ML20214V525
| ML20214V525 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 03/17/1987 |
| From: | BECHTEL GROUP, INC. |
| To: | |
| Shared Package | |
| ML20214U944 | List: |
| References | |
| PROC-870317, NUDOCS 8706120140 | |
| Download: ML20214V525 (20) | |
Text
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RAllCHO SECO NUCLEAR GENERATDIG STATI0tl SACPA!! ENTO l1UNICIP'AL- UTILITY DISTRICT DESIGN CALCULATION REVIEW PROGRAM PLAN REVISION O MARCH 16,1987 '
u Prepared by Becht I ,. N Date .9//6/87 ReviewTeamLeadge ,
Aporoved by M. H A G A/k Mw Date617$[
Bechtel Manager of En neering
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St!UD Nuclear Engineering Manager Bechtel Western Power Corporation
San Francisco, California
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1 OESIGN CALCULATICH REVIEW PP0GPAll TABLE OF CONTENTS Page I Section Description 1.0' INTRODUCTION AND PURPOSE 1 2.0 SCOPE 2 3.0 PROCEDURE 3 4.0 RESULTS, RECOMMENDATIONS AND 5 CONCLUSIONS 5.0 ORGANIZATION 6 EXHIBIT 1 ECN REVIEW SUMMA,RY' Form EXHIBIT 2 CALCULATION REVIEW
SUMMARY
Form EXHIBIT 3 CALCULATION REVIEW OBSERVATIONS Form EXHIBIT 4 RESPONSE TO REVIEW OBSERVATION Form EXHIBIT 5 CONTINUATION SHEET Form APPENDIX 1 SYSTEM REVIEW SCOPE APPENDIX 2 ECN REVIEW SCOPE APPENDIX 3 REVIEW TEAM MEMBERS
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DESIGN CALCULATf0N REVIEW PROGRAM 1.0 It!TRODUCTICH MD PURPOSE The Design Calculation Review (DCR) Program will entail 3 tecnnical revi w of Rancho Seco design. This review will establish the technical adequacy and completeness of existing calculations for the scope described in section 2.0. The specific technical and programmatic problems identified by the NRC vertical audit team in their February 12, 1987 exit meeting will be considered in the review, as well as other aspects recuired for the design and the design intent to be adequately supported by engineering calculations.
The DCR Program will provide a mechanism for documenting review results, providing recommendations and closing out any required actions. The review and recommendation process will be performed by Bechtel while corrective or investigative action will be addressed by SMUD. Problems identified during the review will be documented as observations on standard forms.
Observations may result from the review of individual documents or, after all individual documents have been reviewed, from an evaluation of all observations for generic or programmatic concerns. The technical and programmatic significance of each observation will be described and corrective or investigative action will be recommended to resolve the observation. Recommendations will be made consistent with the significance and generic nature of the observation and commensurate with the nature of the material that was reviewed.
Observations with potential safety significance are reviewed by the Bechtel Manager of Engineering before release to SMUD for follow-up action.
However, a preliminary copy of the observation is provided to SMUD for information immediately. Potential safety significance is a condition which the reviewer believes may exist which could result in a loss of safety function to the extent that there may be a major reduction in the degree of public health and safety protection. It is SMUD's responsibility to determine whether or not the con'dition is . safety significant.
The results of SMUD's investigative or corrective action will also be documented on standard forms and submitted to Bechtel for concurrence that the observation has been satisfactorily resolved. If Bechtel cannot provide this concurrence, the reasons will be documented and transmitted to SMUD.
Any observation with potential safety significance will be satisfactorily resolved prior to plant restart or the condition will be determined to have no safety significance. Observations which may not be resolved by plant restart will be evaluated by SMUD and justification will be provided for resolution after plant restart.
A final report will be issued summarizing the results of the DCR Program.
All observations will be addressed along with actions that were taken to resolve them. Conclusions will be provided regarding the technical adequacy and completeness of the existing calculations within the review scope. Any applicability of these conclusions outside the review scope will also be presented.
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DESIGN CALCUl.ATION REVIEW PROGRAM 2.0 SCOPE The DCR Program will address the recent design activities most Oritical to
, plant restart. To accomplisn this goal, the review scope will include all ECN's (Engineering Change Notices) issued against " Selected Systems" which are scheduled for implementation prior to plant restart. " Selected Systems" are defined in the Rancho Seco Action Plan, Amendment 2, December 15, 1986.
