ML20203J951
| ML20203J951 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 02/25/1998 |
| From: | Reid D VERMONT YANKEE NUCLEAR POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| BVY-98-22, TAC-M99265, NUDOCS 9803040369 | |
| Download: ML20203J951 (12) | |
Text
VERMONT YANKEE
, g
' NUCLEAR POWER CORPORATION 185 Old Ferry Road, Brattleboro, VT 05301 7002 (802) 95/ 5271 February 25,19951 BVY 98-22 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washingten, D.C. 20555
References:
(a)
Letter, Yankee Atomic Electric Company to USNRC, Yankee Atomic Electric Company Operational Quality Assurance Program (YOQAP-1-A), Rev. 28, dated June 23,1997 y%
(b)
Letter, Yankee Atomic Electric Company to USNRC, Yankee Atomic Electric Company Operational Quality Assurance Program (YOQAP-1 A), Rev. 28, dated October 1,1997 (c)
Letter, USNRC to VYNPC, Request for Additional Information (RAI) Regarding the Vermont Yankee Nuclear Station Operational Quality Assurance Program, Revision 28 (TAC NO. M99265) dated November 24,1997 (d)
Letter, USNRC to Yankee Atomic Electric Company, Acceptance of Revision 11 to Yankee Atomic Electric Company (YAEC) Operational Quality Topical Report, YOQAP-1-A, dated May 24,1982 (e)
Letter, VYNPC to USNRC, Vermont Yankee Third Interval inservice Inspection (ISI) Program, BVY 93-137, dated December 3,1993 (f)
Letter, USNRC to VYNPC, Evaluation of the Third 10-Year Interval Inspection Plan and Associated Requests for Relief for Vermon* Yankee Nuclear Power Station (TAC NO. M88344) dated June 14,1995
Subject:
Vermont Yankee Nuclear Power Station License No. DPR 28 (Docket No. 50 271) i Operational Quality Assurance Program, Revision 28, TAC NO. (M99265)
Refen nces (a) and (b) submitted Revision 28 to the Yankee Atomic Operational Quality Assurance Program (YOQAP-1-A). YOQAP 1-A, Revision 27, is currently applicable to the Vermont Yankee Nuclear Pcwer Corporation (VYNPC). Reference (c) requested information about the exception taken to Regulatory Guide 1.26 in Revision 28 of YOQAP-1-A. The response to each request follows the restated request below.
Request 1. a.
" lease provide documented evidence showing that the use of ANS 22, Draft 4 Revision 1, May 1973,
" Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants," was found acceptable by the NRC staff as an alternative to RG 1.26, for component classification at VYNPS.
Response.
i The use of ANS 22, Draft 4, Revision 1 May 1973," Nuclear Safety Criteria for the Design of Stationary p g g' Boiling Water Reactor Plants," as an alternative to the component classification scheme of RG 1.26 was y-documented in Yankee Atomic Operational Quality Assurance Program (YOQAP-1-A). Revision 11, and was accepted by the NRC in reference (d), Attachment 1.
h\\,\\)kkkkkkkkkkk ' ' '.
9003040369 980225 PDR ACOCK 05000271 P
VERMONT Y ANKUB NUCLEAR POWER CORPORATION Docket No. 50-271 BVY 98 22 Page 2 of 3 Request 1 h.
Please provide the bases for Class 1,2, and 3 component classifications, as applied to inservice inspection (ISI) activities, at VYNPS (i.e., describe the Class boundaries). Include a cross reference of RG 1.26 criteria with those portions of ANS 22 and ANS 52.1,1983," Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants", being used for component classification at VYNPS.
Response.
Systems are classified into Safety Classes using the Vermont Yankee Safety Classification Manual. This manual, which is based on ANS 22 and ANS 52.1, provides a systematic approach to classifying systems and components according to their importarse to safety in the same fashion as RG 1.26 assigns systems and components to quality groups.
