ML20055D348
| ML20055D348 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/29/1990 |
| From: | Mroczka E NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| B-13560, NUDOCS 9007060217 | |
| Download: ML20055D348 (31) | |
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June 29, 1990 Docket No. 50 245 B13560 j
RE: CRDR ISAP
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L U.S. Nuclear Regulatory Commission Attention: Document Control Desk l
Washington, DC 20555 Gentlemen: -
Millstone Unit No. 1 Response to NRC Staff Additional Information Request on Control Room Desian Review On Juns 1s, 1990, representatives for Northeast Nuclear Energy Company (NNECO)
L on behalf of Millstone Unit No. I attended an NRC Staff requested meeting at the White Flint headquarters.
NNECO personnel provided supplementary informa-tion, to that previously submitted, pertaining to the Control Room Design j
Review (CRDR) and the Integrated Safety Assessment Program (ISAP). During the meeting, additional verbal and written information for Millstone Unit No. I was provided to the NRC Staff personnel.
l The pur)ose of this letter is to provide information in addition to that I
providec during-the meeting as requested by the NRC Staff for the Millstone l'
Unit Nd 1 CRDR program.
Figure 13 of the Millstone Unit No.1 CRDR Summary Report, dated October 30, 1989, identified those: priority 1 Human Engineering Discrepancies (HEDs) that were dispositioned for no corrective action. to this letter
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provides further justification and rationale for those HEDs dispositioned for no corrective action (i.e., HED numbers 6.4.003, 6.8,001, Q-3, and Q 27). to this letter provides the_ revised HED to ISAP_ crnss reference tabletto' completely replace Attachment 4 to the recent Millstone Unit No.1 ISAP submittal report, dated April 30, 1990. Attachment 3 provides reconcili-ation between the CRDR Summary Report and the revised HED cross reference l-table. provides a comprehensive description of the CRDR l
Characteristics Review Methodology, in lieu of the CRDR contractor specification. provides professional resumes of the contractor personnel who performed the Characteristic Reviews of Millstone Unit No.1.
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U.S. Nuclear negulatory Commission B13560/Page 2 June 29, 1990 We believe that this letter will provide the NRC Staff the information neces-sary to issue a Safety Evaluation Report for the Millstone Unit No.1 CRDR issue.
If you have any further questions on this topic, please contact us.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY FOR: E. J. Mroczka Senior Vice President BY:
C. F. Sears Vice President Attachments cc:
T. T. Martin, Region 1 Administrator M. L. Boyle, NRC Project Manager, Millstone Unit No. 1 W. J. Raymond, Senior Resident inspector, Millstone Unit Nos.1, 2, and 3 i
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Docket No. 50-215 B13560
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.10 i:7 Justification for HEDs Dispositioned for No Corrective Action 4
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Justification for HEDs Dispositioned for No Corrective Action 6;4.003 This HED represents fourteen (14) individual HEDs, eleven (11) of which were-
-dispositioned.for no corrective action. These HEDs identify control movements which do not conform to population stereotypes.
(NUREG 0700 Section 6.4.2.1).
6.4.003D and 6.4.003L Both these HEDs concern reverse acting controllers, where the controller output is increased to close a valve (i.e.,
reverse acting temperature controller will increase output signal to increase process temperature' which is accomplished by closing a cooling water system valve).
Modification of these controllers to conform to population stereotypes would misrepresent the process being controlled.
The CRDR core team decided that a class improvement (enhancement; shall label all such controllers as reverse acting.
6.4.003J This HED concerns a counter clockwise movement, rotary selector switch for which position is uniquely identified.
This switch is used to select LPRM display _ channels and as such the direction of rotation is not a concern.
6.4.003E and 6.4.003K These HEDs identify concerns with switches which are used only during surveil-lance testing, are not E0P related and are located on auxiliary panels.
As such, these devices are beyond the scope of review.
6.4.003C. 6.4.003F. 6.4.003G. 6.4:003H. and 6.4.003I These HEDs identify. concerns with electrical distribution system controls (motor' operated disconnects and circuit breakers). Although they deviate from NUREG ' 0700. criteria, they are consistent with the standard conventian for.
' electrical distribution. system equipment (right to close breaker; left to trip /open breaker).
6.4.003N This HED ' identifies a concern with a two position selector switch.
This switch is the LPCI valve close permissive switch.
The switch positions are uniquely labelled (normal-close), consistent with the plant convention for l_
permissive switches (the normal position being the left).
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6.8.001 J
This HED represents 5 individual, priority 1 HEDs that were dispositioned for
-no corrective action.
These HEDs identify components not grouped by task sequence or system function.
6.8.001A This HED concerns an indicating device which is 30" to the left of its asso-ciated controls.
This was dispositioned as not significant because,:the operator can take a single step to the left to read the device and is _ not required to be reading the indicator and operating the controls simultaneous-u y
ly.
1 6.8.001B This HED concerns wide range reactor level indicators which are not located near the LPCI/ core spray system controls.
There are two (2) Yarway reactor level indicators and one reactor fuel zone level indicator immediately adja-cent to the LPCI/ core spray controls for the operators' use.
-6.8.001C This_ HED concerns the. reactor D/P indication not being located. next to the l
core. pressure drop / total core flow recorder.
During asse',sment, it 'was identified that these locations are correct for the required operator actions.
These indications are not used in conjunction with one another.
6.8.001D This HED identifies two isolation condenser (IC) system valves which are 50"
-away from other IC system controls. During assessment, it was identified that
.this location aided the operators in their tasks as.it placed them in front of functionally-related indicators.
(Note:
These devices were relocated to be
- grouped with the other IC system' controls because the associated indicators-L were relocated as part of'the overall enhancement effort.)
6.8.001E
-This HED concerns a recorder associated with the hydrogen recombiners, is not
~ used in :the performance of E0Ps and is located on an auxiliary panel.
As such, this device is beyond the scope of review.
M This HED represents 14 individual -HEDs of which three (3) are dispositioned L
for no corrective action.
These HEDs concern equipment which operators L
commented should be on the main control panel.
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B13560\\Page 3 0-3A. 0-3E. and 0-3L These HEDs identify concerns with the -location of hydrogen recombiner and off-gas system controls.