Appendix 1 of this program plan lists 1;hese systems with their associated Rancho Seco calculation index identification code. The ECNs against these systems which are scheduled for implementation prior to plant restart are noted in Appendix 2.
l ECNs may authorize physical changes to the plant which require supporting l engineering calculations. The initiating problem, as described in the i
System Status Report (SSR) or other applicable reference documents, will De reviewed to ensure that the design intent is adequately addressed by the ECN. The DCR Program will establisn the completeness of existing.
calculations for each ECN identified in Appendix 2 through a multidiscipline review of the ECN design changes and the type of existing calculations. A reviewer from each affected discipline will determine whether the scope of existing calculations is sufficient to support the design changes made in
,' that discipline's field for each ECN. The effect of the ECN on both system l level process variables and structural capabilities will be evaluated. Any required calculations which do not exist will be iden,tified.
Design requirements common to systems and structures throughout the plant are programmatically controlled by individual SMUD procedures. The need for any additional reviews of these programs is presently being evaluated by SMUD. Therefore,. calculations associated with these programs are not .
I. included within this calculation review scope.
The technical adequacy of the existing calculations identified from the review of ECNs is determined thr'ough a detailed review of both the system level and structural type calculations. This review will cover 100% of the system level calculations and a 20% sample of the structural type calculations. If any calculations are too specialized for Bechtel to
! completely evaluate (e.g. detailed equipment manuf acturer calculations),
j this conclusion will be so documented. The 20% sample will be subjectively 4 selected to include unique or complex calculations as well as representative
- examples of the standard calculation categories (e.g. pipe supports, i structural steel, etc. ) . Calculations which were generated for the initial i plant design or for ECN's implemented prior to the December 1985 plant shutdown will also be reviewed as necessary to establish the completeness
< and adequacy of calculations for the ECNs listed in Appendix 2. Such a review of earlier calculations will be performed to validate an assumption or referenced input used in a recent calculation, to confirm a previous
' revision was an acceptable base for a recent design change or to verify that an earlier calculation was correctly revised due to a recent design change.
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DESIGN CALCULAT10N REVIEW PROGRAM 3.0 PROCEDURE This section provides the detailed process '.shich will ce usad implement the DCR Program. Exhioits 1 througn 5 will ce completed as apprcpriate to document the program results.
3.1 The lead discipline reviewer obtains a thorough understanding of the ECN and the problem that it is intended to resolve. The corresponding System Status Report (SSR), ECN Design Basis Report (DBR) and other applicable references are reviewed to accomplish this. See Appendix 2 for ECN lead disciplines. The SMUD system design engineer may be contacted if necessary ta_ facilitate this understanding. The reviewer also confirms that the problem description and the ECN problem resolution are compatible.
3.2 The lead discipline reviewer coordinates completion of the ECN Review Summary form (Exhibit 1). Using available reference material, such as the ECN DBR or system calculation index, the scope of existing calculations is documented along with the respective revision numbers and responsible disciplines. Each calculation listed is labeled to indicate if it is a system level or structural type design calculation.
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3.3 The lead and all affected discipline reviewers jointly evaluate the scope of existing calculations to determine its adequacy to support the ECN design. The discipline reviewer's experience plus informal checklists provide the basis for reaching a-conclusion. For each instance where it is concluded that a calculation required to support the design is missing, a Calculation Review Observation form (Exhibit 3) is processed per step 3.6.-
3.4 A Caiculation Review Summary form (Exhibit 2) is used to document the detailed calculation reviews. A form is completed for every system level calculation and for 20% of the structural type calculations in the review scope. Structural calculations will be selected for detailed review by the discipline reviewer to include the more unique and complex calculations plus representative examples of the various standard types of calculations. Structural calculations selected for review are noted on the ECH Summary form. If a calculation is considered to be too specialized for Bechtel to evaluate, the reviewer will document this judgement in the comments section of the ECN Summary form..
. 3.5 The responsible discipline reviewer answers the calculation adequacy checklist questions. Significant input from other disciplines is documented in the comments section of the form. Calculations' prepared prior to the ECN are reviewed as necessary to verify the adequacy of the ECN design. Such a review is normally required if the recent ECN or its associated calculations rely on inputs from earlier calculations or if it is apparent that earlier calculations are effected by the recent desian change. Earlier calculation reviews are documented in the comments
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DESIGN CALCULAT80N REVIEW PROGRAM section of tne form. A Calc'Jiation Review Observation form (Exhibit 3) is .orocessed per steps 3.6 for each instance tnat results in a negative
("N") response to the calcJ1ation adecuacy checxlist questions.
