - a.f. Cont.rol Room.

24 hr/ day .-

6 . .. ' '. /:. ' .7  !.. .

..: g. Technical Support Center

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,'- 24 hr/da'y

' Health Physics Area ..

t.- .:

\ . .. . ..

. . '., Primary Acci.is' Point. -

1

.,24 hr/ day .,

' ' Passageway to Unit 1'(2402) .

~

1 hr/ day' - .

. Hallway 2409 .

I hr/ day 1-

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Electrical Penetration Rooins **' 'T hr (approximate 1y' 1 br. af.ter accident)'

e to eliminate occupancy requirement is 'bein gorJp dered.

• • ,Design Zone maps chan11 wi be updated as necessary. .

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. Unit 2 * '

J' . Area _0ccupancy Period .

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6 ' Hallway 2322 (Outside Sarple Room forLiquidSample)*** 1 hr/ day' .,

. Spectro Photometer *** .

- ~ '

1.'hr/ day

'. ICable Spreading Room u

\.

1/2 hr. * . ..

I".

,. ' Filter Rooms' ...

'./ ,

2 hr/ day *.* .

P.,. - *

.. ::Switchgear Rooms (Eley.121') - '

• ~:1/2hr*. . . .

g.y:. ." .'. ... J'

. ;,. .Ho,t Shutdown Panel, ., . . .

., '. .. 24 hr/ day *. ,.

. s. ..

...~ ..  :. . . . .; . .....  : .. .- -

e,. :.# . . '

. D'-

.CCW Pump Roem' J *-

.: ,. .' '1/2 :hr .. * .

m. .

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. . . . ./., Corridor 2161 .. .  ! . 1/2 hi .*' . . .

1;. '. , -*

[; . . . , .'J RHR Heat Exchangei Room

, . . I/2 hr * * .

7' .

.' Stairway No. l'.. .- -

. . Transit to' elevation at

• West side of aux. b1dg.

. . . Sta'irway No. 2 ***

Transit to elevations

,17sj83c. .

i. . . Stairway No. 8 ,

. Transit to elevations at '

north and east sides of

. ~

.:. aux. b1dg.

. . ..:: .'. . .s . .

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• Infrequent-brief access to these areas may be required post-accident. -

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.f:.. '*** Complete evaluation of these areas"is based on resolution of. shielding

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i. associated. ;. with the . . el.ectrical penetration rooms..  ;;t;l :..:.. ;;,1..f.

d f'._ Tan a.ccident. .Each . of thhse

3.r..~;,

.:...: .

areas has ... c. * ,. been.an'alyzed

.  ; .. . . .  ::6 determine the .. dose -

. rates

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.'.: ..r . . ..

. The Primary Access Poirit was~not' initially considered but was later designated '

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. area for direct radiation. The security center will be included in the .

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radiation zone maps. The main control roo'm and the technical support center were

• considered as areas requiring-continuous occupancy. , ,

.:..u. ...

a As a result of these studies the following shielding modifications are listed f;r Units 1 and 2: '.

Add shielding 'to the portion of line 3" GCC'12 which is

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exposed in' the area of the Seal Injection Fil,ter valve station to reduce the dose rate in this area.

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II.B.2 (Continued) 29

2. Place temporary shielding at the containment radiation monitor to reduce dose rate in the corridon (RE-011, 012).

3. Re-route the RCS sample discharge line so that spent samples are returned by a more direct route to the VCT without entering the letdown line.

4. Add additional shielding outside the auxiliary personnel hatch to minimize potential effects at the Elevation 155' for the access control area and Technical Support Center.

5. The requirement to add shielding at hydrogen analyzers'; around lines to hydrogen analyzers; and around reactor coolant and containment air sample lines was due to the fact that personnel access was required within one hour after the accident. Further analysis has shown that design modifications which remove the necessity of operator action from this area are more practical than the shielding nodifications. These modifications include either the relocation of eight breakers or the addition of disconnect devices outside the electrical penetration room for the normally locked out valves in the ECCS flow path. The decision of which nodification to implement is pending further analysis. Design and hardware for the modification ultimately selected will be available for implementation on-site by August 1, 1981. (Note: The qualification of this equipment to siesmic and environmental critera is expected to be available by April 1,1982 if not at the time of hardware delivery.) The modification selected will be completed at the first outage of sufficient duration but no later than the Turbine Outage currently scheduled for fiarch,1982 on Unit 2 and third refueling on Unit 1.

The following is a discussion of the computer programs used for these analysis.

1. Source term concentrations in pCi/cc for each isotope 'along with the volumetric source strengths in Mev/cc/sec. were calculated using the HUCLYD computer progrem. This program calculates values of the specific activity and volumetric source strength at any given decay time for a given mixture or isotopes. The program also provides an integral energy release for that given mixture of isotopes from t = 0 to l any specified time. This computer program is analogous to ORIGEN.

2. Dose rates were calculated with the CYLSO conputer program.

This program uses the Rockwell Point Kernel theory for one dimensional cylindrical volumetric sources. Self attenuation in the source as well as the shielding effects of various construction materials such as steel, lead, concrete and water are considered in the code. The code output is in ter:.3 of dose rate vs. distance, for various piping diameters and shielding configurations.

3. This computer program is similar to the SDC code.

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II.B.2 (Continued) 29a In addition to the above study, the effects of radiation on equipment are being considered as part of the IE Bulletin 79-OlB and NUREG-0588 review. Source terms for LOCA events in which the primary system may not depressurize will be addressed during the above review.

The shielding design evaluation is a complex iterative ' process. All modifications listed above and modifications required to resolve the outstanding design issues will be completed for Units 1 and 2 by January 1,1982 except the electrical modification described above.

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