The Safety Class Definitions from the VY Safety Classification Manual are as follows:
Safety Class I (SCI)- The classification SCI applies to a structure, system, or component v'hich performs any of the following functions:
Forms part of the reactor coolant pressure boundary (as defined in 10CFR50.2) such that failure could result in leakage of reactor coolant greater than that from a 3/4-inch nominal pipe size.
Provides mechanical suppon to any portion of the reactor coolant pressure boundary.
Safety Class 2 (SC2) - The classifications SC2 applies to a structure, system, or component not classified as Safety Class I above, but which performs any of the following functions:
Inserts negative reactivity to shut down the reactor.
Prevents rapid insertion of positive reactivity.
Maintains core geometry appropriate to all plant process conditions.
Provides and maintains primary or secondary containment integrity.
Removes residual heat from the reactor and reactor core.
Stores spent fuel.
Piping or components which form part of the reactor coolarit pressure boundary, but whose rupture would not result in leakage greater than that from a 3/4-inch nominal pipe size.
Provides mechanical support to any of the above Safety Class 3 (SC3) - The classification SC3 applies to a structure, system, or component not classified as Safety Class 1 or 2, but which performs any of the following functions:
Processes or houses rdioactive wastes where failure of that single component or structure would result in a whole body Jose that would exceed 0.5 rem at the site boundary or its equivalent to any pan of the body. (Note - ANS 22 specifies 170 mrem at the site boundary; however, the VY licensing basis is 500 mrem for these conditions. See FSAR section 14.2.1)
Provides or supports any safety system function.
Removes decay heat from the spent fuel pool.
Provides mechanical support to any of the above j
(Note - T*.ose systems that would be the subj:ct of paragraphs C.2.d. or C.3 of RG l.2L for classification are included in VY Safety Class SC3.)
1 VERMONT YANKEE NUCLEAR POWER CORPORATION DocLet No. 50-271 IIVY 98 32 Page 3 of 3 Non Nuclear Safety (NNS) The classification of NNS applies to any other structure, system, or component which is not categorized above items in this classification may be integral pans of the power conversion process or other ponions of the plant, but have no direct safety function.
Safety class designations are applied to VY systems using the above definitions in a process defined by the VY Safety Classification hianual. Safety Class boundaries are identified on piping and instrumentation drawings (P&lD's). Component safety classes are identified in a computer database. These two entitles are ued in developing the Vermont Yankee Inservice inspection Program. All safety class 1,2, and 3 vessels, piping system components and their suppons are identified and scheduled for inspection and testing in accordance with the requirements of the ash 1E Code. The design modification program includes a requirement for review of modifications by the ISI Coordinator for ISI Program impact as well e ar compliance with the AShiE Code rules for repair and replacement activities. The ash 1E Code of ruord for the VY ISI Program is the 1986 edition of Section XI with no addenda.
The third interval ISI Propam was submitted by reference (e). The NRC in reference (f) accepted it. This proyair includes augmented inspection and testing of safety class ccmponents as required by VY commitments to the NRC or as warran:t ' by industry experience. Piogram revisions, inspection summaries, and repair an) replacement summary reports are submitted to the NRC as required by the AShiE C ade and regulatory requirements. An independent third pany program reviewer (Authorized Nuclear Inservice inspection agency, ANil)is contracted to review the program and its implementation as required by the AShin Code.
Regtiest 2.
Please provide a comparison of ANS 22, Draft 4, Revision 1, hiay 1973 and those ponions of ANS 52.1, 1983 that have been used as a substitute for the information provided by ANS 22, as stated in the Yankee Atomic Operational Quality Assurance Prt, gram.
Response. provides a table of rystems with three conte.t topics: Safety Fe -tion, Definition, and Safety Class. The table entries compare the two standards w here any topic in the VY Screty Classification hianualis derived from ANS 52,1. Italics indicate the applic+la topic.
Should there be any questioni please contact this office.