These are infrequently used, non-EOP related con-trols which are located on auxiliary panels ~and as such are beyond-the scope of review.
D.:21.
This HED represents fourteen-(14) HEDs concerning controls that are difficult to use.
Four (4) of these were dispositioned for no corrective action.
0-27B and 0-27D These HEDs concerned difficulty in the operation of the electrical and mechan-ical pressure regulators and General Electric model CR-2940 control switches.
Further_ questioning (operator interviews), revealed no operational problems with the devices but reflected individual preferences.
9-21.G This HED~ concerned operation of the turbine generator and electrical-distri-
~bution controls' while synchronizing onto the grid.
These controls. are on adjacent sides of adjacent panels,-.are not E0P related and require only two steps from one to the other.
Hence this HED is dispositioned as not signifi-cant and is beyond the scope of review.'
Dall!
This HED concerns the control of reactor water level below 60" during E0P operation.
Further review of this concern.by consultation with Reactor Plant Systems discipline and operator interviews, identified that inherent system dynamics under these conditions necessitate the operational requirements which were perceived as difficult to control.
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Docket No. 50 245' B13560 Revised HED to ISAP Cross Reference (to~ replace completely Attachment 4 to the-
' April.30, 1990 ISAP Submittal' Report) l$
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. MP1 CRDR HED'S TO IS AP TOPIC CROSS REFERENCE SUBJFLT HED NUMBER ISAP TOPIC i
RELOCATE CTMT PARAMETER INDICATIONS 6.1.001 C ~
1.07.1 6.1.001D 1.07.1 6.1.001F 1.07.1 6.3.010 1.07.1 6.8.006 1.07.1 ICCR-6 1.07.1 0 14 A 1.07.1 O.19A 1.07.1 O1A 1.07.1 0 25J 1.07.1 0 27L 1.07.1 0 3M 1.07.1 l
O 3N 1.07.1 TA-4 1.07.1' TA 50 1.07.1 TA 62 1.07.1 T A-6 5 1.07.1 VD 2 1.07, t 6.9.004 1.07.1.1.07.3 TA 25 1.07.1.1.07.3 T A-31 1.07.1.1.07.3
- COffrROL ROOM ENVIRONMFNI' 6.1.004 1.07.2 6.1.006 1.07.2 6.1.019 1.07,2 0 10B 1.07.2 l
O-11C 1.07.2 011D 1.07.2 0 11F 1.07.2 0 110 1.07.2 011H 1.07.2 0 11J 1.07.2 O.11K 1.07.2 l
O-4' 1.07.2 0 7A 1.07.2 l
Q-7B 1.07.2 0-?D 1.07.2 0 7E 1.07.2 O8 1.07.2-TA-36 1.07.2 T A-4 3 1.07.2 i
INSTRUMENT SCALES 6.1.003 1.07.3 6.2.003 1.07.3 6.2.004 1.07.3 6.3.005 1.07.3 6.3.007 1.07.3 Page 1
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i j-MP1 CRDR HED'S 'IO IS AP TDPIC CROSS REFERENCE I
6.3.008 1.07.3 6.3.015 1.07.3 6.3.021 1.07.3 6.4.003M 1.07.3 6.4.005 1.07.3 6.5.002 A 1.07.3 6.5.002 B 1.07.3 6.5.002C 1.07.3 6.5.003B 1.07.3 6.5.003E 1.07.3 6.5.003F 1.07.3 6.5.0030 1.07.3 6.5.003H 1.07.3 6.5.0031 1.07.3 6.5.004 A 1.07.3 6.5.007 A 1,07.3 6.5.007D 1.07,3 6.5.008 A 1.07.3 6.5.008B 1.07.3 6.5.008C 1.07.3 6.5.008 D 1.07.3 6.5.008E 1.07.3 6.5.008F 1.07.3 6.5.0080 1.07.3 6.5.009C 1.07.3 6.5.010B 1.07.3 6.5.010C 1.07.3
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6.5.010D 1.07.3 i
6.5.010E 1.07.3 6.5.010F 1.07,3 i
6.5.0100 1.07.3 6.5.010H 1.07.3 6.5.0101 1.07.3 6.5.011A 1.07.3 6.5.011 B 1.07.3 6.5.011C 1.07.3 6.5.0! 1 D 1.07.3 6.5.01 1 E 1.07.3 6.5.012 1.07.3 6.5.013B 1.07.3 6.5.013 D 1.07.3 6.5.014 A 1.07.3 6.5.014B 1.07.3 6.5.014C 1.07.3 6.5.014D 1.07.3 6.5.014 E 1.07.3 6.5.014F 1.07.3 6.5.0140 1.07.3 6.5.014 H 1.07.3 Page 2
MPI CRDR IIED'S TO ISAP TOPlc CROSS REFERENCE 6.5.0141 1.07.3 6.5.014 J 1.07.3 6.5.014 K 1.07.3 6.5,014L 1.07.3 6.5.014 M 1.07.3 6.5.014 N 1.07.3 6.5.014 0 1.07.3 6.5.014P 1.07.3 6.5.014 0 1.07.3 6.5.014R 1.07.3 6.5.015 A 1.07.3 6.5.015 B 1.07.3 6.5.015C 1.07.3 6.5.015 D 1.07.3 6.5.015E 1.07.3 6.5.015 P 1.07.3 6.5.0150 1,07.3 6.5.016 A 1.07.3 6.5.016B 1.07.3 6.5.016C 1.07.3 6.5.016D 1.07.3 6.5.016E 1.07.3 6.5.016F 1.07.3 6.5.0160 1.07.3 6.5.01611 1.07.3 6.5.0161 1.07.3 6.5.016J 1.07.3 6.5.016 K 1.07.3 6.5.016L 1.07.3 6.5.016M 1.07.3 6.5.016N 1.07.3 6.5.017 A 1.07.3 6.5.017 B 1.07.3 6.5.017 D 1.07.3 6.5.017E 1.07.3 6.5.017 F 1.07.3 6.5.0170 1.07.3 6.5.017 H 1.07.3 6.5.0171 1.07.3 6.5.017J 1.07.3 6.5,018 A
