ML20078S799
| ML20078S799 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 12/20/1994 |
| From: | Mcmeekin T DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-89-10, NUDOCS 9412290220 | |
| Download: ML20078S799 (24) | |
Text
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ll l Dukelbwer Company T. C McVam ,
McGuire NudearGenemtion Depawnent \ke hesident IZiCOHagen feny Road (MG0lbP) (M)8754800 Huntenvelle, NC280788985 (M)8754809 Fax UUKEPOWER December 20, 1994 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
McGuire Nuclear Station Docket Nos: 50-369 and 370 Generic Letter 89-10 Proposed Schedule Extent. ion
Dear Sir:
As stated in Duke Power Company letter of October 27,1994, attached is information required by Generic Lette:. 89-10, Supplement 6 to support proposed schedule extension of the McGuire GL 89-10 program. The proposed completion date for the Group 1 valves is extended to July 19, 1995 and the proposed completion schedule for the Group 2 valves has been accelerated from December 29, 1998 to July 19,1995.
The attached materials provide appropriate details required by GL 89-10, Supplement 6 including the proposed schedule adjustments, background information, current program status, schedule extension justification, and technical information for ,
each unverified valve. l Should you require further information, please contact James E.
Snyder at (704) 875-4447. l Very truly yours,
. C. McMeekin l
l 9412290220 941220 l PDR ADOCK 05000369 0g.
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US Nuclear Regulatory Commission 12-20-94 Page 2/2 cc: Mr. S.D. Ebneter Administrator, Region II U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite'2900 Atlanta, Ga. 30323 Mr. Victor Nerses U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. Robert E. Martin U.S. Nuclear Regulatory Commission Office'of Nuclear Reactor RegulatAon l Washington, D.C. 20555 Mr. G.F. Maxwell NRC Resident Inspector McGuire Nuclear Station i l
Dayne Brown, Chief Division of Radiation Protection P. O. Box 27687 Raleigh, N. C. 27611-7687 l \
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. 1 L U. S. Nuclear Regulatory Commission i December 20, 1994 1
T. C. McMeekin, being duly sworn, states that he is Vice President i of Duke Power Company, McGuire Nuclear Site; that he is authorized on the part of said Company to - sign and file with the Nuclear Regulatory Commission this revision to the McGuire Nuclear Station i License numbers NPF-9 and NPF-17, and that all the statements and
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matters set forth therein are true and correct to the best of his j knowledge. l i
s T. C. McMeekin ,
McGuire Nuclear Station Subscribed and sworn to before me this 2 dayofih/Y f.
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No[ary lic My Commission Expires:
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McGuire Nuclear Station NRC Generic Letter 89-10 Request for Schedule Adjustment Proposed Schedule Adjustments In accordance with the guidelines established by Generic Letter 89-10, Supplement 6, McGuire is proposing two adjustments to the present schedule:
. For Group 1 and low-margin Group 2 MOVs, it is requested that the scheduled l completion date for certain Stage 2 activities be extended to July 19,1995.
. . For the balance of Group 2 MOVs, it is proposed that the scheduled completion date l for all Stage 1 and Stage 2 activities be adiusted to July 19,1995. This constitutes an improvement of 3.5 years over the previous schedule.
Figure 1 - MNS GL 89-10 Schedule - Proposed Revision per Supplement 6 l
Group 1 l :
High Risk i
All stage 1
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-* a July 19,1995 l GL 89-10 Stage 2 MOVs Not High
- l Group 2 l :
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Background
NRC justification for issuing Generic Letter 89-10 was increased theoretical core melt frequency resulting from higher-than-originally-expected MOV failure rates. I NUREG/CR-5140,"Value-Impact Analysis for Extension of NRC Bulletin 85-03 to Cover All Safety-Related MOVs," documents thisjustification based on reported Bulletin 85-03 failure rates, cost estimates from MOVATS Incorporated, a "best estimate" MOV population of 100 per unit (Iow of 80, high of 130), conducting full design-basis differential pressure testing on 10 percent of the applicable population, and replacing 1 percent due to "uncorrectable deficiencies."
Very early in the program. Duke Power Company (Duke) recognized that their unit average MOV population for McGuire Nuclear Station (MNS) far exceeded the estimated "high" of 130. In the Duke initial response to GL 89-10 (dated December 28,1989), a risk-based schedule was specified based on Phase 1 (high risk) and Phase 2 (not high risk)
MOVs. Later, this terminology was changed to Group 1 (high risk) and Group 2 (not high risk) MOVs. Group 1 and Group 2 are defined below:
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l e Group 1 MOVs are those that are active and are important to core melt scenarios. They are the most safety significant MOVs and are given the highest priority.
- Group 2 MOVs consist of the balance of 89-10 MOVs not in Group 1. They are less safety significant than Group 1 MOVs.
j Completion schedule for Group 1 was specified as 5 years from December 28,1989 (December 28,1994) or 3 refueling outages after June 28,1990, whichever is longer. For Group 2, this schedule was specified as 8 years from December 28,1989 (December 28, 1997) or 6 refueling outages after June 28,1990, whichever is longer.
Figure 2 - MNS GL 89-10 Initial Schedule l
High Risk iGroup 1 l i December 28,1994 l l All
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GL 89-10 1 MOVs Not High i Group 2l i December 28,1997 l l
On February 5,1991, Duke personnel met with the NRC staff to discuss various aspects of the GL 89-10 program. As a result of this meeting, the NRC staff requested that Duke submit a detailed schedule to provide information on the completion of Stage 2. This request was documented in a NRC letter dated March 18,1991 In a letter dated October l 31,1991, Duke provided the following definitions for Stage 1 and Stage 2:
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. Stage 1 - initial base-line diagnostic testing to verify valve function-ability based on "best available" information.
l e Stage 2 - performing flow and differential pressure testing on a population of MOVs in combination with engineering analyses to validate the initial Stage I set-up methodology.
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In addition, this letter also specified the following schedule:
- Stage 1 and Stage 2 programs for Group 1 and marginal Group 2 MOVs will be completed by December 28,1994 or within 3 refueling outages starting after June
! 28,1990, whichever is longer.
. Stage 1 and Stage 2 programs for the remainine Group 2 MOVs will be completed by December 28,1998 or within 6 refueling outages starting after June
! 28,1990, whichever is longer.
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l l Figure 3 - MNS GL 89-10 Schedule - October,1991 Revision High Risk tage 2 All Margin GL 89-10 Not High MOVs Risk Stage 1 & Stage 2 o
7 Group 2,i i, December 28,1998 l l
This schedule is documented on page 13 of the Oconee Phase 1 inspection report dated August 8,1991. In regards to the schedule, this report states:
This is a concern, but due to the licensee's efforts to test the highest priority MOVs first, the large number of MOVs that require testing, and the small population of MOVs that will be tested beyond the schedule recommendations, the licensee's schedule for completion is acceptable. The licensee should continue to evaluate its schedule during the testing program to ensure that any necessary revisions are made.
- McGuire Phase 1 inspection report dated May 12,1992 also document this completion schedule.