Sincerely, VERMONT YANKFI NUCIIIAR J0wtR CORPOR ATION Donald A. Reid Senior Vice President, Operations cc:
USNRC Region 1 Administrator USNRC Resident Inspec'or - V' a USNRC Project hianager-VYNPS Vermont Department of Public Servi hiichaelT. Andenon INEEL Research Center 2151 Nonh Boulevard PO Box 1625 Idaho Falls, Idaho 83415 2209 1
A W M uryd W /
J. E. Tribblo TN V 73-n D. E. Vandenburgh/U. P. Johnsor 9
p.vtseg L. H. Hsidst
.t jo, UNITED STATES D. W. Edwards /R. E. Half rich
, 8 y v.q
- n NUCLEAR REGULATORY COMMISSION D. E. Moody
)
y,
}
WASHWOTON D. C. 20555 A. C. Kadak W. P. Murphy-2 4
t,%.....#
[*Qy 77 ggp MAY 2 41982 J. D. Haavitine J. Pelletier J. A. Kay D. A. Reid NYR *2-111 J. K. Thayer R. Kenney YANEE A70MC NVY 82-83 A. M. Shepard-2 R. Smith H. A. Autio W. Conway Mr. W. P. Johnson, Vico President RESPONSIBluTY.
R* E. L8PP Yankee Atomic Electric Company R. L. Berry C. H. Rice 1671 Worcester Road t ' B * 'Pi k E J. G. Robinson R. G. Staker Framingu m, MA 01701 D. B. Pike orig.-Lic. ri be : 6-150 - 62.
E. W. Jac uon-2 M & YR) har Mr. Johnson:
J. B. Sinclair A. M. Shepard-2
SUBJECT:
ACCEPTANCE OF REVISION 11 TO YANKEE ATOMIC ELECTRIC COMPANY (YAEC) OPERATIONAL QUALITY TOPICAL REPORT, YOQAP-1-A We have reviewed and evaluated Revision 11 to the YAEC Operational Quality Assurance Topical Report, YOQAP-1-A, submitted with your letter of March 1, 1982.
Revision 11 reflects quality assurance program and editorial changes.
We find that this report describes a quality assurance program that meets the criteria in Appendix B to 10 CFR Part 50 and is therefore acceptable.
You may implement it upon issuance. - For the YAEC quality assurance program, you need only reference this topical report in Chaptor 17 of license appli-cations. Wt 30 not intend to repeat our review of this topical report when it is referenced in en application.
Should regulatory criteria or regulations change such that our conclusions about this topical report are invalidated, we will notify you.
You will be given the opportunity to revise ano resubmit it should you so desire.
Pro-grammatic changes by YAEC to this topical report are to be submitted to NRC for review prior to implementation. Organizational changes are to be submit-ted no later than 30 days af ter announcement.
_Please include a coDV of this letter in the recort, renumber the reoort f00AP-1-A.
Revision 11. and transmi t 40 copies +o the NR,Cu_In yo
.mi ttal letter. please indicate to which,pjagts Revision j,1,,wi1,,,1],e,,u,I trans-8 % able.
Should you have any questions regarding our review or if we can provide assis-tece, please enntact Mr. ilnhn Gilray on (301) 492-4730.
Sincerely, e-h 4
Walter P. kahss, C i f dQuality Ass'Urance B'Minch Division of Engineering E
52 MM. ] 9........
Docket No. 50-271 BVY 98-22 4
Page I of 10 Attachneemt 2 Reactivity ControlSysteams Content of Standard ANS 22 Draft 4. Rev.1 (1973)
ANSI /ANS-52-1-1983 Gectxm of Document 4.2 4.2 i
A. Safety Function ne reactivity control system functions to make and hold the 77 e nuclear saferrfunctirm ofthe reactivity control systems is to reactor suberitical under Condition of Design 11, III and IV and achiew andmamtain the reactor core sa iiiuJfor arr mode to hold the reactor subcritical under normal shutdown ofnormal operation or em or to introduce negatiw #emti,irj conditions.
orlimit the introduction ofpositiw rextivirrfor anv PC-3A or S ewnt.
B. Definition De reactivity control system is comprised of the following-The reactivity control system is m..y.bcd of the followieg-a.