~ 1.07.3 6.5.0191 1.07.3 6.5.020 1.07.3 6.5.026 1.07.3 6.5.031 A 1.07.3 6.5.03 i B 1.07.3 6.5.031 C 1.07.3 6.5.031 D 1.07,3 6.5.031E 1.07.3 Page 3
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,a MPl CRDR HED'S TO IS AP TOPIC CROSS REFERENCE 6.5.031 F 1.07.3 6.5.032R 1.07.3 6.5.033 A 1.07.3 6.5.034 A 1.07.3 6.5.034 B
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6.5.034C 1.07.3 6.5.036 A 1.07.3 6.5.036B 1.07.3 6.5.036C 1.07.3 6.5.036D 1.07.3 6.5.036E 1.07.3 6.5.036F 1.07.3 6.5.0360 1.07.3 6.5.036H 1.07.3 6.5.040 1.07.3 6.5.041 1.07.3 c
6.5.0421 1.07.3 6.5.044 1.07.3 6.6.001 1.07.3 f
6.6,002 1.07.3 I
6.6,003 1.07.3 6.6,004 1.07.3 6.6.005 1.07.3 6.6.006 1.07.3 6.6,007 1.07.3 6.6,008 1.07.3 6.6.009 1.07.3 6.6.010 1.07.3
- 6.6.011' 1.07.3 l
6.6.012 1.07.3 6.6.015 1.07.3' 6.6.016 1.07.3 i
6.6,017 1.07.3 l
6.6.018 1.07.3
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6.6.019 1.07.3' i
6.6.020 1.07.3 6.6,023 1.07.3 6.6,024 1.07.3 6.6.026 1.07.3 l
6.6,027 1.07.3 6.6,029 1.07.3 6.6.030 1.07.3 I
6.6.031 1.07.3 j
6.6.034 1.07.3 L
6.8,002 1.07.3 6.8.003 1.07.3 6.8.004 1.07.3 6.8.005 1.07.3 L
6.8.007 1.07.3 i
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4, MPI CRDR HED'S TO ISAP TOPIC CROSS REFERENCE 6.8.012 1.07.3 6.9,002 A 1.07.3 6.9,002B 1.07.3 6.9.002C 1.07.3 6.9.002 D 1.07.3 6.9.003 1.07.3 6.9,005 1.07.3 1
6.9 010A 1.07.3 l
l 6.9.010B 1.07.3 ICCR-1 1.07.3 i
ICCR 14 1.07.3 ICCR 18 1.07.3 1CCR-4 1.07.3 ICCR 9 1.07.3 O 12 1.07.3 0-14 0 1.07.3 0-14 M 1.07.3 01B 1.07.3 02 1.07.3 O.21 1.07.3 O 27K 1,07.3 j
O 29D 1.07.3
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O 290 1.07.3 O 33 1.07.3 O 5B 1.07.3 l
O-5C 1.07.3 l
O 5D 1.07.3
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O 5E 1.07.3 l'
T A - 101 1,07.3 1
TA-111 1.07.3 i
f TA 23 1.07.3 4_
TA-26 1.07.3-l TA-44 1.07.3 i.
TA 46 1.07.3
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TA 49 1.07.3 l.
TA 56 1.07.3 TA-57 1.07.3 l
TA 58 1.07.3 TA 59 1.07.3 j
TA 61 1.07.3 TA-63 1.07.3 TA 64 1.07.3
'l TA 66 1.07.3 T A-7 1.07.3 TA 85 1.07.3 l:
TA-9 1.07.3 i
V-5 1.07.3' VD-1 1.07.3 4
VD 3 1.07.3 Page 5 i /
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MP1 CRDR HED'S TO ISAP TOPIC CROSS REFERD4CE VD4 1.07.3 VD 6 1.07.3 V D.7 1.07.3 VD.9 1.07.3 TA 2 1.07.3.1.07.12 0 140 1.07.3.1.07.13
- 6.5.010 A 1.07.3.1.07.13,1.07.15 6.3.024 1.07.3.1.07.4 TA 72 1.07.3.1.07.4 ANNUNCIATORS 6.3.001 1.07.4 6.3.009 A 1.07.4 6.3.012 1.07.4 6.3.019 1.07.4 0 20 1.07.4 0 22 1.07.4 0 23 1.07.4 0 24 1.07.4 T A 10 1.07.4 T A.91 1.07.4 6.3.011 1.07.4.1.07.6 CREATE COMPtTIT.R DISPLAYS 6.1.001 A 1.07.5 6.1.001 B 1.07.5 6.1.001E 1.07.5 6.5.019H 1.07.5 0 14C 1.07.5 0 3H 1.07.5 O 5A 1.07.5 TA11 1.07.5 T A-16 1.07.5 T A 21 1.07.5 T A-7 9 1.07.5' TA-8 1.07.5 TA 80 1.07.5 TA 84 1.07.5 TA 99 1.07.5 ADDITION OF NEW EQUIPMENT 6.1.011 1.07.6 6.1.012 A 1.07,6 6.6,035-1.07.6 0 10E 1.07.6 0 14B 1.07.6 0 26 1.07.6 0 29A 1.07.6 TA 108 1.07.6 T A.15 1.07.6 T A.17 1.07.6 TA 73 1.07.6 Page 6
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MP1 CRDR HED'S TO IS AP TOPIC CROSS REFERENCE TA 77 1.07.6 TA 78 1.07.6 V-1 1.07.6 V2 1.07.6 V-6 1.07.6 VD 5 1.07.6 ALL PANELS O 11B 1.07.7 NON EOP RELATED COPEROL PANEL MIMIC 6.1.012C 1.07.8 ADDITION OF VALVE OPERATORS TA-39 1.07.9 TA 40 1.07.9 T A-5 2 1.07.9 JROCEDURE MODIFICATIONS (590 SERIES) '
TA 33 1.07,10 l
T A-4 2 1.07.10 REACTOR MODE SWTTCH REPLACEMENT O 28A 1.07.11 FEEDWATER AND RX VESSEL LEVEL IND.