3.6- The Calculation Review Observation forms which are required from steps i 3.3 and 3.5 are initiated by the reviewer who identifies the problem.
The observation is clearly described such that the subsequent statements l on significance and recommendations are a logical extension of the
- issue. The technical . significance evaluation documents the impact, if i any, on plant hardware, system function or plant procedures. The impact to SMUD procedures and practices is assessed under the programmatic significance section.
Corrective action is recommended as appropriate to resolve.the specific observation. - If additional infomation from SMUD is required to resolve the observation, investigative action recommendations are provided.
The completed observation form is reviewed by the Bechtel calculation-review team leader for conformance to the program intent, consisten'cy, and reasonableness prior to being assigned an observation number. A log is maintained to track all observations, revisions and resolutions -
If the recommendations would require extensive follow-up action by SMUD, in the judgement of the reviewer, the observation will be submitted to 3-the appropriate Bechtel Chief Engineer for review and concurrence.
Observations which are identified as potentially safety significant are transmitted to 'the Bechtel Manager of Engineering for concurrence and 3
possible additional action. A preliminary copy of the observation is
- transmitted to the SMUD Manager of Nuclear Engineering for information.
Chief Engineer and Manager of Engineering reviews are documented in the
!~ additional reviews section of the fom prior to submitting the form to i St1UD for resolution.
Observation forms can be revised if the need arises. A new set of signatures is required for each revision.
3.7 For each Calculation Review Observation form issued by Bechtel, SMUD prepares a Response To Review Observation form (Exhibit 4). Meetings may ,
be held between Bechtel and SMUD personnel to clarify the observation or discuss potential corrective or investigative action alternatives. The preparer notes wnether or not the observed condition is safety significant. The actions taken or planned by SMUD are documented in the appropriate sections and the response is reviewed by the responsible SMUD Discipline Group Supervisor. Observations concluded to be safety significant are reviewed by the SMUD Manager of Nuclear Engineering prior to being returned to Bechtel.
3.8 The SMUD response is normally evaluated by the originating Bechtel reviewer and the fom is marked to show whether or not the observation is resol ved. If review meetings with SMUD personnel are unable to resolve the observation, the basis is described in the comments section and the response fom is returned to SMUD. Bechtel's action on that observation is considered to be complete at this point.
Prior to closing out the observatiofin the logfor returning an unresolved response form to SMUD, the fom is reviewed at the same organizational level within Bechtel as the corresponding observation form.
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DESIGN CALCULATION REVIEW PROGRAM
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4.0 RESULTS, RECOD1*ENDATIONS AND CONCLUSIONS The overall results of tne DCR Program will oe documented in a final report.
This report will include a program description, a summary of observations ano recommendations by Bechtel, a summary of ooservation responses and actions taken by SMUD, a conclusion describing the adequacy of design calculations within the review scope, and an extrapolated conclusion on the adequacy of design calculations outside the review scope to the extent possible considering the nature of the material that was reviewed.
The final report is expected to be issued within 4 weeks of resolving all observations. In the event that all observations cannot be resolved within a reasonable period, and interim report will be issued' which will document conclusions that can be made at that time and the items that must be resolved prior to issuing the final report. A schedule for final resolution will be provided and justification for restarting the plant with any items unresolved will also be included.
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DESIGN CALCULATION REVIEW PROGRAM 5.0 ORGANIZATION
. The design calculation review will ce perfonned primarily at tne aancno Seco plant site by a team of senior, experienced Bechtel engineers. The work of the review team will be under the overall direction of the Manager of Engineering, Bechtel Western Power Corporation, San Francisco. Day to day direction of the review team activities as well as program implementation, planning and coordination is the responsiblity of the Review Team Leader.
Routine interface with the SMUD Nuclear Engineering Department is also handled ~
by the Review Team Leader.
The review team consists of representatives from each engineering discipline as required to competently review the scope described in section 2.0.
Additional reviews may be requested through the appropriate hcme office Chief Engineer for significant issues or for technical issues beyond the expertise of the review team members. All requests for additional assistance are coordinated through the Review Team Leader.
Exhibit 3 identifies the present review team members and will be updated for the final DCR Program report.