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l Current Program Status i Figure 4 provides the McGuire Nuclear Station (MNS) GL 89-10 program completion j status for refueling outages beginning on or before December 28,1994 and ending January 22,1995:
Figure 5 shows the level of completion of DP testing projected by refueling outages beginning on or before December 28,1994 and ending January 22,1995:
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! FIGU R E 4 450 G 417 MNS COMP LE T ION S T AT US ACO h350
- 2 300 287 cc
$250 236 236
!200 197 181
! laj 146 150 4 0 i i i i i i i i i i a
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g&g$S$S s $ms8 S8s 08 8ss Hg M $s*lS$S so 8sam sagssa o m I
j F IGU R E 5 MNS - DP TE STING COMPLE T E D - 50% OF
- g. M 250-
$200- 166 T G AL (NCN- CAPABLE G DPTESTS j KERG EST) BEINGDP CCWLET E ON-j T EST ED @ CR SIT U)BY E ND l > 50% 2E007 I
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Mechanical Improvements Achieved or In Progress McGuire has performed a number of modifications to improve the performance of MOVs. The table below shows the approximate number of modification activities performed. Attachment 2 provides a detailed summary of the modifications performed at each of the three sites. Note that there are no outstanding corrective actions based on GL 89-10 program to date.
NUMBER OF V 4 ijp
[ MODIFICATION
] MODIFICATIONS y INCLUDED IN A M TYPE $ PERFORMED $ ATTACHMENT 2 s
,p $ $ @
REPLACE OPERATOR ONLY 24 YES g;c A 5 4 REPLACE SPRING PACK ONLY d 8 .
YES h l6 h j h
[ TORQUE SWITCH WIRING SYPASSES y 293 y NO 4%
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e (completed for oil gate and butterfly voNes) Q '5
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- Modifications are only counted once, by the rnost significant activity.
TechnicalImprovements in Progress Duke has initiated several test programs which will be completed at approximately the ;
same time as the original schedule completion date for the Group 1 valves. Duke is also participating in industry-sponsored programs intended to improve the understanding of MOVs. These programs have been adjusted and modified in response to emerging regulatory and industry issues and, in their final form, are expected to be useful for the completion of Stage 2 of the Duke GL 8910 program. These activities include:
KEROTSST FLOW LOOP TESTING (WATER) 23 Kerotest globe valves representative of the installed population at the Duke plants i have been tested with water under controlled conditions at differential pressures ranging from 0 psid to over 2,500 psid and flow velocities in excess of 200 feet per second. The results of these tests are applicable to approximately 300 MOVs in the Duke program.
KEROTEST VALVE TESTING (STEAM) 3 Kerotest globe valves representative of the installed population at the Duke plants are planned to be tested with steam under controlled conditions at differential pressures of approximately 2,500 psid and flow velocities up to blowdown conditions. These tests are applicable to Kerotest globe valves in steam service.
EPRI MOV PERFORMANCE PREDICTION PROGRAM Duke has actively supported the EPRI MOV Program and anticipates utilizing this methodology in selected cases, pending industry review and final resolution of comments.
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Program Completion Since the original schedule was established, Stage 1 and Stage 2 test activities have been implemented for both Group 1 and Group 2 valves. Emphasis, however, has been placed on the Group 1 valves in recognition of their greater safety significance.
Several techniques, singularly or in combination, will be used for Stage 2 justification of the remaining MOVs. Listed below are the techniques anticipated to be used:
- 1. FULL DP TESTING. Design basis testing of valve. This is the application of test results taken at or near design basis (accident) conditions for the specific valve in question.
- 2. PARTIAL DP TESTING. This is the application of test results taken at less than design basis (accident) conditions for the specific valve in question.
- 3. Duke in-house test data or outside Duke test data (GROUPING). This is the application of test data from other similar or identical valves that are tested at a Duke nuclear plant.
- 4. PROTOTYPE TESTING. This is the application of test results taken for a prototype valve or valves that are tested at a flow loop facility.
- 5. EPRI MOV Program (EPRI PPP) results. This is the application of EPRI flow loop and in-situ test results and/or the actual validated program methodologies.
- 6. Siemens similarity analysis (SIMILARITY). This is the application of similarity results similar to that being performed at Grand Gulf.
- 7. MARGIN ANALYSIS coupled with other technique (s) analysis. This is the process of demonstrating adequate switch set-up margin based on extremely conservative assumptions and use of test results of similar valves.
In accordance with GL 89-10 Supplement 6, Attachment I contains a detailed list of each '
valve within the scope of this extension request, along with the available sizing factor 1 (valve factor for gate and globe valves) for each MOV. The expected Stage 2 justification method is also listed for each MOV.
l Extension Justification l l
McGuire Nuclear Station believes that a schedule extension to July 19,1995 for certain Stage 2 Group 1 activities isjustified because:
- 1) The large number of MOVs in McGuire's 89-10 program (433 as compared to a high estimate of 260,130 per unit). This has resulted in a large amount of required testing and with several changes being identified in the 89-10 program (6 supplements to the G.L.), this testing is being completed in the current outage (2EOC9) which started within the 89-10 time frame. With testing just completing, some time is needed to factor that data into verification bases.
Therefore, the extension of 6 months is requested for Group 1 MOVs.
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l l 2) McGuire Group 2 MOVs will be completed well ahead of the previous schedule --
l an improvement of approximately 3.5 years.
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- 3) All McGuire GL 89-10 MOVs have design bases identified and all but 16 Group 2 MOVs have been set-up using conservative sizing factors. The best available sizing factor data have been employed in the existing setups and the functionality of MOVs is confirmed by actually performing diagnostic testing.
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l 4) These improvements are expected to exceed the potential impact of an extension to July 19,1995.
Attachments The following attachments are provided for McGuire GL 89-10 program MOVs for which Stage 2 will not be completed in refueling outages beginning before December 28, 1994 and ending January 22,1995:
Attachment Description i
1 McGuire MOVs Applicable to Schedule Extension Request 2 McGuire Modifications j 3 Table of Abbreviations l
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McGUIRE NUCLEAR STATION ATTACHMENT 1-MOVc WITHOUT STAGE 2 JUSTIFICATIONS AS OF 12-28-94 ,-
PLANNED VALVE DESIGN AVAIL. - STATIC PLANIEED STAGE STAGE 2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COIAPLETION SEQUENCE No. VALVE NO TYPE PSID GPRA GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE RAETHODS DATE 1EOC9 EPRIPPP, 1 ORN0002 36-tN. BF 22 28200 2 RC CROSSOVER SUPPLY TO RN A TRAIN. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 2 ORN0003 36-IN. BF 22 28219 2 RC CROSSOVER SUPPLY TO RN A TRAIN. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 3 ORN0004 36-IN. BF 22 28220 2 RC CROSSOVER SUPPLY TO RN B TRAIN. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRI PPP, 4 ORN0005 36-IN. BF 22 28219 2 RC CROSSOVER SUPPLY TO RN B TRAIN. NA (9/94) GROUPtNG 2nd ORT 95 STANDBY NUC SM POND SUPPLY TO RN A 1EOC9 EPRIPPP, 5 ORN0007 36-tN. BF 16 25470 1 TRAIN. NA (9/94) GROUPtNG 2nd ORT 95 STANDBY NUC S/W POND SUPPLY TO RN B 1EOC9 EPRIPPP, 6 ORN0009 36-IN. BF 16 25470 1 TRAIN. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 7 ORN0010 36-IN. BF 22 28220 1 LOW LEVEL INTAKE SUPPLY TO RN B TRAIN. NA (9/94) GROUPtNG 2nd ORT 95 1EOC9 EPRIPPP, 8 ORN0011 36-IN. BF 22 28220 1 LOW LEVEL INTAKE SUPPLY TO RN B TRAIN. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 9 ORN0012 36-IN. BF 25 28220' 1 LOW LEVEL INTAKE SUPPLY TO RN A TRAIN. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 10 ORN0013 36-IN. BF 25 28219 1 LOW LEVEL INTAKE SUPPLY TO RN A TRAIN. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 11 ORN0014 36-IN. BF 24 28219 2 RN SUPPLY TRAIN CROSSOVER. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 12 ORN0015 36-IN. BF 24 28219 2 RN SUPPLY TRAIN CROSSOVER. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 13 ORN0147 36-IN. BF 22 28220 1 RN A TRAIN DISCHARGE HEADER TO RC NA (9/94) GROUPING 2nd ORT 95 IEOC9 EPRIPPP, 14 ORN0148 36-IN. BF 29 28220 1 RN A TRAIN DISCHARGE HEADER TO RC NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 15 ORNO149 36-IN. BF 21 25500 2 RN A TRAIN SNSWP DISCHARGE. NA (9/94) GROUPtNG 2nd ORT 95 RN A TRAIN DISCHARGE HEADER 1EOC9 EPRIPPP, 16 ORN0150 36-IN. BF 19 14500 2 CROSSOVER. NA (9/94) GROUPING 2nd ORT 95 RN B TRAIN DISCHARGE HEADER 1EOC9 EPRIPPP, 17 ORN0151 36-IN. BF 22 14500 2 CROSSOVER. NA (9/94) GROUPING 2nd ORT 95 Page 1 of 12
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McGUIRE NUCLEAR STATION ATTACHMENT 1-MOVs WITHOUT STAGE 2 JUSTIFICATIONS AS OF 12-28-94 .