Components necessary for scram such as control rods, a.
Components necessary for scram such as control rods, control rod drives, and portions of the control rode drive control rod drives, and portens of the control rode drive control units control units b.
Standby liquid control system b.
Liquid poison control syvem c.
Recirculation pump trip system i
d.
Reactor coolant recimilation flow control C. Safety Class SC-2 for reactivity control components and the standby SC-2 for reactrvity control syvems pressure boundary reactivity control components wmy..at within the scope of ASME B + PVC, Sec. Ill SC-3 forallper components 1
i
-e a
,r-,
e w
w ev
.e--
u
Docket No. 50-271 BVY 98-22 Page 2 cf l0 Reactor Coolant System Content of Standard ANS 22, Draft 4, Rev. I (1973)
ANSI /ANS-52-I-1983 Section of Document 4.4 4.4 A. Safety Function Cool the reactor core and to form a barrier against the release SAME.
of reactor coolant and radioactive material to the environs.
To provide syvem pressure relief.
Non Nuclear Safety fte of the RCS is to transfer heat from the reactor core to the power conversion system or shutdown heat removal systems for any normal gu.dkni.
. NC.th The RCS is comprised of the following-SAME Reactor coolant pressure boundary components such as a.
reactor vessel; main steam lines out to and including the outermost primary containment isolation valve; safety and relief valves; feedwater lines out to and including the outermost primary containment isolation valve; recirculation piping, pumps, and valves; cu.uyuucat supports; and reactor vessel appurtenances such as control rod drive housing, nozzles and guide tubes.
b.
Main steam flow line restnctors, main steam and feedwater line isolation valve operators, portions of safety / relief valves needed for the automatic depressurizing function c.
Other mechanical components such as the relief valve discharge piping.
d.
Other electncal wmyvowts such as the recirculation pump motors SC-Ifor RCPB equipment mrhm the scope ofASME B+PI C SC-I for RCPB components, excluding 3/4" lines or less C. Safety Class
- SC-2 for 3/4" lines or less and components in Definition Sec. III SC-3foraH orhera p as, unimSC-2 is requiredto past (b).
SC-3 for all other components (Defimition (c) and (d).
sarig-interfxe cracria of3.32 e
- Note - VYNPS follows more closely the requirements of ANS52.1. Ilowever, piping downstream of the relief and safety valves in Nuclear System Pressure Relief System is classified as non-nuclear safety. See VYNPS FSAR section 4.4.5.
Derket No.50-27I
~
BVY 98-22 Page 3 of 10 Shutdown IIcat Removal Systems Content ofStandard ANS 22. Draft 4, Rev.1 (1973)
ANSI /ANS-52-1-1983 Section of Document 4.5 4.5 A. Safety Function Remove residual heat from reactor cort during shutdown 7he nuclear saferrfanctions ofthe SHRS for anr esent ukn ik conditions and maintain core coolant inventory during reactor is shutdown that does not require ECCS operation are Remose residual heatfrom the RCS ly direct circulation of Conditions of Design I and II. Portiens of the STIRS which a
form part of the RCPB also form a bamer for containic3 the reactor ch aral radioactive material and reactor coolant.
b.
Afaintain reactor coolam irrentory in the RCS The Non Nuclear Safetrfunctions cfthe SHRSare to remove residual heatfrom the RCS or maintain reactor coolant inwntory in the RCSfor norrral operation ukn the ree-ror is shur Jaun-B. Definition ne SliRS are comprised of the following.
SAME Reactor core isolation cooling system components such as a.
steam piping and valves, turbine drive, pump, coolant piping and valves.
b.
Residual heat removal system components such as RIIR pumps, heat exchangers, valves and piping.
c.
Electrical and control components associated with RCIC and RIIR systems.