6.5.005C 1.07.12 6.5.023 1.07.12 ICCR 2 1.07.12 0-27 A 1.07.12 T A-1 1.07.12 0 14P 1.07.12.1.07.16 j.
UNUSED COMPONENTS 6,4.002 1.07.13 0-25 A 1.07.13 i
0 25B 1.07.13 0 25C 1.07.13 0 25D 1.07.13 0 25F 1.07.13 l
O 25 0 1.07.13 O 25H 1.07.13 0-"'
1.07.13 V-3 1.07.13 V-4 1.07.13 1
u SECONDARY CTMT DP INDICATION ICCR 10 1.07.14 l
T A-71 1.07.14 MULT1-POINT RECORDER REPLACEMENT 6.5.035 A 1.07.15 6.5.035 B 1.07.15 6.5.035C 1.07.15 6.5.035E 1.07.15 6.5.035F l.07.15 6.5.0350
' 07.15 6.5.035 H 1.07.15 Page 7
MP1 CRDR llED'S TO ISAP topic CROSS REFERENCE 6.5.0351 6.5.037C 1.07.15 6.5.04 2 C 1.07.15 1.07.15 6.5.042D 1.07.15 6.5.04 2 E 6.5.04 3 F l.07.15 6.5.04311 1.07.15 6.5.0431 1.07.15 O-31 1.07.15
__!j)7.15 PANEL LABELLINO. ROD DISPLAY AND CONTROL SWITCH CONVENTIONS 6.4.004 6.4.013 1.07.16 0- 14 L 1.07.16
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0-29E 1.07.16 1.07.16 TA-3 TA 47 1.07.16 1.07.16 T A-5 1.07.16
_ MODIFICATION OF EXISTING CONTROLS 6.4.003 A 1.07.I7 6.4.003 B T A-98 1.07,17 1.07.17 APR 120 SEC. TIMER BYPASS SWITCH T A-14 1.07.18 ADMIN CNTL ADMIN CNTL / TRAININO 6.1.005 COMPLETED ADMIN CNTL / TRA'NING _
_ 6.4.006 COMPLETED ADMIN CNTL / TRAaNING 6.4.007 COMPLETED ADMIN CNTL
_ 6.5.029 COMPLETED O-10 A TECllNICAL SPECIFICATIONS COMPLETED TECTINICAL SPECIFICATIONS ICC R-12 COMPLE'mD O-17 DRYWELL LEVEL INSTRUMENTATION CORRECTION IN PROGRESS ICCR-8
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COMPLETED TA - 19 COMPLETED FEED REG. VALVE POSITION INDICATION
__J 0C COMPLETED PROCEDURE CORRECTION PROCEDURE CORRECrlON O-6 PROCEDURE CORRECrlON T A - 105 COMPLETED PROCEDURE CORRECTION T A - 107 COMPLETED PROCEDURE CORRECrlON
_ICCR - 13 COMPLETED PROCEDURE CORRECrlON T A - 100 CORI3ECrlON IN PRMRESS PROCEDURE CORRECrlON.___
T A 10 2 __
CORRECTION IN PROGRESS PR_OCEDURE CORRECrlON T A - 13 CORRECTION IN PROGRESS PROCEDURE CORRECTION T A-18 CORRECrlON IN PROGRESS PROCEDURE CORRECrlON T A-20 CORRECrlON IN PROGRESS PROCEDURE CORRECTION TA-35 CORRECTION IN PROG _RESS o
CORRECTION IN PROGRESS TA-37 CORRECrlON IN PROGRESS Page 8
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,i MP1 CRDR HED'S TO ISAP TOPIC CROSS REFERENCE 1
6.5.0351 1.07.15 6.5.037C 1.07.15 6.5.042C 1.07.15 6.5.042D 1.07.15 6.5.04 2 E 1.07.15 6.5.04 3F 1.07.15 6.5.043H 1.07.15 6.5.0431 1.07.15 0 31 1.07.15 PANEL LABELLINO. ROD DISPLAY AND 6.4.004 1.07.16 CONTROL SWTTCH CONVENTIONS 6.4.013 1.07.16 0 14L 1.07.16 O-29E 1.07.16 TA 3 1 07.16 TA 47 1.07.16 TA 5 1.07.16 MODIFICATION OF EXISTING CONTROLS 6,4.003 A 1.07.17 6.4.003B 1.07.17 TA 98 1.07.17 APR 120 SEC. TIMER BYPASS SWITCH T A-14 1.07.18 ADMIN CNTL 6.1.005 COMPLE'mD ADMIN CNTL / TRAINING 6.4.006 COMPLETED ADMIN CNTL / TRAININO 6.4.007 COMPLETED ADMIN CNTL / TRAINING 6.5.029 COMPLE'mD ADMIN CNTL O 10A COMPLETED TECHNICAL SPECIFICATIONS ICCR-12 COMPLETED TECIINICAL SPECIFICATIONS 0 17 CORRECTION IN PROGRESS DRYWELL LEVELINSTRUMENTATION ICCR 8 COMPLETED T A-19 COMPLETED FEED REO. VALVE POSITION INDICATION 0 30C COMPLETED PROCEDURE CORRECTION 06 COMrWE
' PROCEDURE CORRECTION T A-105 COMPLETED PROCEDURE CORRECTION TA 107 COMPLETED PROCF. DURE CORRECTION ICCR 13 CORRECTION IN PROGRESS PROCEDURE CORRECTION TA 100 CC RRECTION IN PROGRESS PROCEDURE CORRECTION T A-102 CO1RECTIONIN PROGRESS PROCEDURE CORRECTION T A-13 col'.RECTION IN PROGRESS PROCEDURE CORRECTION T A 18 CORRECTION IN PROGRESS PROCEDURE CORRECTION TA-20 CORi'ECTION IN PROGRESS PROCEDURE CORRECTION TA-35 CORRSCTIONIN PROGRFSS PROCEDURE CORRECTION TA 37 CORRECTION IN PROGRESS I
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MP1 CRDR llED'S TO ISAP TOPIC CROSS REFERENCE l
~l PROCEDURE CORRFfrlON TA 6 CORRECTION IN PROGRESS PROCEDURE CORRECrlON TA 70
- CORRECrlON IN PROGRESS PROCEDURE CORRECTION TA 74 CORRECrlON IN PROGRESS PROCEDURE CORRFfflON TA 75 CORRECrlON IN PROGRESS PROCEDURE CORRECrlON TA 76 CORRECTION IN PROGRESS PROCEDURE CORRECTION TA 87 CORRECrlON IN PROGRESS PROCEDURE CORRECrlON TA 93 CORRECTION IN PROGRESS j
PROCEDURE CORRFfflON TA 97 CORRECTION IN PROGRESS TRAINING TA 94 -
COMPLETED TRAINING O 14P TRAINING TRAINING -
0 27F TRAINING TRAINING O 27J TRAININO TRAINING O 29C TRAINING l
DRYWELL COOLER MODIFICATION TA-54 CORRECrlON IN PROGRESS PA#83-017 l
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CONDmON OF DRAWINGS O 16 A COMPLETION IN 1991 CONDmON OF DRAWINGS O 16B COMPLFTION IN 1991 CONDmON OF DRAWINGS O 16C COMPLET10N IN 1991 CONDmON OF DRAWINGS O 16D COMPLETTON IN 1991 COMMUNICATIONS 6.2.006 COMPLETED COMMUNICATIONS 6.2.005 COMPLETION IN 1995 COMMUNICATIONS O-7 F COMPLETION IN 1995 DRYWELL COOLER PROJECT O 19B CORRECTION IN PROGRESS i
MAINTENANCE O-28B MAINTENANCE MAINTENANCE O 30A MAINTFRANCE MAINTENANCE O 30B MAINTENANCE l
MAINTENANCE O 32E MAINTENANCE
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Docket No. 50-245 B13560 t
Reconciliation of HEDs Between CRDR Sumary Report and ISAP Report
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B13560/Page 1 Reconciliation of HEDs Between CRDR Summary Report and the Revised ISAP Report (Attachment 2)