PLANNED VALVE DESIGN AVAIL, STATIC PLANNED STAGE STAGE 2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COMPLETION SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE METHODS DATE 1EOC9 EPRIPPP, 18 ORN0152 36-IN. BF 20 25500 1 RN B TRAIN SNSWP DISCHARGE. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 19 ORN0283 36-IN. BF 26 28220 1 RN A TRAIN DISCHARGE TO RC HEADER. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 20 ORN0284 36-IN. BF 29 28220 1 RN B TRAIN DISCHARGE TO RC HEADER. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 21 ORNO301 24-IN. BF 23 2673 2 RN SUPPLY TO RV SYSTEM. NA (9/94) GROUPING 2nd ORT 95 1EOC9 EPRIPPP, 22 ORNO302 24-IN. BF 23 2673 2 RN SUPPLY TO RV SYSTEM. NA (9/94) GROUPING 2nd ORT 95 THE NON-SAFETY-RELATED CONDENSATE EPRIPPP, 23 ICA0007 8-IN GT 117 N/A 1 SOURCE 0.5 11/8/91 GROUPING 2nd ORT 95 THE NON-SAFETY-RELATED CONDENSATE EPRIPPP, 24 1CA0009 8-IN GT 117 N/A 1 SOURCE 0.5 11/5/91 GROUPING 2nd ORT 95 FROM NON-SAFETY-RELATED CONDENSATE EPRIPPP, 25 1CA0011 8-IN GT 117 N/A 1 SOURCE 0.5 11/9/91 GROUPtNG 2nd ORT 95 EPRI PROVIDES TRAIN RELATED FLOWPATH FOR PPP MARGIN THE CA MDP A FROM SAFETY RELATED ANALYSIS, 26 1CA0015 6-IN GT 116 N/A 1 ASSURED RN SUPPLY. OPEN FUNCTION. 0.35 11/29/91' GROUPING 2nd ORT 95 EPRI PROVIDES TRAIN RELATED FLOWPATH FOR PPP MARGIN THE CA MDP B FROM SAFETY RELATED ANALYSIS, 27 1CA0018 6-IN GT 116 N/A 1 ASSURED RN SUPPLY. OPEN FUNCTION. 0.35 10/18/91 GROUPING 2nd ORT 95 PROVIDES ISOLATION FOR S/G C FROM THE EPRIPPP, 28 1CA0050 4-IN GT 2075 N/A 1 TDP IN THE EVENT OF A FAULTED S/G. 0.5 12/5/91 GROUPING 2nd ORT 95 PROVIDES ISOI.ATION FOR S/G A FROM THE EPRIPPP, 29 1CA0066 4-IN GT 2075 N/A 1 TDP IN THE EVENT OF A FAULTED S/G. 0.5 10/14/91 GROUPING 2nd ORT 95 EPRI PROVIDES TRAIN RELATED FLOWPATH FOR PPP, MARGIN CATDP FROM SAFETY RELATED ASSURED ANALYSIS, 30 1CA0086 8-IN GT 116 N/A 1 RN SUPPLY. OPEN FUNCTION. 0.35 5/31/92 GROUPING 2nd ORT 95 Page 2 of 12
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McGUIRE NUCLEAR STATION ATTACHMENT l-MOVs WITHOUT STAGE 2 JUSTIFICATIOtts -
AS OF 12-28-94 ,- ;
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PLANNED f' VALVE DESIGN AVAIL. STATIC PLANIED STAGE STAGE 2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COGAPLETION ,
SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE RAETHODS DATE :
EPRI t PROVIDES TRAIN RELATED FLOWPATH FOR PPP, MARGIN ;
CA TDP FROM SAFETY RELATED ASSURED ANALYSIS, !
31 1CA0116 8-IN GT 116 N/A 1 RN SUPPLY. OPEN FUNCTION. 0.35 5/22/92 GROUPING 2nd ORT 95 t EPRI !
I PROVIDES THE FLOWPATH FOR THE CA TO PPP. MARGIN PUMP FROM THE RC SYSTEM IN A SSS ANALYSIS, l 32 1CA0161 8-IN GT 50 N/A 1 EVENT. OPEN FUNCTION 0.35 5/21/93 GROUPING 2nd ORT 95 i EPRI f PROVIDES THE FLOWPATH FOR THE CA TO PPP. MARGIN j PUMP FROM THE RC SYSTEM IN A SSS ANALYSIS, j 33 1CA0162 8-IN GT 50 N/A 1 EVENT.OPEN FUNCTION O.35 5/2643 GROUPING 2nd ORT 95 [
SG PREHEATER BYPASS ISOLATION TO THE EPRIPPP, 34 1CF0126 6-lN GT 862 N/A 2 AUXILIARY FEEDWATER Nn771 FS. 0.5 5/3049 GROUPING 2nd ORT 95 SG PREHEATER BYPASS ISOLATION TO THE EPRIPPP, 35 1CF0127 6-IN GT 862 N/A 2 AUXILIARY FEEDWATER NOZZLES. 0.5 5/2989 GROUPING 2nd ORT 95 EG PREHEATER BYPASS ISOLATION TO THE EPRIPPP, 3 36 1CF0128 6-IN GT 862 N/A 2 AUXlLIARY FEEDWATER NOZZLES. 0.5 7/25/90 GROUPING 2nd ORT 95 SG PREHEATER BYPASS ISOLATION TO THE EPRIPPP, 37 1CF0129 6-IN GT 862 N/A 2 AUXILIARY FEEDWATER NOZZLES. 0.5 5/3049 GROUPING 2nd ORT 95 BYPASS THE FUEL LUBE OIL FILTER ON HIGH OPEN,LARGE 38 1LD0108 4-IN GT 57 N/A 2 DIFFERENTIAL PRESSURE. OPEN FUNCTION. 0.35 2/3/93 MARGIN 2nd ORT 95 -
BYPASS THE FUEL LUBE OIL FILTER ON HIGH OPEN, LARGE _j 39 1LD0113 4-IN GT 57 N/A 2 DIFFERENTIAL PRESSURE. OPEN FUNCTION 0.35 3/3/93 MARGIN 2nd ORT 95 .I EPRIPPP, 40 1NC0031 3-IN GT 2335 N/A 1 ISOLATE THE INLET TO EACH NCS PORV 0.5 5/31/93 GROUPING 2nd ORT 95 EPRIPPP, 41 INC0033 3-IN GT 2335 N/A 1 ISOLATE THE INLET TO EACH NCS PORV 0.5 5/27/93 GROUPING 2nd ORT 95
- EPRIPPP, 42 1NC0035 3-IN GT 2335 N/A 1 ISOLATE THE INLET TO EACH NCS PORV 0.5 5/28/93 CROUPING 2nd ORT 95 Page 3 of 12
McGUIRE NUCLEAR STATION ATTACHMENT 1 -
MOVa WITHOUT STAGE 2 JUSTIFICATIONS AS OF 12-28-94 .-
PLANNED VALVE DESIGN AVAIL STATIC PLANNED STAGE STAGE 2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICA110N COMPLETION SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE METh00S DATE CONTAINMENT ISOLATION FROM THE EPRIPPP, REACTOR MAKEUP WATER PUMPS AND GROUPING.