SC-2 for SIIRS part of RCPB, within the scope of ASME SC-1 for SIIRS components part of RCPB, excluding 3/4" C. Safety Class lines or less B +PVC, Sec. Ill SC-3 for all other nuclear w nyonws SC-2 for other SIIRS components and 3/4" lines or less NNS for Non Nuclear Safety SC-3 for other safety related components q
- r 2%
um%
Docket No.50-27I BVY 98-22 Page 4 of 10 Cooling Water Systems Content of Standard ANS 22. Draft 4. Rev. I (1973)
ANSI /ANS-52-I-1983 Section of Document 4.7 4.7 A. Safety Function Supply cooling water for the purposes of hest removal from the SAME systems and wingegats uhich provide a safety function durmg Non-Nuclear Safety functwn of the CWS is to remove heat from any Condition of Design equipment during any mode of normal ne, or event.
B. Definition The CWS consist of forced circulation loops that provide heat The CHXare defmedas t/mse sutems sharprorrJe heat removal 5
removal from systems and components. Portions of these CWS armf hear tranrportfrom equpment to the alumate heat sink. The provide a safety function such as the residual beat removal.
CD50pically consists ofcooling sntems wherem coolmg is containment cooling, diesel generator cooling. emergency core accomp/nhed by wuter direeth from the ninmate heat smA or cooling equ>ent and area cooling.
throegh an intermediate closedsprem that is cooledin turn by water direct &frw the uitmsate heat sink.
A service unter sntem tspically inclu&~s:
Pumps to circulate wuterfrom the ultsmate heat sink a
through thevpa.; to be cooled and b.
Ptymg. ndses anJfittmgs nee &~d between theprinci;4e components in or&v toprovide airTrorr'ateFaths andfow control An intermediate CH5 espically includes:
flear exchangers used to transfer heatfrom the intermedure a
closed-systen water to the servsce waterfrom the ultmuate heatsink.
b.
Pumps to circulate suf:cient closedcoolmg systemfew to meet the manmum heat removal objectises.
A surge tank to accommodate volume changes andto serve c.
for makeup control, d P$ing, valres anJfittmgs neededbetween hey Mq,A components to provide approprsatefewpaths andfow contrcL SC-3 for C% Lwr.. cat for nuclear safety SC-3 for CWS components performing a safety function C. Safety Class NNS for other CWS equ4,ncat "Other" for other CWS components
1 Docket No.50-27I l.
BVY 98-22 Page 5 of10 Emerzency Core Coohng Syh Coseest of Standard ANS 22, DrsR 4. Rev.1 (1973)
ANSE/ANS-52-1-1983
~
I Section of Document 4.8 4.8 9
A. Safety Function Limit core damage and metal-water reactiorts by provxiing Pror:Je coo &mt to the RCSfor arr emir thur regurer i
sufficient er~secy core cooling when required during engmeeredsaferyfeursres armaran when other anamur of Conditions of Design III and IV. Portions of the e,~ ency core i
cooling systems also function as a bamer for contaming pror:dag coo &mt are not saficaent to adapmasely cool the 4
reactor core.
i radsoective masenals.
B. Definition Those muisim.b which must function to provide water to Those s3 ws and m..yo.~ s that provide the nuclear safety adequately cool the reactor core for Conditions of Design III and function above. The ECCS also include the sources of water i
IV when ea.3ecj cooling is required. The ECCS shall also necessary to accomplish the nuclear safety function.
)
include its source ofinjection water necessary to accomplish safety fus.ctions. Portions of the ECCS form part ofthe RCPS.
These portions include piping and equipment that communicate with the RCS, and extend to and include the outermost pnmary contamment isolation valves. The ECCS may consist of several subsystems to accomplish the required functions so long as the criteria established below are met by the overall operation for the ECCS nder the specified Conditions of Design.