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EXHIBIT 1 RANCHO SECO Revision 0 SACRAMENTO MUNICIPAL UTILITY DISTRICT DESIGil CALCULATION REVIEW PROGRAM ECN REVIEW
SUMMARY
ECH Number: System:
Description:
Lead Discipline: M E I C P Affected Disciplines: M E I C P Existing Calculation Numbers:
- System ** Structural ARE THE ABOVE CALCULATIONS SUFFICIENT TO SUPPORT THE ECN DESIGN?
Lead Discipline: [] Yes [] No Reviewer: Date:
Affected Discipline: [] Yes [] No Revi~ ewer: Date:
[] Yes [] No Reviewer: Date:
[] Yes [] No Reviewer: Date:
If "No" is indicated above, complete a Calculation Review and Observations form for each instance.
COMMENTS:
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EXHIBIT 2 RANCHO SECO Revision 0 SACRAMENTO l1UNICIPAL UTILITY DISTRICT DESIGN CALCULATION REVIEW PROGRA'.1 CALCULATION REVIEW
SUMMARY
ECN Number: System:
Calculation Number: Revision: Date:
Description:
Responsible Discipline: l1 E I C P Calculation Adequacy Checklist:
- 1. The calculation purpose is clearly stated? Y N
- 2. Applicable codes, standards and other project requirements Y N (FSAR, Reg. Guides, etc.) are identified along with applicable dates and sections?
- 3. References are appropriate and retrievable with applicable Y N dates and sections?
4 All assumptions are clearly described with technical '
rationale? Y N
- 5. - All assumptions are appropriate for the calculation's Y. N purpose?
- 6. All equations and calculation techniq'ues are appropriate Y N for the intended purpose?
- 7. The calculation has been checked? Y N s
- 8. The calculation conclusion coincides with the calculation's Y N purpose?
( 9. Considering the purpose, inputs and methodology, are the Y N l calculation results reasonable?
If "N" is indicate'd above, complete a Calculation Review Observati'o n form.
1 Comments:
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i Prepared by: Date:
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EXH888T 3 hvision 0 r RANCHO SECO
. SACRAMENTO P1U!!ICIPAL UTILITY DISTRICT DESIGN CALCULATION RE'/IEW PROGRAfi CALCULATION REVIEW OBSERVATIGH Observation Number: Revision:
ECil Number:
Calculation Number: Revision: Date:
ECN/ Calculation
Description:
Observation
Description:
i Significance: Potentially Safety Significant? [] Yes [] No [] Insufficient Information Technical s
Programmatic i
I Recommendations:
Corrective Investigative i
Prepared By: Date: l I
Reviewed By: Date:
l Additional Reviews: Date:
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EXH838T 4 Revision 0 RANCHO SECO SACRAItE!!TO t!UNICIPAL UTILITY DISTRICT DESIGN CALCULATI0il REVIEW PROGRAM RESPONSE TO REVIEW OBSERVATION Observation Humber: Revision:
Safety Significant? [] Yes [] No Response / Action Taken:
Action Planned / Schedule:
Prepared By: Date:
Reviewed By: Date:
Observation Resnived? [] Yes () No Comments: .
Prepared By: Date:
Reviewed By: Date:
_ Additional Reviews: Date:
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EXH891T 5 RANCHO SECO RQvision 0 SACPAMENTO MUNICIPAL UTILITY. DISTRICT -
DESIGN CALCULATION REVIE'l PROGRAM CONTINUATION SHEET
[] ECN Review Sumary - ECN No.
[] Calculatioh Review Sumary - Calculation No.
[] Calculation Review Observation - Observation No.
[] Response to Review Observation - Observation No.