43 1NCn056 4-IN GT 159 N/A 2 HEADER TO THE PRT. 0.5 2/6/94 SIMILARITY 2nd ORT 95 ISOLATE THE NC SYSTEM FROM THE ND EPRIPPP, 44 1ND0001 14-IN GT 386 N/A 1 SYSTEM. 0.5 4/29/93 GROUPING 2nd ORT 95 ISOLATE THE NC SYSTEM FROM THE ND SYSTEM. PROVIDE CONTAINMENT ISOLATION EPRIPPP, 45 1ND0002 14-IN GT 530 N/A 1 DURING A SSS EVENT. 0.5 10/30/91 GROUPING 2nd ORT 95 PROVIDE ND PUMP SUCTION ISOLATION DURING THE RECIRCULATION PHASE OF AN EPRIPPP, 46 IND0004 14-IN GT 200 N/A 1 ECCS ACTUATION. 0.5 4/21/93 GROUPING 2nd ORT 95 PROVIDE ND PUMP SUCTION ISOLATION DURING THE RECIRCULATION PHASE OF AN EPRIPPP, 47 1ND0019 14-IN GT 200 N/A 1 ECCS ACTUATION. 0.5 4/28/93 GROUPING 2nd ORT 95 ALLOW HIGH PRESSURE SAFETY INJECTION INTO THE REACTOR COOLANT SYSTEM EPRIPPP, 48 IN10009 4-IN GT 2710 N/A 1 (FROM THE NV PUMPS). 0.5 10/16/91 GROUPING 2nd ORT 95 ALLOW HIGH PRESSURE SAFETY INJECTION INTO THE REACTOR COOLANT SYSTEM EPRIPPP, 49 IN10010 4-IN GT 2710 N/A 1 (FROM THE NV PUMPS). 0.5 10/16/91 GROUPING 2nd ORT 95 ALLOW COLD LEG ACCUMULATOR SAFETY INJECTION INTO THE REACTOR COOLANT EPRIPPP, 50 1NIOO54 10-IN GT 633 N/A 1 SYSTEM 0.5 5/4/93 GROUPING 2nd ORT 95 ALLOW COLD LEG ACCUMULATOR SAFETY INJECTION INTO THE REACTOR COOLANT EPRIPPP, 51 1N10065 10-IN GT 633 N/A 1 SYSTEM 0.5 5/20/93 GROUPING 2nd ORT 95 ALLOW COLD LEG ACCUMULATOR SAFETY INJECTION INTO THE REACTOR COOLANT EPRIPPP, 52 1N10076 10-IN GT 633 N/A 1 SYSTEM 0.5 5/19/93 GROUPING 2nd ORT 95 ALLOW COLD LEG ACCUMULATOR SAFETY INJECTION INTO THE REACTOR COOLANT EPRIPPP, 53 1N10088 10-IN GT 633 N/A 1 SYSTEM 0.5 9/2/93 GROUPING 2nd ORT 95 Page 4 of 12
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i McGUIRE NUCLEAR STATION ATTACHMENT 1 - .
MOVc WITHOUT STAGE 2 JUSTIFICATIONJ AS OF 12-28-94 .-
PLANNED VALVE DESIGN AVAIL STATIC PLANNED STAGE STAGE *2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COMPLETION SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE METHODS DATE OPEN DURING THE COLD LEG INJECTION PHASE OF ECCS OPERATION TO ALLOW GROUPING, 54 1N10100 8-IN GT 200 N/A 1 FLOW FROM THE RWST TO THE SIPS. 0.35 4/23/33 SIMILARITY 2nd ORT 95 i OPEN TO ALLOW S.P DISCHARGE INTO THE RCS HOT LEG DUR:NG THE HOT LEG RECIRCULATION PHASE OF ECCS GROUPING, 55 1N10121 4-IN GT 1004 N/A 2 OPERATION. 0.5 11/30/91 SIMILARITY 2nd ORT 95 OPENS TO ALLOW SIP DISCHARGE INTO THE RCS HOT LEG DUR:NG THE HOT LEG RECIRCULATION PHASE OF ECCS GROUPING, 56 1N!0152 4-IN GT 1004 N/A 2 OPERATION. 0.5 10/11/91 SIMILARITY 2nd ORT 95 OPENED TO REALIGN THE SPRAY PUMPS SUCTION FROM THE RWST TO THE GROUPING 57 1NS0001 12-IN GT 68 N/A 1 CONTAINMENT SUMP. 0.5 5/29/93 SIMILARITY 2nd ORT 95 CLOSED TO REALIGN THE SPRAY PUMPS SUCTION FROM THE RWST TO THE GROUPING, 58 1NS0003 12-IN GT 69 N/A 1 CONTAINMENT SUMP. 0.5 5/24/93 SIMILARITY 2nd ORT 95 OPEN UPON RECEIPT OF A SP SIGNAL AND STAY OPEN TO PROVIDE FLOW TO THE EPRI 59 1NS0012 8-IN GT 63 N/A 1 SPRAY HEADERS. 0.5 3/29/93 PPP, GROUPING 2nd ORT 95 OPEN UPON RECEIPT OF A SP SIGNAL AND STAY OPEN TO PROVIDE FLOW TO THE EP91 60 1NS0015 8-IN GT 63 N/A 1 SPRAY HFADERS. 0.5 3/30/93 PPP. GROUPING 2nd ORT 95 OPENED TO REALIGN THE SPRAY PUMPS SUCTION FROM THE RWST TO THE GROUPING, 61 1NS0018 12-IN GT 68 N/A 1 CONTAINMENT SUMP. 0.5 5/21/93 SIMILARITY 2nd ORT 95 CLOSED TO REALIGN THE SPRAY PUMPS SUCTION FROM THE RWST TO THE GROUPING, 62 1NS0020 12-IN GT 69 N/A 1 CONTAINMENT SUMP. 0.5 5/23/93 SIMILARIT'Y 2nd ORT 95 OPEN UPON RECEIPT OF A SP SIGNAL AND STAY OPEN TO PROVIDE FLOW TO THE EPRI 63 1NS0029 8-IN GT 63 N/A 1 SPRAY HEADERS. 0.5 4/14/93 PPP GROUPtNG 2nd ORT 95 OPEN UPON RECEIPT OF A SP SIGNAL AND STAY OPEN TO PROVIDE FLOW TO THE EPRI 64 1NS0032 8-IN Q 63 N/A 1 SPRAY HEADERS. 0.5 4/1/93 PPP. GROUPING 2nd ORT 95 Page 5 of 12
. . . _ _ . . - . _ _ - . - . . - - . - . _ . -._ - - . -~- . - . . - - . - . . . . - - - . .. - - - ~
McGUIRE NUCLEAR STATION ATTACHMENT 1 - .