}
C. Safety Class SC-1 for ECCS comyomos part of RCPB SC-2 for ECCS part of RCPB. within the scope of ASME e
SC-2 forother ECCS components B+PVC Sec. III j
e
}
SC-3 for all other (omyo.m.b that provide safety fe but are not within the scope of ASME III i
i 1
I J
i 1
4 1
j 1
.. _ - =. _ - -
Docket No. 50-271 BVY 95-22 l
. Page 6 of10 J
C _"_- _ j Coetnameet Ceetent of Standerd ANS 22, DraR 4. Rev.1 (1973)
ANSI /ANS-52-I-1983
~
Section of Dm._;.s; 4.10' 4.10 A. Safety Function Confine for treatment and controlled release to the environment Confinefor treannent andcauro#rdrdemse to she emwomment by the standby gas treannent system:
radioacthe matersds char mar leaf)Fom er soar be rdnased a..
Radioactive fission products which may leak form the outside ofsheprmiary contamment during err event.
primary containment durang Conditions of Design III or IV b.
Radioactive fission products that are released dunng Conditions of Design III or IV when the pnmary contamment is normally open, such as danng refueling
- c.. Radioactive fission products resuking from the rupture ofan mstrument line outside the pnmary contamment j
The standby gas treatment system functmas-j a.
To process effluent from the secondary containment when required to limit the discharge of radioactive material to the
,i' environs b.
To process effluent from the primary containment for post l'
LOCA, including hyya control.
1 B. Definition
- a. The secondary contamment includes those valves, pipes, seals SAME and s'ructural parts required to accomplish the secondary containment function
- b. The standby gas treatment system normally consists of:
I
- flow controlling components such as pipes, dos-mi, valves, and fans which wntam, direct, and control the flow through the system
- process components such as demisters, fikers, heating elements, and charcoal beds which assist in the removal of
)
radioactive isotopes and associated instrumentation.
C. Safety Class SC-2 for secondary contamment and standby gas treatment SC-3 for secondary contanment system i
i l
1 I
j l
1
--i
Docket No.50-27I BVY 98-22 Page 7 of 10 Containment Auxiliary Systerns Content of Standard ANS 22, Draft 4, Rev.1 (1973)
ANSI /ANS-32-1-1983 Section of Document 4.11 4.11 A. Safety Function Limit the primary containment temperature and pressure during CASfunctions are to:
conditions ofdesign 1II and IV.
Remow hearfrom arnilunit the pressure in theprunary a
contamment b.
Remow airbornefissionproductsfrom thepremary containment atmosphere c.
Control combustible gas mixtures in the primary containmentatmosphere d Control andtreat radioactive materials releasedto the secondarycontainment B. Definition The major equipment includes heat exchangers required for The CASare 4-fu:edas those sntems andco,,p,,w,.s which rejecting heat removed from the suppression pool water and from v provade the nuclear safetyfunctiort the primary containment atmosphere, pumps, pipes, valves, ring 77 e CASconsists of headers, and fittings needed to connect these components a Primary containment supps ession poolcooling sprem b.
Przmary contamment sprarsprem c.
Prsmary contamment imfrogen controlsntem d Secondarr containment atmosphere treatment system C. Safety Class SC-2 for CAS components SC-2for AGpressure boundary equipment andsupports within the scope ofASAfE B+P1*C Sec. 3 SC-3for other AGcomponents whsch provide nuclear safety xv5for an orhercomponents
1 Docket No. 50-271 BVY 98-22 Page 8 of 10
\\
{
t' Radioactive Waste Processing Systems Content of Standard
- ANS 52.1 Draft 1 ANSI /ANS-52-1-1983 Section of Document 4.13 4.17 A. Safety Function Confine or immobilize radioactive materials within the plant The RHTSpof no nuclear saferrfuncrwrt such that the requirements of Secten 2.2.3 (a) are met.
7he Non-Naclear Saferyfuncrmn ofthe RNTS is to control the RWPS shall function to control the collection, processing and collection, p w wing and daposal ofradmactive morerials so disposal of radioactive materials so that doses to persons onsite shar dases ogsne are mamramed withm the criterna and and offsite are maintamed within the limits established in Table 3-1 10CFR20 and the design objectives identified in 10CFR50.