In order to reconcile disparities between the HED totals in the Summary. Report and those presented in Attachment 2, the original HEDs were recounted.
The' following is the result of this recount:
Summary Report Recount Total Number of HEDs 686 692 Duplicate HEDs 54 56 i
Non-HEDs 38 61 Nonsignificant HEDs 52 58 Justifiable HEDs 104 123 Recommended for Correction' 401 347 (In ISAP) 47 (non-ISAP)'
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These errors were due to:
1 1)
Individual HEDs appearing multiple times on Figure 14 to the Summary Report.
Utilizing the line numbers for counting HEDs resulted in erroneous totals.
2)
Incorrect counting of non-HEDs on Figure 14 to the Summary Report.
Therfore, the ISAP total of 347 HEDs is correct and all others have been accounted for.
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Docket No. 50-245-J B13560 i
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CRDR Characteristic Review l
Methodology Description 1
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June 1990 I.
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Title:
Review of Millstone Point Unit No.1 Draft Emergency Operating Procedures Relative to the BWR Owner's Group Emergency Procedures Guidelines to -
Define and Compare Plant Specific and GenericTask Element Characteristics.
1.0 Purpose This review was performed to define the task element characteristics of the Millstone Point Unit No.1 (MP-1) Emergency Operating Procedures (EOPs), Rev.
O and the BWR Owner's Group (BWROG) Emergency Procedures Guidelines =
(EPGs), Rev. 4.
Further, this review was performed to tabulate the subject characteristics for comparison / verification and to provide conclusions / recommendations relative to the compared characteristics.
2.0 Scooe This characteristics review applies specifically to the following MP-1 EOPs, Rev.
0:
EOP 570 RPV Control EOP 575 Failure to Scram EOP 580 Primary Containment Control EOP 585 Secondary Containment Control and specifically to the following BWROG EPGs, Rev. 4:
Operator Precautions RPV Control Guideline Primary Containment Control Guideline Secondary Containment Control Guideline Radioa.tivity Release Control Guideline Cont!ngency #1 Alternate Level Control Ccatingency #2 Emergency RPV Depressurization Contingency #3 Steam Cooling Contingency #4 RPV Flooding Contingency #5 Level / Power Control Contingency #6 Primary Containment Flooding The task elements of the above listed EOPs have been reviewed and the plant specific q'uantitative characteristics of these task elements have been defined, as
-tabulated in the Required Instrumentation / Control Characteristics justification Tables, Section 7.0 (Attachments) of this document.
The task elements of the above listed BWROG EPGs have also been reviewed and the generic quantitative characteristics of these task elements have been defined. The generic characteristics have been correlated to and tabulated with Page 1 of 44
a j.e the plant specific characteristics of EOP task elements evaluated as derived from the subject EPG task elements.
Defined quantitative characteristics of EOP (EPG) task elements which have been determined by evaluation to have no counterpart EPG (EOP) task element have been tabulated in Section 7.0 and conclusions / recommendations have been made relative to these uncorrelated task elements.
Task element characteristics tabulations have been grouped in Section 7.0 according to system relationship and sub grouped according to instrumentation / control type. These groupings were subjectively based upon MP-1 system relationships and/or common industry standards and practices.
Tabulation groups have been numbered from 1 to 60, as required to correspond to MP-1 System Description tab numbers, or with numbers greater than 60 for 1) systems not related to MP-1 and 2) components at MP-1 not specifically related to a single system (e.g., floor drains).
Tabulation sub groups have been arbitrarily ordered and sequentially.
numbered starting at 1.
Most Limiting Characteristics (MLC) tabulations have been derived from the composite characteristics of each sub-group and tabulated to define the worst-case /most limiting characteristics for the associated instrumentation / control features (e.g., largest range required, smallest resolution required, etc.). These MLC tabulations have been given the same numerical designations as the associated sub-grouped tables, with the exception that the numerical designations of the MLC tabulations are suffixed "(MLC)". MLC tabulations have not been independently. developed for sub-grouped characteristic tabulations that present one set of defined characteristics. These one-input tabulations implicitly define their own MLC.
Plant specific characteristic accuracies and response times have been defined (as
' appropriate) in the MLC tabulations p_r one-input tabulations only, as these characteristics are not explicitly presented in the EOP set, but rather are implicitly derived /obtained. Generic characteristic accuracies and response times have not been defined, as these characteristics are not presented by the EPG set and there'is no practical purpose for their derivation.