MOVs WITHOUT STAGE 2 JUSTIFICATIONS AS OF 12-28-94 .
PLANNED VALVE DESIGN AVAIL STATIC PLANNED STAGE STAGE'2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COMPLETION SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE METHODS DATE OPENED TO PROVIDE A FLOWPATH FROM THE RHR PUMPS TO THE AUXILIARY EPRI 65 1NS0038 8-IN GT 204 N/A 1 CONTAINMENT SPRAY HEADERS. 0.5 4/16/93 PPP. GROUP NG 2nd ORT 95 OPENED TO PROVIDE A FLOWPATH FROM THE RHR PUMPS TO THE AUXILIARY EPRI 66 1NS0043 8-IN GT 204 N/A 1 CONTAINMENT SPRAY , TDERS. 0.5 4/16/93 PPP GROUPING 2nd ORT 95 CONTAINMENT ISOLAU. ?OR THE GROUPING, 67 1NV0094 4-IN GT 134 N/A 2 REACTOR COOLANT PLMP SEAL RETURN. 0.5 10/25/88 SIMILARITY 2nd ORT 95 CONTAINMENT ISOLATION FOR THE GROUPING, 68 1NV0095 4-IN GT 150 N/A 2 REACTOR COOLANT PUMP SEAL RETURN. 0.5 11/13/91 SIMILARITY 2nd ORT 95 ISOLATION FOR THE VOLUME CONTROL TANK AND THE SUCTION OF THE RECIPROCATING GROUPING, 69 1NV0141 4-IN GT 89 N/A 2 CHARGING PUMPS. 0.5 10/8/91 SIMILARITY 2nd ORT 95 ISOLATION FOR THE VOLUME CONTROL TANK AND THE SUCTION OF THE RECIPROCATING GROUPING, 70 1NV0142 4-IN GT 89 N/A 2 CHARGING PUMPS. 0.5 10/7/91 SIMILARITY 2nd ORT 95 PROVIDE A FLOWPATH FROM THE RWST TO THE NV PUMPS. CLOSE TO ISOLATE THE GROUPING, 71 1NV0221 8-IN GT 183 N/A 1 RWST FROM THE NV PUMPS. 0.5 5/12/93 SIMILARITY 2nd ORT 95 PROVIDE A FLOWPATH FROM THE RWST TO THE NV PUMPS. CLOSE TO ISOLATE THE GROUPING, 72 1NV0222 8-IN GT 183 N/A 1 RWST FROM THE NV PUMPS. 0.5 9/1/93 SIMILARITY 2nd ORT 95 ISOLATION OF RN TRAIN SUPPLY TO RN 1EOC9 EPRIPPP, 73 1RN0016 36-IN. BF 8 14500 1 PUMP. NA (9/94) GROUPING 2nd ORT 95 ISOLATION OF RN TRAIN SUPPLY TO RN 1EOC9 EPRIPPP, 74 1RN0018 36-IN. BF 8 14500 1 PUMP. NA (9/94) GROUPING 2nd ORT 95 RN SUPPLY TO THE AUX BLDG NON- 1EOC9 EPRIPPP, 75 1RN0042 10-IN. BF 121 98 2 ESSENTIAL HEADER. NA (9/94) GROUPING 2nd ORT 95 MARGIN UNIT 1 AUX BLDG VENT UNITS DISCHARGE TO 1EOC9 ANALYlSIS, 76 1RN0279 6-lN. BF 4 750 2 RN SYSTEM. NA (9/94) GROUPING 2nd ORT 95 Page 6 of 12
_ . _. _ , . _ .. . ._....__.m___._ ...m_ _ - . _ _ . . _. - _ . _ - _ . . ~ _ _ . _ . . _ _ ._. . - -.. . _ . _ _
~
McGUIRE NUCLEAR STATION ATTACHMENT 1- ;
MOVa WITHOUT STAGE 2 JUSTIFICATIONS AS OF 12-28-94 , .-
PLANNED VALVE DESIGN AVAll. STATIC PLANNED STAGE STAGE 2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COMPLETION SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE METHODS DATE MARGIN UNIT 1 RV AUX BLDG VENT UNITS DISCHARGE 1EOC9 ANALYlSIS, 77 1RN0299 6-IN. BF 3 750 2 TO RN SYSTEM. NA (9/94) GROUPING 2nd ORT 95 CONT,ISOL FOR THE LOWER CONTAINMENT VENT UNITS AND THE INCORE INSTRUMENT 1EOC9 EPRIPPP, 78 1RV0032 12-IN. BF 106 4080 2 ROOM VENT UNITS. NA (9/94) GROUPING 2nd ORT 95 CONT. ISOL FOR THE LOWER CONTAINMENT VENT UNITS AND THE INCORE INSTRUMENT 1EOC9 EPRIPPP, [
79 1RV0033 12-IN. BF 106 4080 2 ROOM VENT UNITS. NA (9/94) GROUPING 2nd ORT 95 CONT. ISOL FOR THE LOWER CONTAINMENT VENT UNITS AND THE INCORE INSTRUMENT 1EOC9 EPRIPPP, 80 1RV0076 12-IN. BF 106 4000 2 ROOM VENT UNITS. NA (9/94) GROUPING 2nd ORT 95
- VENT UNITS AND THE INCORE INSTRUMENT 1EOC9 EPRIPPP, 81 h?V0077 12-IN. BF 106 4000 2 ROOM VENT UNITS. NA (9/94) GROUPING 2nd ORT 95 CONTAINMENT ISOLATION FOR THE VUCDT 1EOC9 EPRIPPP, 82 1WLO321 6-IN. BF 91 0 1 INPUTS. NA (9/94) GROUPING 2nd ORT 95 CONTAINMENT ISOLATION FOR THE VUCDT 1EOC9 EPRIPPP, 83 IWLO322 6-IN. BF 91 0 1 INPUTS. NA (9/94) GROUPING 2nd ORT 95 THE NON-SAFETY-RELATED CONDENSATE EPRIPPP, 84 2CA0007 8-IN GT 117 I 'A 1 SOURCE 0.5 2/12/92 GROUPtNG 2nd ORT 95 THE NON-SAFETY-RELATED CONDENSATE EPRI PPP, 85 2CA0009 8-IN GT 117 N/A 1 SOURCE 0.5 2/14/92 GROUPING 2nd ORT 95 ISOLATES THE ASSURED RN SOURCE FROM THE NON-SAFETY-RELATED CONDENSATE EPRIPPP, 86 2CA0011 8-IN GT 117 N/A 1 SOURCE O.5 2/13/92 GROUPING 2nd ORT 95 PROVIDES THE TRAIN RELATED FLOWPATH FOR THE CA MDP A FROM THE SAFETY RELATED ASSURED RN SUPPLY FOR A DBA. EPRIPPP, 87 2CA0015 6-IN GT 116 N/A 1 OPEN FUNCTION 0.35 11/10/95 GROUPING 2nd ORT 95 PROVIDES THE TRAIN RELATED FLOWPATH FOR THE CA MDP B FROM THE SAFETY RELATED ASSURED RN SUPPLY FOR A DBA. EPRIPPP, 88 2CA0018 6-!N GT 116 N/A 1 OPEN FUNCTION 0.35 11/17/95 GROUPING 2nd ORT 95 Page 7 of 12
McGUIRE NUCLEAR CTATION ATTACHMENT l' MOVs WITHOUT STAGE 2 JUSTIFICATIONS AS OF 12-28-94 ,