{
B. Definition RWPS is that equipment, including piping, valves, pumps, 7 hose structures..g stems, andcomponents that provede the fittings, tanks, process equipment, buildings, and structures saferrfunctiort The RHTS tipically consists ofpipmg. vaher, j
needed to collect, transport, store, treat and sample radioactive pumps.fttrings, ranks. process equipment. badJmgs, and waste materials, and for preparing such materials for reuse or s mi, ; neededro collect ir-et store w andsample disposal radioactise maste marcrwis. andforp.mng such materials Ventilation systems ahich service radioactive areas shall not be for reuse or deposal 7he radioacrise wastes include solidx, considered to be part of the radioactive waste processing system; liquidr, andgases.
however, they can be used for the treatment ofsuch effluents.
C. Safety Class SC-3 for components of the radwaste system that process or NNSfor alles.,.ar hou-c radioactive wastes and designed for the SSE as follows-a.
Gaseous radwaste components shall be SC-3 unless a single component failure would not result in calculated potential exposures in excess of.17 rem whole body at the site boundary Gaseous radwaste components shall be designed for the SSE unless postulated simultaneous failure of all j
anupvocr.ts not designed for the SSE would result in l
conservatively calculated offsite exposures significantly below 10CFR100 guidelines b.
Liquid radwaste vowis.ts shall be SC-3 unless (1) they I
are located in a SC-3 building designed for the SSE or (2) if a single component failure would not result in calculated l
4 potential exposures in excess of.17 rem whole body at the
(
i site boundary. Liquid radwaste components need not be l
designed for the SSE (1) if the component is located :n a SC-3 building designed for the SSE or (2) if SSE would
~ DocketNo.50-271
. Page 9 of 10 Content of W
- ANS 52.1 DrsR 1 ANSL'ANS-52-I-1983 resuk in conservatrvely calca:ased offsne exposures significantly below 10CFR100 guidelines it must be noted that ANS-22 Section 14 Page 13-1 was missing from all the available copies of the ANS-22 documer.t.
As a substitute, the information from Draft I ofANS 52.1/N212.was used. This wm done with the understanding that the material was very similar, if not exactly the same as ANS-22, Draft 4, Rev.1.
See note in Question Ib. Response under Safety Class 3 (SC3) definition.
Docket No. 50-271 BVY 98-22 Page 10 of 10 Control Complex
~
Content of Standard ANS 22 Draft 4, Rev.1 (197??
ANSI /ANS-52-1-1933 Section of Document 4.17 4.16 A. Safety Function Provide a centralized control area for plant safety Provide ccetralized areas for the control and systems functicns during any Condition of Design monitoring ofnuclear safety-related equipment during any mode of normal operation or event B. Definition Contains panels for unit control, including The controlcompler is defmedas those strws., A recording instruments, switchyard control for oft-sprems, amImm,,,,a sharprovidethesaferr site power, radiation monitoring. in-core function ins umwh and nuclear instrumentation 7he controlcompter typical & consists of readouts, and computer operator console. 'Ihe unit The main controlroom includingpanels with a
control panels contain those instruments and mstrumentation amIcontrolsfor anr mode of controls necessa y for operation of unit functions normaloperation or ewnt such as the reactor and its auxiliary system, b.
The remore shutdown system. Iocata(outside turbme generator, and the steam and power the mam controlroom. incIndmgpancIs with conversion systems. Selectwn ofloadmg from the instrumentation amicontrols to achieve and various plant electncal distribution boards such as mamram hot safe shutdown or the reactor those supplied from offsite and onsite power with aporential capabilityfor subsequent cold sources relevant to the safe operation of the shutdown through the use ofsmirable nuclear power unit is accomplished from the unit procedures control panels. The control room also includes its c.
Support areas mcladmgpanels with associated heating and ventilation systems.
mstrumentation and controlsfor such operations asfuel hanEing, radioactive muste processing andcampling C. Safety Class SC-3 for control room and e chuo systems, and Sc.Jfor controlroom.y4wprovidmg equipment wo>.uy for the control room to meet nuclearsafe-tvfunction its performance criteria XYSfor other comj,,,s
.