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DE51GN CALCULATION REV8EW PROGRAli APPENDIX 1 _
SYSTEM REVIEW SCCPE Calculation Description System Code Index Code Reactor Coolant System RCS RCS Decay Heat Removal System DHS DHS
> Seal Injection and Makeup System SIM SIM (Include High Pressure Injection)
Purification and Letdown System PLS PLS Nuclear Service Cooling Water System NSW NSW Nuclear Service Raw Water System NRW NRW Steam Generator System OSTG MSS Main Steam System MSS MSS Main Feedwater System MFW FWS Auxiliary Feedwater System AFW AFW Reactor Protection System (includes ARTS) RPS RPS Safety Features Actuation System SFS SFS Emergency Feedwater Initiation and Cont'ror System EFIC EFIC Integrated Control System ICS ICS Non-Nuclear Instrumentation System NNI NNI 125 Volt DC Vital Power System DCV DCS DCS VBS 125 Volt DC Non-Vital Power System DCN OCS DCS VBS 120 Volt AC Vital Power System 120 EDS VBS PTS
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DESZGN CALCULATZCN REVIEW PROGRAM SYSTEM RE'lIEkl SCCPE (cont. )
Calculation Description System Code Index Code 480 Volt AC System 480 EDS PSG VBS PTS
- MCC 4160 Volt AC System 4KV EDS PSG VBS PRL-PTS 6900 Volt AC System 7KV EDS PSG
< PRL PTS Radiation Monitoring System RDM RDM i Control Room /TSC Essential HVAC* System HVAC HVS Emergency Diesel Generator System EGS- EGS Component Cooling Water System CCW CCW Plant Air System SAS SAS r Instrument Air System IAS IAS Auxiliary Steam System ASC ASC Fire Protection System FPS FPS FPP HSEB Essential HVAC NHVS HVS NEH t
Reactor Sampling System RSS RSS Page 2 of 2 Revision 0
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DESVGN CALCULAT!ON REV!EB PROGRAM APPENDIX 2 ECtl REVIEW SCCPE (Reference - SMUD Nuclear Engineering ECN Closure Status Report, Dated 3/10/87)
ECH SYSTEM LEAD NUMBER CDDE DISCIPLINE NUMBER CODE DISCIPLINE A2332 RDM M A5415H AFW' I A3062 AFW M AS415J AFW P A3285 IAS/SAS P AS415K EFIC I A3319 AFW P A5415L EFIC I A3441 IAS I AS415M AFW I A3660Z DCS E AS415N- AFW I A3725 FPS M AS415P AFW I A3725A NEH/ FPS M AS4150 AFW I i' ,
A3748 EGS M A5415S EFIC I A3867 FPS E A5415T EFIC I A3867E FPS E AS415U AFW I A3881 -A EGS E A5415V AFW I A4353 RSS P AS415W AFW I A4382 FPS E AS415X AFW I A4414 RDM I AS415Y MFW -
I AS415Z EFIC I A4615 RCS P A5530 FPS M
- A4615A
- RCS P ?A5544 AAE E A46158 RCS P A5564 EGS/4KV E A4687 DCS E A4711I RSS M A5620A NNI I A4714 I A56208 NNI I A5034
' RDM kVS I . A5620C HNI I A5198 480 E A5620D NNI I A5233 IAS/SAS M A5620E NNI I A5249 s NNI I A5620F NNI I
- A5339 CCW I A5672 RPS I AS415 EFIC M A5710 120 E A5415A EFIC M A5735 RSS I AS415AA1 FWS I A5743 IAS/SAS I AS415AB MFW M
- AS415AC EFIC P- A5760 NNI I AS415AD EFIC P A5765 ASC I l A5415AE EFIC 7 A5767 FPS M AS415AF EFIC I A5772 DHS E AS415AH EFIC I A5773 RSS I A5782 HVS E 1 A5415B AFW I R0048 NRW I Li R0087 CCW I AS415C EFIC I R0112 4KV E
! A54150 RPS I R0142 HVS M AS415E RPS I A5415F AFW I R0163 AFW E
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DESZGN CALCULATION REVZEW PROGRAM-APPENDIX 2 ECN REVIEW SCOPE (cont.)
ECN SYSTEM LEAD ECN SYSTEM LEAD NUMBER CODE DISCIPLINE NUMBER CODE DISCIPLINE R0164 HVS I R0594 -NNI E R0182 HVS I R0595 SFS E R0197 FPS M R0598 DHS' I R0225 RSS I R0608 DCS E R0285 DHS M R0609 DCS E R0286 PLS P R0614 RPS- E R0295 RDM E R0615 RPS I R0314 HVS M R0619 SFS E R0317 RSS I R0636 RPS E R0328 NRW E R0367 SFS E R0337 DHS I R0642 RPS I R0357A AFW I R0644 RPS E R0357B ICS I R0663 RPS E R0359 NNI I R0685 NNI I R03598 NNI I R0688 RCS I R0361 RSS M R0380 RCS I R0699 AFW E.