PLANNED VALVE DESIGN AVAIL STATIC PLANNED STAGE STAGE 2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COMPLETION SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE METHODS DATE ISOLATION FOR S/G D FROM THE TDP IN THE EPRIPPP, 89 2CA0038 4-IN GT 2075 N/A 1 EVENT OF A FAULTED S/G. 05 2/27/92 GROUPING 2nd ORT 95 ISOLATION FOR S/G C FROM THE TDP IN THE EPRIPPP, 90 2CA0050 4-IN GT 2075 N/A 1 EVENT OF A FAULTED S/G. 0.5 1/22/92 GROUPING 2nd ORT 95 ISOLATION FOR S/G B FROM THE TDP IN THE EPRIPPP, 91 2CA0054 4-IN GT 2075 N/A 1 EVENT OF A FAULTED S/G. 0.5 8/25/93 GROUPING 2nd ORT 95 ISOLATION FOR S/G B FROM THE MDP A IN EPRIPPP, 92 2CA0058 4-IN GT 1605 N/A 1 THE EVENT OF A FAULTED S/G. 0.5 2/29/92 GROUPING 2nd ORT 95 ISOLATION FOR S/G A FROM THE TDP IN THE EPRIPPP, 93 2CA0066 4-IN GT 2075 N/A 1 EVENT OF A FAULTED S/G. 0.5 1/27/92 GROUPING 2nd ORT 95 PROVIDES THE TRAIN RELATED FLOWPATH EPRIPPP, FOR THE CA TDP FROM THE SAFETY GROUPING, RELATED ASSURED RN SUPPLY FOR A DBA. MARGIN 94 2CA0006 8-IN GT 116 N/A 1 OPEN FUNCTION. 0.35 7/1/93 ANALYSIS 2nd ORT 95
. PROVIDES THE TRAIN RELATED FLOWPATH EPRIPPP, FOR THE CA TDP FROM THE SAFETY GROUPING, RELATED ASSURED RN SUPPLY FOR A DBA. MARGIN 95 2CA0116 8-IN GT 116 N/A 1 OPEN FUNCTION 0.35 6/29/93 ANALYSIS 2nd ORT 95 EPRIPPP, PROVIDES THE FLOWPATH FOR THE CA TDP MARGIN TO PUMP FROM THE RC SYSTEM IN A SSS ANALYSIS, 96 2CA0161 8-IN GT 116 N/A 1 EVENT. OPEN FUNCTION. 0.35 7/12/93 GROUPING 2nd ORT 95 EPRIPPP, PROVIDES THE FLOWPATH FOR THE CA TDP MARGIN TO PUMP FROM THE RC SYSTEM IN A SSS ANALYSIS, 97 2CA0162 8-IN GT 116 N/A 1 EVENT. OPEN FUNCTION. 0.35 7/12/93 GROUPING 2nd ORT 95 SERVES AS PREHEATER BYPASS ISOLATION EPRIPPP, 98 2CF0126 6-IN GT 862 N/A 2 TO THE AUXILIARY FEEDWATER NOZZLES. 0.5 526/89 GROUPING 2nd ORT 95 SERVES AS PREHEATER BYPASS ISOLATION EPRIPPP, i 99 2CF0127 6-IN GT 862 N/A 2 TO THE AUXILIARY FEEDWATER NOZZLES. 0.5 5/28/89 GROUPING 2nd ORT 95 SERVES AS PREHEATER BYPASS ISOLATION EPRI PPP, 100 2CF0128 6-IN GT 862 N/A 2 TO THE AUXlLIARY FEEDWATER NOZZLES. 0.5 5/28/89 GROUPING 2nd ORT 95 Page 8 of 12
-. - - . . - .~ . _ . . - . - . - - .-- -
McGUIRE NUCLEAR STATION ATTACHMENT 1 '
MOVc WITHOUT STAGE 2 JUSTIFICATIONS AS OF 12-28-94 ,
PLANNED VALVE DESIGN AVAIL STATIC PLANNED STAGE STAGE"2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COMPLET10N SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE METHODS DATE SERVES AS PREHEATER BYPASS ISOLATION EPRIPPP, 101 2CF0129 6-IN GT 862 N/A 2 TO THE AUXILIARY FEEDWATER NOZZLES. 0.5 5/27/89 GROUPING 2nd ORT 95 TO THE NV EXCESS LETDOWN HEAT 102 2KC0305 3-IN GT 125 N/A 2 EXCHANGER. 0.5 2/23/92 PARTIAL dP TEST 2nd ORT 95 TO THE NV EXCESS LETDOWN HEAT 103 2KCO315 3-IN GT 125 N/A 2 EXCHANGER. 0.5 1/29/92 PARTIAL dP TEST 2nd ORT 95 BYPASS THE FULL LUBE OIL FILTER ON HIGH OPEN, LARGE 104 2LD0108 4-IN GT 57 N/A 2 DIFFERENTIAL PRESSURE. OPEN FUNCTION. 0.35 2/23/93 MARGIN 2nd ORT 95 BYPASS THE FULL LUBE Ott FILTER ON HIGH OPEN, LARGE 105 2LD0113 4-IN GT 57 N/A 2 DIFFERENTIAL PRESSURE. OPEN FUNCTION. 0.35 3/14/93 MARGIN 2nd ORT 95 EPRIPPP, 106 2NC0031 3-IN GT 2335 N/A 1 ISOLATE THE INLET TO EACH PORV 0.5 8/1&S3 GROUPtNG 2nd ORT 95 EPRIPPP, 107 2NC0033 3-IN GT 2335 N/A 1 ISOLATE THE INLET TO EACH PORV 0.5 8/19/93 GROUPING 2nd ORT 95 EPRIPPP, 108 2NC0035 3-IN GT 2335 N/A 1 1SOLATE THE INLET TO EACH PORV 0.5 8/20/93 GROUPING 2nd ORT 95 ISOLATE THE NC SYSTEM FROM THE ND EPRI PPP, 109 2ND0001 14-IN GT 386 N/A 1 SYSTEM. 0.5 7/21/93 GROUPING 2nd ORT 95 ISOLATE THE NC SYSTEM FROM THE ND SYSTEM. PROVIDE CONTA!NMENT ISOLATION EPRIPPP, 110 2ND0002 14-IN GT 530 N/A 1 DURING A SSS EVENT. 0.5 2/11/92 GROUPING 2nd ORT 95 PROVIDE ND PUMP SUCTION ISOLATION DURING THE RECIRCULATION PHASE OF AN EPRIPPP, 111 2ND0004 14-IN GT 200 N/A 1 ECCS ACTUATION. 0.5 7/7/93 GROUPING 2nd ORT 95 14.00-IN EPRIPPP, 112 2ND0019 GT 200 N/A 1 PROVIDE ND PUMP SUCTION ISOLATION. 0.5 7/22/93 GROUPtNG 2nd ORT 95 ALLOW HIGH PRESSURE SAFETY INJECTION EPRIPPP, 113 2N10009 4-IN GT 2710 N/A 1 INTO THE REACTOR COOLANT SYSTEM 0.5 2/5/92 GROUPING 2nd ORT 95 l ALLOW HIGH PRESSURE SAFETY INJECTION EPRIPPP, 114 2Nt0010 4-IN GT 2710 N/A 1 INTO THE REACTOR COOLANT SYSTEM 0.5 2/6,92 GROUPING 2nd ORT 95 Page 9 of 12
. _ _ . _ _ _ _ .. . ._.m _ . . _ _ _ . - _ _ . _ . _ _ . . _ . . . _ . _ - _ . ___._ _ _ _.m . _ . . . _ _ _ _ _
McGUIRE NUCLEAR STATION ATTACHMENT l ' ,
NOVA WITHOUT STAGE 2 JUSTIFICATIONJ AS OF 12-28-94 ,
.' l PLANNED VALVE DESIGN AVAIL STATIC PLANNED STAGE STAGE'2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COMPLETION SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE METHOOS DATE ALLOW COLD LEG ACCUMULATOR SAFETY .'.