Verification of task element characteristics is sufficient if performed for the MLC or one-input tables only. Verification of all specific task element characteristics may be used as a backup method or for verification of specific parameters / characteristics.
. Specific task element characteristics notes and review summaries have been appended to the sub-grouped characteristics tabulations to provide sufficient Page 2 of 44
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u information for verification and subsequent evaluation of defined characteristics (as required).
n Review summaries appended to the sub-grouped tabulations have been replicated in Section 5.0 (Conclusion / Recommendations) of this document, as required, for verification / evaluation of the compared generic and plant specific l
characteristics.
General Notes which apply to the entire set of tabulations have been placed as leader pages to Section 7.0.
3.0 References 3.1-BWR Owner's Group, Emergency Procedure Guidelines, Revision 4.
Prepared for the BWR Owner's Group by the Emergency Procedures Committee, General Electric Company and Operations Engineering, Inc.
NEDO-31331, Class 1, March 1987.
. 3.2 Millstone Unit 1, Emergency Operating Procedures, Rev. 0.
3.3 Technical Basis for the Millstone Nuclear Power Station Emergency
- Operating Procedures, OEI Document 8602-7, Draft, July 22,1988.
3.4 Millstone' Nuclear Power Station Emergency Procedures Guidelines Deviation / Justification Report, OEI Document 8602-2, Revision 1, May 6, 1988.
3.5 USNRC Regulatory Guide 1.97, Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident, Revision 2, December 1980.
l 3.6 ONP 502, Unit ~ Emergency Plant Shutdown, Revision 4.
3.7 Technical Specifications, Millstone Nuclear Power Station, Unit No.1, Docket No. 50-245, Appendix A to License No. DPR-21, Original through Amendment No. 22,8/22/88.
1 3.8 NUREG 0585, TMI-2 Lessons Learned Task Force Final Report, October 1979.
3.9 NUREG-0659, Staff Supplement to the Draft Report on Human
. Engineering Guide to Control Room Evaluation, March 1981.
3.10 NUREG-0700, Guidelines for Control Room Design Reviews, September 1981.
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-3.11 NUREG 0737, Supplement No.1, Clarification of TMI Action Plan Requirements, January 1983.
3.12 NUREG-0801, Evaluation Criteria for Detailed Contr61 Room Design Review, October 1981.
3.13 NUREG 0835, Human Factors Acceptance Criteria for the Safety Parameter Display System, October 1981.
3,14 NUREG-0899, Guidelines for the Preparation of Emergency Operating Proceduro, August 1982.
3.15 TX-1302, Control Rod Drive System, Rev.1.
3.16 TX-1301 A, Reactor Recirculation System, Rev,2.
3.17 TX-1301B, Reactor Recirculation Speed Control System, Rev.1.
3.18 TX-1307, Isolation Condenser System, Rev.1.
3.19 TX 1305, Shutdown Cooling System, Rev.1.
3.20 TX-1306, Reactor Vessel Head Cooling System, Rev.1.
3.21 MNPS Unit 1 System Description, Reactor Water Cleanup System, Rev. O.
3.22 ~ TX-1336, Core Spray System, Rev.1.
3'.23 TX-1335, Low Pressure Coolant injection System (LPCI), Rev.1.
3.24 TX-1334, Feedwater Coolant injection System, Rev.1.
3.25 TX-1337, Automatic Pressure Relief System, Rev.1.
3.26 TX-1304, Standby Liquid Control, Rev.1.
3.27 MNPS Unit 1 System Description, Neutron Monitoring System, Rev. O.
3.28 TX-1300B, Reactor Vessel Instrumentation System, Rev.1.
3.29 TX-1406A, Process Radiation Monitoring System, Rev.1.
3.30 TX-1311 A, Primary Containment System, Rev.1.
3.31 TX-1321, Service Water System, Rev.1.
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3.32 TX-1322, Emergency Service Water, Rev.1.
3.33 TX-1341,4160 VAC Distribution System, Rev.1.
l 3.34. MNPS Unit 1 System Description,480 Volt Electrical System, Rev. O.
3.35 MNPS Unit 1 System Description,125 Volt DC System, Rev. O.
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L 3.36 MNPS Unit 1 System Description,24 Volt DC System, Rev. 0.
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3.37 MNPS Unit 1 System Description, Vital and instrument AC Electrical l
Systems, Rev. O.
3.38 TX-1338, Diesel Generator, Rev.1.
3.39 - TX-1339, Gas Turbine Generator (GTG), Rev.1.
I 3.40 TX-1315, Condensate System lRev.1.
A 3.41 -TX 1331, Plant Heating and Condensate Recovery System, Rev.1.
3.42 TX-1316, Feedwater System, Rev.1.
j 3.43 TX-1329, Standby Gas Treatment System, Rev.1.
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3.44 MNPS. Unit 1 System Description, Reactor Building Heating, Ventilation y
and Air Conditioning System, Rev. 0.
3.45 MNPS Unit 1 System Description, Control Room Heating, Ventilation and -
~ Air Conditioning System, Rev 0.
3.46 TX-1407A, Area Radiation Monitoring System, Rev.1.
3.47 TX-1302A, Reactor Manual Control System, Rev.1.
3.48 TX-1317, Main Steam System, Rev.1.
-3.49 TX-1409A, Anticipated Transient Without Scram System, Rev.1.
3.50 LP-1300C, Reactor Fuel Text, Rev.1.
3.51 MNPS Unit 1 System Description, integrated Computer System, Rev. O.
3.52 MNPS Unit 1 System Description, Drywell Compressor System, Rev. O.
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'i 3.53 Millstone Unit 1 System Description, Fire Protection System, Rev. O.
3.54 MNPS Unit.1 System Description, Primary Containment Atmosphere Monitoring System, Rev. 0, 3.55 TX 1340,24KV Electrical System, Rev.1.
3.56-MNPS Unit 1 System Description, Post Accident Sampling, Rev. 0.