R0415A 4KV E R0415B EGS E R06998 MFW E R0416 ASC P R0424C RSS M
. R0717 MFW I R0732 RSS I R0442 ICS I R0763 HVS M R0457 RDM I . R0764 HVS M R0458 FPS M R0765 MSS E R0767 FPS M R0459 RCS/SFS E R0769 HVS M R0465 RSS I R0770A EGS M R0469 ICS E R07708 EGS M R0470 FWS I
. R0477 ICS E R0788 HVS M R0488 HVS P R0789 HVS M R0498 DHS P R0796 HVS E R0499 NNI E R0803 FPS M R0517 ICS I R0517A ICS I R0822 NNI I R0527 FPS M R0823 MFW I .
?R0546 AAE E R0824 ICS I R0559 RSS I R0562 RSS I R0825 ICS I R0584 SFS E R0826 NNI I R0585 SFS E R0828 MSS /MFW I R0587 SFS E R0830 SFS E R0588 SFS E R0838 FPS M Page 2 of 4 Revision 0
.0ESXGN CALCULAT80N REVTEW PROGRAM APPENDIX 2 ECN REVIEW SCOPE (cont.)
ECN SYSTEM LEAD ECN' SYSTEM LEAD NUMBER ~ CODE DISCIPLINE NUMBER CODE DISCIPLINE R0859 AFW/CCW I R1023D NEH M R0861- MSS- I R0126 - NEH. M R0127 SIM 'P
'R0872 RDM I _ - R1028 RCS I.
R0876 MFW I R1035 NEH I R0878 ASC I R1036 - SIM I R0889 ASC I R1041 RDM I R0890 EGS E R1045 4KV E R0894 MFW P R1078 - FPS M R0896 - MFW/NNI- I R1079 FPS E R0899 7KY E R1081 HVS M R0904 HVS M R1098 IAS/SAS M R0904A HVS M R1107 NEH M R09048 HVS M R1108 EGS E -
R0904C HVS M R1118 HVS M R0904D HVS M R1119 NEH M R0911 . HVS E R1127 OCS- E R0913 RDM I R1128A 4KV- E R0914 SIM E R11288 480 E R0918 ICS I R1128C 4KV E R0919 NNI E R1128D 4KV E R0924 480 E R1128E 4KV E R0927 DCS E R1142 FPS M R0937 NEH M R1150 EGS E R0938 HVS M R11.57 480 E R1158 NEH M R0953 NNI I R1159 HVS M R0955 DCS E R1160 HVS M R0956 FPS E R1170 NEH/HVS M R0957 HVS I R1185 FPS M
?R0968 MOV E
?R0975 AAE E R0989 HVS M R1214 EGS E R1000 EGS E R1217 ICS I R1002 HVS M R1218 ASC M R1227 RDM I R1018 SIM M R1230 NRW P R1022 NEH M R1255 NNI I R1257 DHS M R1023 NEH M R1259 RCS P R1023A NEH M R1260 HVS M R10238 NEH M R1272 NNI I R1023C NEH M R1295 SFS E
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DESIGN CALCULATION REVIEW PROGRAM
. APPENDIX 2 ECN REVIEN SCOPE (cont.)
ECN SYSTEM LEAD ECN SYSTEM LEAD NUMBER CODE DISCIPLINE- NUMBER CODE DISCIPLINE R1322 MSS P R1323 120 E R1328 RSS I R1367 MSS I R1372 RCS M R1392 480 E R1399 4KV E R1401 FPS M R1402 HVS M R1407 OCS E R1414 FPS M R1419 NNI E R1451 SIM M R1460 SIM M R1461 SIM M
?R1465 AAE E R1486 FPS M
?R1490 MOV E
?R1493 MOV E R1496 MFW I R1508 RPS .I
? = Generic type of ECN - Specific applicability to Selected Systems to be determined during the review process.
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DESIGN CALCULATION REVZEW PROGRAM
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APPENDIX 3 REVIEW TEAft MEMBERS I Name Responsibility R. J. Bulchis
- Lead J. C. Bradford Mechanical - NSSS/B0P
. J. J. Cayanaugh Mechanical ,HVAC F. E. Stumpp - Mechanical - Fire Protection L. Carey Controls C. K. Kuo Electrical S. K. Shim Electrical 1
P. W. Chew -
Electrical M. H. Lee Plant Design - Stress P. Gulko Plant Design - Pipe Supports (Any additional team members will be identified in the final DCR Program i
report. )
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