tNJECTION INTO THE REACTOR COOLANT EPRIPPP, 115 2N10054 10-IN GT 633 N/A 1 SYSTEM 0.5 7/17/93 GROUPING 2nd ORT 95 ALLOW COLD LEG ACCUMULATOR SAFETY INJECTION INTO THE REACTOR COOLANT EPRIPPP, 116 2N!0065 10-IN GT 633 N/A 1 SYSTEM 0.5 8/11/93 GROUPING 2nd ORT 95 ALLOW COLD LEG ACCUMULATOR SAFETY INJECTION INTO THE REACTOR COOLANT EPRIPPP, 117 2NIOO76 10-IN GT 633 N/A 1 SYSTEM 0.5 6/18/92 GROUPING 2nd ORT 95 ALLOW COLD LEG ACCUMULATOR SAFETY INJECTION INTO THE REACTOR COOLANT EPRIPPP, 118 2N10088 10-IN GT 633 N/A 1 SYSTEM 0.5 7/17/93 GROUPING 2nd ORT 95 ALLOW FLOW FROM THE RWST TO THE SIPS.
CLOSE ON LOW RWST LEVEL TO ISOLATE EPRIPPP, 119 2N10100 8-4N GT 185 N/A 1 RWST FROM THE CCP, S!P, AND RHR PUMPS 0.5 1/23/92 GROUPING 2nd ORT 95 OPENED TO REALIGN THE SPRAY PUMPS SUCTION FROM THE RWST TO THE SIMILARITY, 120 2NS0001 12-IN GT 68 N/A 1 CONTAINMENT SUMP. 0.5 7/29/93 GROUPING 2nd ORT 95 CLOSED TO REALIGN THE SPRAY PUMPS SUCTION FROM THE RWST TO THE SIMILARITY, 121 2NS0003 12-IN GT 69 N/A 1 CONTAINMENT SUMP. 0.5 B/21/93 GROUPING 2nd ORT 95 OPEN UPON RECEIPT OF A SP SIGNAL AND STAY OPEN TO PROVIDE FLOW TO THE SIMILARITY, 122 2NS0012 8-tN GT 63 N/A 1 SPRAY HEADERS. 0.5 7/8/93 GROUPING 2nd ORT 95 OPEN UPON RECEIPT OF A SP SIGNAL AND STAY OPEN TO PROVIDE FLOW TO THE S!M;LARITY, 123 2NS0015 8-IN GT 63 N/A 1 SPRAY HEADERS. 0.5 7/7/93 GROUP 1NG 2nd ORT 95 OPENED TO REALIGN THE SPRAY PUMPS
- SUCTION FROM THE RWST TO THE SIMILARITY, 124 2NS0018 12-IN GT 68 N/A 1 CONTAINMENT SUMP. 0.5 7/29/93 GROUPtNG 2nd ORT 95 CLOSED TO REALIGN THE SPRAY PUMPS SUCTION FROM THE RWST TO THE SIMILARITY, 125 2NS0020 12-IN GT 69 N/A 1 CONTAINMENT SUMP. 0.5 8/12/93 GROUPtNG 2nd ORT 95 Page 10 of 12
_ -. .. ~ . _ . . - . - - . . . - . . - - - . - - ._ _ . . .- .. . ~_-=.- - - . . . . _ .. .
McGUIRE NUCLEAR STATION ATTACHMENT 1 '
MOVs WITHOUT STAGE 2 JUSTIFICATIONS AS OF 12-28-94 ,
PLANNED VALVE DESIGN AVAIL. STATIC PLANNED STAGE STAGE 2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COMPLETION SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION ,
FACTOR DATE METHODS DATE OPEN UPON RECEIPT OF A SP SIGNAL AND STAY OPEN TO PROVIDE FLOW TO THE SIMILARITY, !
126 2NS0029 8-IN GT 63 N/A 1 SPRAY HEADERS. 0,5 7/4/93 GROUPING 2nd ORT 95 OPEN UPON RECEIPT OF A SP SIGNAL AND STAY OPEN TO PROVIDE FLOW TO THE SIMILARITY, 127 2NS0032 8-IN GT 63 N/A 1 SPRAY HEADERS. 0.5 7/7/93 GROUPING 2nd ORT 95 OPENED TO PROVIDE A FLOWPATH FROM THE RHR PUMPS TO THE AUXILIARY SIMILARITY, 128 2NS0038 8-IN GT 204 N/A 1 CONTAINMENT SPRAY HEADERS. 0.5 7/26/93 GROUPING 2nd ORT 95 THE RHR PUMPS TO THE AUXILIARY SIMILARITY, 129 2NS0043 8-IN GT 204 N/A 1 CONTAINMENT SPRAY HEADERS. 0.5 7/26/93 GROUPlNG 2nd ORT 95 CONTAINMENT ISOLATION FOR THE SIMILARITY, 130 2NV0094 4-IN GT 134 N/A 2 REACTOR COOLANT PUMP SEAL RETURN. 0.5 7/1/88 GROUPING 2nd ORT 95 CONTAINMENT ISOLATION FOR THE SIMILARITY, 131 2NV0095 4-IN GT 134 N/A 2 REACTOR COOLA!4T PUMP SEAL RETURN. 0.5 7/6/88 GROUPING 2nd ORT 95 ISOLATION FOR THE VOLUME CONTROL TANK AND THE SUCTION OF THE RECIPROCATING SIMILARITY, 132 2NV0141 4-IN GT 89 N/A 2 CHARGING PUMPS. 0.5 8/5/93 GROUPING 2nd ORT 95 AND THE SUCTION OF THE RECIPROCATING SIMILARITY, 133 2NV0142 4-IN G1 89 N/A 2 CHARGING PUMPS. 0.5 1/30/92 GROUPING 2nd ORT 95 PROVIDE A FLOWPATH FROM THE RWST TO GROUPING, 134 2NV0221 8-IN GT 183 N/A 1 THE NV PUMPS. 0.5 2/11/92 EPRIPPP 2nd ORT 95 PROVIDE A FLOWPATH FROM THE RWST TO GROUPING, 135 2NV0222 8-IN GT 183 N/A 1 THE NV PUMPS. 0.5 8/7/93 EPRIPPP 2nd ORT 95 ISOLATION OF RN TRAIN SUPPLY TO RN 2EOC9 GROUPING, 136 2RN0016 36-IN. BF 8 14500 1 PUMP. NA (12/94) EPRIPPP 2nd ORT 95 ISOLATION OF RN TRAIN SUPPLY TO RN 2EOC9 GROUPING, 137 2RN0018 36-IN. BF 8 14500 1 PUMP. NA (12/94) EPRIPPP 2nd ORT 95 RN SUPPLY TO THE AUX BLDG NON- 2EOC9 GROUPING, 138 2RN0042 10-IN. BF 121 98 2 ESSENTIAL HEADER _._ NA (12/94) EPRIPPP 2nd ORT 95 Page 11 of 12
McGUIRE NUCLEAR STATION ATTACHMENT 1 -
MOVs WITHOUT STAGE 2 JUSTIFICATIONS AS OF 12-28-94 .