3.57 TX 1300, Reactor Vessel Construction Text, Rev.1.
1 3.58 MNPS Unit 1 P&lD, Reactor Building Closed Cooling Water,25202-26006, Sheets 1 through 4.
L 3.59 MNPS Unit 1 P&lD, Fuel Pool Cooling System, 25202-26007, Sheets 1-t through 5.
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3.60 MNPS Unit 1 P8lD, Core Spray, Low Pressure Coolant-Injection and Emergency Service Water,25202-26008, Sheets 1 through 7.
3.61~ MNPS Unit 1 P&lD, Atmospheric Control System, 25202 26009, Sheets 1 through 6.
l 3.62 MNPS Unit 1 P&lD, Main Steam System,25202 26012, Sheets 1 through 8.
3.63 MNPS Unit 1 P&lD, Condensate and Feedwater, 25202-26013, Sheets 1 h
' through 12.
1 3.64 MNPS Unit 1 P&lD, Service Water and Circulating Water System,.25202-26015, Sheets 1,3 & 7.
.3.65 MNPS Unit 1 P&lD, Station and Instrument Air Systems, 25202-26016, Sheets 1 & 15.
3.66 MNPS Unit 1 P&lD, Turbine Building Closed Cooling Water,25202-26017, Sheets 1 & 2.
- 3.67 MNPS Unit 1 P&lD, Domestic Make up and Demineralized Water Systems, 25202 26018, Sheets 1 & 3.
3.68 ' Proto Power Evaluation, Review of Millstone Point Unit No.1 Draft Emergency Operating Procedures Relative to the BWR Owner's Group L
Emergency Procedures Guidelines to identify Task Discrepancies, File 7711518,10/13/88.
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Discussion The characteristics tabulations of Section 7.0 (Attachments) have been defined for use in verification of MP-1 physical plant instrumentation / control characteristics. The comparative tabulation of Generic, Plant Specific and Verified characteristics allows review of the subject characteristics to ensure that the EOPs delineate instrumentation / control as intended in the EPGs and that the instrumentation / control tasks of the EOPs may be performed in the actual physical plant of MP-1.
i The generic and plant specific characteristics of Section 7.0 were tabulated by personnel with Engineering Staff and/or Senior License experience at licensed boiling water reactor plants exclusive of MP-1.
The tabulations of Section 7.0 were generated by performance of a review that was intentionally " blind" to the MP 1 plant specific control board inventory and specific instrurnent calibration data. This blind review methodology was implemented to enhance unbiased definition of EOP/EPG characteristics. Plant
-specific Technical Specifications, Training Texts, System Descriptions and P&lDs were utilized during the definition of characteristics and in the development of summaries, conclusions and recommendations. These documents were consulted to provide an understanding of MP-1 plant technical requirements in
- relationship to generic technical requirements.
The defined characteristics of Section 7.0 were developed for quantitative and specific-action task elements. General operator determinations (e.g., "a condition which requires a reactor scram", "the reactor will remain shutdown under all conditions without boron") have not been defined for instrumentation / control characteristics.- These general operator determinations are dependent upon operator training and experience in conjunction with specific instrumentation / control otherwise defined in Section 7.0. These general determinations do not lend themselves to tabulation.
- However, recommendations / conclusions relevant to these general determinations have been made in Section 5.0, as pertinent.
Steps which provide internal directions in the EOPs/EPGs (e.g., "go to" overrides) have not been defined for instrumentation / control characteristics in Section 7.0.
Nor have non-quantitative " Purpose" statements. These types of steps do not lend themselves to tabulation. However, recommendations / conclusions relevant to these steps have been made in Section 5.0, as pertinent.
This review has been performed as Scope item B of a two part review process.
Scope item A," Review of Millstone Point Unit No.1 Draft Emergency Operating Procedures Relative to the BWR Owner's Group Emergency Procedures Guidelines to Identify Task Discrepancies" was issued as a draft on October 13,
'1988. This Scope item B document effectively supersedes the Scope item A 1
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- e; document by drawing conclusions / recommendations relative to all Scope itern A concerns.
See Section 7.0 for detailed characteristics tabulations and Section 5.0 for recommendations / conclusions.
~ 5.0.
Conclusions / Recommendations Conclusions have been made relative to the plant specific MP 1 EOPs where it has been determined that the EOP tasks and/or their defined characteristics meet the generic intent of the BWROG EPGs. The references of Section 3.0 have' been used as standards by which many of these conclusions were reached, s
Recommendations have been made relative to the plant specific MP-1 EOPs where it has been determined that quantitative and/or textual differences from the BWROGs EPGs exist and where these differences cannot be justified based upon plant specific documentation such as the MP-1 Technical Specifications and Training Texts.
Recommendations have also been made relative to the plant specific MP-1 EOPs -
where it has been determined that:
1)
Further detail or elaboration may be required to establish accurate plant specific interpretations of generic steps, and 2)
Errata is suspected to have been generated during the development of the plant specific MP-1 EOPs.
L Conclusions / recommendations have been listed below as follows:
e Section 5.1 lists conclusions /n mendations relative to specific characteristics tabulated in Section 7.0.
e Section 5.2 lists conclusions / recommendations relative to general operator determinations and general EOP to EPG task discrepancies, including steps that provide internal direction
- only, e
Section 5.3 lists conclusions / recommendations relative to errata noted during the review of the EOP text.
5.1 Conclusions / Recommendations Relative to Characteristics Tabulations, Section 7.0.
Page 8 of 44 x
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Docket No. 50-245 B13560 i
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4 Contractor Personnel Resumes 1
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l-L June 1990 t
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E. ROBERT DEWEESE Mr. DeWeese is a Staff Engineer in the Proto-Power Corporation I&C/ Electrical Systems Group. He is responsible for power plant systems technical review, systems engineering, systems design, systems testing and startup program coordination.
Professional Experience Mr. DeWeese has most recently developed discipline specific Technical Standards to establish the physical separation and electrical isolation rec uirements for the -
ind ndence of redundant equipment and components at Public Service Electric &.
Gas PSE&G) Salem Units 1 & 2.