PLANNED VALVE DESIGN AVAIL STATIC PLANNED STAGE STAGE 2 SIZE & DESIGN DP FLOW SAFETY SIZING TEST 2 JUSTIFICATION COMPLETION SEQUENCE No. VALVE NO TYPE PSID GPM GROUP (1/2) SAFETY DESCRIPTION FACTOR DATE METHODS DATE MARGIN UNIT 2 AUX BLDG VENT UNITS DISCHARGE TO 2EOC9 ANALYSIS, EPRI 139 2RN0279 6-IN. BF 12 750 2 RN SYSTEM. NA (12/94) PPP 2nd ORT 95 MARGIN UNIT 2 RV AUX BLDG VENT UNITS DISCHARGE 2EOC9 ANALYSIS. EPRI 140 2RN0239 6-IN. BF 12 750 2 TO RN SYSTEM. NA (12/94) PPP 2nd ORT 95 CONT. ISOL FOR THE LOWER CONTAINMENT VENT UNITS AND THE INCORE INSTRUMENT 2EOC9 EPRIPPP.
141 2RV0032 12-IN. BF 106 4080 2 ROOM VENT UNITS. NA (12/94) GROUPING 2nd ORT 95 CONT. ISOL FOR THE LOWER CONTAINMENT VENT UNITS AND THE INCORE INSTRUMENT 2EOC9 EPRIPPP, 142 2RV0033 12-IN. BF 106 4080 2 ROOM VENT UNITS. NA (12/94) GROUPING 2nd ORT 95 VENT UNITS AND THE INCORE INSTRUMENT 2EOC9 EPRIPPP, 143 2RV0076 12-IN. BF 106 4080 2 ROOM VENT UNITS. NA (12/94) GROUPING 2nd ORT 95 VENT UNITS AND THE INCORE !NSTRUMENT 2EOC9 EPRIPPP, 144 2RV0077 12-IN. BF 106 4080 2 ROOM VENT UNITS. NA (12/94) GROUP 1NG 2nd ORT 95 2EOC9 EPRIPPP, 145 2WLO321 6-IN. BF 91 0 1 CONT. ISOL. FOR THE VUCDT INPUTS. NA (12/94) GROUPING 2nd ORT 95 2EOC9 EPRIPPP, 146 2WLO322 6-IN. BF 91 0 1 CONT. ISOL. FOR THE VUCDT INPUTS. NA (12/94) GROUPING 2nd ORT 95 Page 12 of 12
1 0 l l McGUIRE MODIFICATIONS ATTACHMENT 2 l SEQUENCE l l No. TAG No. COMMENTS / IMPROVEMENTS COMPLETE l l l 1 1 1CA0042 ACTUATOR CHANGE FROM 16NA 57 TO 16NAl 29 X l l 2 l1CA0046l ACTUATOR CHANGE FROM 16NA-57 TO 16NAl-29 l X l )
- 3 l1CA0058l ACTUATOR CHANGE FROM 16NA-57 TO 16NAl-29 l X l j 4 l1CA0062l AC FUATOR CHANGE FROM 16NA-57 TO 16NAl-29 l X l I i 5 X l2CA0042l ACTUATOR CHANGE FROM 16NA-57 TO 16NAl-29 l l 6 l 2CA0046l ACTUATOR CHANGE FROM 16NA-57 TO 16NAl 29 l X l
] 7 l 2CA0058l ACTUATOR CHANGE FROM 16NA 57 TO 16NAl-29 l X l 8 l 2CA0062ll ACTUATOR CHANGE FROM 16NA-57 TO 16NAl 29 i: X l f 9 ll1ND00151l ACTUATOR CHANGE FROM 16NA-57 TO 16NAl-43 ll X ll l 10 ll1ND00304 ACTUATOR CHANGE FROM 16NA-57 TO 16NAl-43 il X ll i
j 11 ll 1NV0221il ACTUATOR CHANGE FROM 16NA-57 TO 16N Al-29 !I X ll j 12 l 2NV0221l ACTUATOR CHANGE FROM 16NA-57 TO 16NAl-29 l X l j 13 l 1NV0222l ACTUATOR CHANGE FROM 16NA-5'7 TO 16NAl-29 l X l j 14 Il 2NV02220 ACTUATOR CHANGE FROM 16NA-57 TO 16NAl-29 ll X ll 1
l 15 ll 1CF0126ll ACTUATOR CHANGE FROM 30NA-115 TO 30NAl-86 ll X :1
} 16 l 1CF0127l ACTUATOR CHANGE FROM 30NA-115 TO 30NAl-86 l X l l 17 l1CF0128l ACTUATOR CHANGE FROM 30NA 115 TO 30NAl-86 l X l l 18 l 1CF0129l ACTUATOR CHANGE FROM 30NA-115 TO 30NAl-86 l X l
! 19 l 2CF0126l ACTUATOR CHANGE FROM 30NA-115 TO 30NAl-86 l X l l 20 l 2CF0127l ACTUATOR CHANGE FROM 30NA 115 TO 30NAl-86 l X l j 21 X l 2CF0128l ACTUATOR CHANGE FROM 30NA-115 TO 30NAl-86 l l l 22 ll 2CF0129h ACTUATOR CHANGE FROM 30NA-115 TO 30NAl-86 ll X ll 23 J ORN0003qSPRING PACK CHANGE [ X ll 3
24 l0RN0005l SPRING PACK CHANGE l X l 1 25 l 0RN0007l SPRING PACK & SMB-000-5 TO SMB-00-10 l X l l 26 l0RN0009l SPRING PACK & SMB-0045 TO SMB-00-10 l X l
) 27 l0RN0011l SPRING PACK CHANGE l X l
} 28 l0RN0013l SPRING PACK CHANGE l X l
} 29 l0RN0014l SPRING PACK CHANGE l X l
! 30 l0RN0015l SPRING PACK CHANGE l X l 31 l1RN0016l SPRING PACK CHANGE l X l 32 l1RN0018l SPRING PACK CHANGE l X l i
i l
j i
4 i
Page 1 of 1 12/19/94 4
ATTACIDENT 3 i l
LIST OF ABBREVIATIONS ABBREVIATION DESCRIPTION l CA AUXILIARY FEEDWATER CCP CENTRIFUGAL CHARGING PUMP DBA DESIGN BASIS ACCIDENT ECCS EMERGENCY CORE COOLING SYSTEM MDP MOTOR DRIVEN PUMP NCS, RCS NUCLEAR COOLANT SYSTEM ND DECAY (RESIDUAL) HEAT REMOVAL NV CHEMICAL VOLUME CONTROL SYSTEM (CHARGING)
PORV POWER OPERATED RELIEF VALVE PRT PRESSURIZER RELIEF TANK RC CONDENSER COOLING WATER i RCS, NCS REACTOR COOLANT SYSTEM RHR, ND DECAY (RESIDUAL) HEAT REMOVAL RN SAFETY RELATED RAW WATER RV RAW WATER TO CONTAINMENT COOLING RWST REFUELING WATER STORAGE TANK SG, S/G STEAM GENERATOR SIPS SAFETY INJECTION PUMPS SNSWP STANDBY NUCLEAR SERVICE WATER POND SP SAFETY SIGNAL FOR HIGH CONTAINMENT PRESSURE '
SSS SAFE SHUTDOWN SYSTEM S/W SERVICE WATER TDP TURBINE DRIVEN PUMP (CA)
VUCDT VENTILATION UNIT, CONDENSATE DRAIN TANK l
i
. . _- . _ _ . ._.