Mr. DeWeese has also recently provided an enoincering evaluation of the indication.
requirements for a steam generator tube ;optUre relative to industry and regulatory criteria for PSE&G Salem Units 1 & 2.
Mr. DeWeese's previous assignments at P,oto Power have included:
e the evaluation of the design bases and licensing commitments relative to physical separation and electricalisolation for safety related circuits and Reg.
Guide 1.97 instrumentation at PSE&G Salem Units 1 & 2.
e technical services to PSE&G Salem Units 1 & 2 during a regulatory audits of Station compliance to Reg. Guide 1.97. These services included research and documentation to support audit responses and licensing correspondence, e
an evaluation and disposition of material discrepancies relative to the Managed Maintenance information Systeu (MMIS) and Configuration-Baseline Data (CBD) for PSE&G Salem Units 1 & 2.
e a Control Room Design Review (CRDR) for Northeast Utilities Millstone Point Unit 1. His CRDR responsibilities included the identification of operator task discrepancies and the characterization of instrumentation / control requirements relative to the MP-1 Emergency Operating Procedures, e
the design and installation of 10CFR50 Appendix R upgrade modifications to the UHF Communications System, RHR Pump Rooms Ventilation System and Diesel Generators CO Fire Suppression System for PSE&G Salem Units 1 & 2.
2 e
the design and installation of a seismic qualification upgrade modification to provide emergency Diesel Generator Ventilation System controls at the Control Room boards for PSE&G Salem Units 1 & 2, with consideration for Separations and Human Factors requirements.
e the design and installation of non-intrusive service water flow instrumentation for PSE&G Salem Units 1 & 2 to meet the requirements of ASME XI, Subsection IWP, with consideration for corrosive environment qualification, Seismic II/I qualification and Human Factors requirements, e
a review and as:essment of identified electrical system-wiring potential deficiencies for safety to non safety system interfaces, safety system channel independence and circuit configurations relative to 10CFR50 Appendix R requirements for PSE&G Salem Units 1 & 2.
06/90-G
L19)ERT DEWEESE(Continued)
Previc,us Professional Experience Prior to joining Proto Power, Mr. DeWoese was an Engineer with the Advisory 4
Operations Division (AOD) of Stone & Webster Engineering Corp (SWEC). Dunng his assignment at Philadelphia Electric Co. Umerick Generatmg Station, Mr. DeWeese per*ormed a comprehensive technical and Human Factors revision of procedures for the operation of control drive hydraulics, reactor water cleanup and radwaste collection, among others.
His RWCU revisions incorporated the latest vendor experience and industry lessons learned into station procedures. Mr. DeWeese also authored station procedures as required to supplement existing procedures and to incorpmate design changes.
In previous SWEC assignments, Mr. DeWeese:
served as a member of the Niagara Mohawk Power Corp. Nine Mile e
Point Unit 2 Technical Su sport Group. He participated in the group's complete review o all Unit 2 operation and maintenance procedures. Additionally, he participated in the review for Unit applicability of all GE SIls, all IE notices and other selected industry generated documents.
o served as a Control Room Startu a Coordinator at Northeast Utilities Millstone Point Unit 3, responsib e as a Management Representative with the Operations Department during the Unit 3 construction and startup. His principle duties included establishing priorities, resolving program conflicts and determining system operability per technica specifications.
Y served as the AOD Low Pressure Safety injection System Engineef e
i and as the AOD Technical Specifications Coordinator for the Duquesne Light Beaver Valley Power Station Unit 2. As Tech. Spec.
Coordinator, Mr. DeWeese was responsible for identifying required surveillance per the Unit 2 Technical Specification. Adcationally, Mr.
DeWeese : served as a Technical Reviewer / Writer and authored i
generic calibration specificsurveillance. procedures for use in the d*velopment of
+
L Prior to joining SWEC, Mr. DeWeese served as a U.S. Navy Reactor Operator aboard l
the first TRIDENT submarine, the USS Ohio, during all phases o" construction l
turnover and operational patrol cycles. In addition to senior watch station and l
maintenance duties he maintained all Reactor Contrcls Division Certified Data and
)
was twice commen,ded, by his command and his squadron, for his technical accomplishments.
Professional Affiliation Certified Test Engineer per NRC Regulatory Guide 1,58 Education l
Associates, Jackson Community College - 1983 Process Control Technology Course, Foxboro - 1989 BSEE Candidate, University of New Haven 06/90 G
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JJTMLN R. DORT Mr. Dort is a Licensed Nuclear Power Plant Operations (BWR SRO) consultant to Proto Power Corporation. He has over twelve years combined exprrience in the operations of both nuclear utility industry and naval nuclear program reactors. This experience has included power plant maintenance programs, procedural review responsibilities and technical training performance.
Professional Experience Mr. Dort is currently assigned as a Station Shift Supervisor at Niagara Mohawk Power Corporation's Nine Mile Point Unit #2 (NMP#2) Nuclear Power Station (GE BWR).
He has previously served as the Chairman - Technical Review Committee for the Nuclear Regulatory Com aliance Group as well as a Senior Instructor in the Training Department at NMP#2. Wr. Dort is an SRO licensee at NMP#2. Mr. Dort he been at NMPd2 since February 1986.
Prior to joining Niagara Mohawk, Mr. Dort served as a U.S. Naval Reactor Operator from October 1977 until February 1986. His final position with the U.S. Navy was as a Supervisor of the Engineering Watch Section in Reactor Operations. Other positions included Supervisor Reactor Controls Division; Supervisor Reactor Controls Work Center; Administrative Coordinator - Engineering Department, and; Technical Training Instructor-Staff 58G Nuclear Prototype.
Educatiqn.
Masters of Business Administration: 90% complete, Organization and Management Major, Syracuse University. Grad Date: December 1990.
Bachelor of Science: Management Human Resources; New School for Soc.ial Research, NY, New York.
Nuclear Industry:
$1mulator instructor Senior Reactor Operator TechnicalWriting Kepner Tregoe Process for Communication Skills Problem Solving and ObserverTraining Decision Making Training System Development U.S. Naval Service:
Leadership, Management Education and Training Naval Nuclear Power School ElectronicsTechnician School Electronics Maintenance / Quality Assurance 6/90 1
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