ML20023D393
| ML20023D393 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 05/17/1983 |
| From: | Harrington W BOSTON EDISON CO. |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| References | |
| 83-129, NUDOCS 8305200447 | |
| Download: ML20023D393 (11) | |
Text
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BosTO N EDISDN COMPANY B00 BOYLsTON STREET BOSTON. massachusetts 02199 WILLIAM D. HARRINGTON May 17,1983 BECo Letter No.83-129
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Mr. Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 License No. DPR-35 Docket No. 50-293
Subject:
Environmental Qualification of Safety-Related Electrical Equipment
References:
1.
Letter from D.B. Vassallo (NRC) to A.V. Morisi (BECo, " Safety Evaluation for Environmental Qualification of Safety-Related Electrical Equipment," dated April 13, 1983 (BECo 1.83.074).
2.
Letter from W.H.
Deacon (BECo) to R.C.
Haynes (NRC), dated February 8,1982 (BECo 2.82.040).
3.
Letter from A.V. Morisi (BECo) to B.H. Grier (NRC), dated Sep-tember 11, 1981 (BECo 2.81.213)
Dear Sir:
On January 21, 1983, the Nuclear Regulatory Commission promulgated 10CFR50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants (48 Federal Register 2729).
This rul e, which became effective February 22, 1983, contained requirements for a program to qualify safety-related electric equipment. Particularly 10CFR50.49(g) requested that we provide by May 20, 1983 a list of qualified equipment within the scope of the rule, and a schedule for either the qualification to the provisions of the rule or for the replacement of the remaining electric equipment important to safety within the scope of the rule.
This letter provides Boston Edison's response to satisfy these requirements.
Background
Since the issuance of the rule, Boston Edison has reviewed and interpreted the requirements as part of its effort to respond to the rule by May 20, 1983.
In some cases, we have provided an explanation of our interpretation of these require-ments to prevent a misunderstanding of our responses.
Our positions on these requirements are consistent with Boston Edison's previous interpretations of IE Bulletin 79-018, Director of Operating Reactors (DDR) guidelines, and NUREG-0588.
Different interpretations could substantially increase Boston Edison's equipment qualification effort, which we understand was not the NRC's intent in issuing 10CFR50.49.
It is Boston Edison's understanding that the intent of the NRC in this regard is that the rule imposes no new requirements on licensees who were b
8305200447 830517 PDR ADOCK 05000293 P
CDATON EDIEDN COMPANY Mr. Domenic B. Vassallo, Chief May 17, 1983 i
Page 2 required to qualify safety-related electrical equipment under the guidelines of IE Bulletin 79-01B and D0R guidelines.
Further, the NRC clearly stated that the rule would merely codify existing requirements and that if censees in compliance 4
i with existing interim requirements would be in compliance with the final rule.
i Since the issuance of IE Bulletin 79-01B, DOR guidelines and NUREG-0588, Boston Edison has submitted a number of responses to comply with the intent of these documents and has received an NRC safety evaluation along with a technical evalua-tion report (TER) (Reference 1).
As part of our effort in responding to the safety. evaluation, Boston Edison is providing under separate cover, justification for continued operation for items in NRC Categories I.B, II.A, II.B, and IV of the TER.
Boston Edison's plans for qualifying the equipment listed in these i
four categories are included in Attachment 1 to this letter.
The equipment covered by these categories are identified by an asterisk.
The final updated list of equipment that is required to be qualified pursuant to IE Bulletin 79-01B, DOR guidelines, and NUREG-0588 was provided in Reference 2.
As a result of ongoing reviews of our equipment qualification program, the list of equipment and qualification plans that were addressed in Reference 2 and are provided in Attachment 1 to this letter, will require future update.
Boston Edison will advise the staff regarding the status of this effort in the future.
A careful evaluation at various stages of review will be performed to ensure that equipment qualification concerns do not adversely affect the continued safe operation of Pilgrim Nuclear Power Station.
Boston Edison has performed an evaluation of all design basis events (DBE) as required in 10CFR50.49 b(1) and has concluded that the DBEs do not create a more severe environment than the currently assumed worst case environments created by pipe breaks inside and outside containment.
t Response to the Rule i
1.
List of all equipment required to be qualified pursuant to the rule. to this letter provides a list of equipment addressed in Refer-ence 2.
This list contains equipment that is addressed in 10CFR 50.49, Sections b(1), b(2), and b(3) based on our interpretation of these sections.
The methods used to determine equipment covered by these sections are given below.
Section b(1) Safety-Related Electrical Equipment Under this section, a list was made of those systems required during or following normal operating events (including anticipated operational occur-rences) and design basis accidents to ensure achievement of the safety actions specified in 10CFR50.49 b(1).
These safety actions require main-taining i) the integrity of the reactor coolant pressure boundary,11) the capability to shutdown the reactor and maintain it in a safe shutdown condi-tion, and 111) the capability to prevent or mitigate the consequences of accidents that could result in offsite doses comparable to 10CFR100 guide-lines.
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BOSTON EDISON COMPANY Mr. Domenic B. Vassallo, Chief May 17, 1983 Page 3 The systems list was used, in turn, to develop the list of components. of Reference 3 provides the detailed methodology that Boston Edison used to identify the list of safety-related equipment.
The Master List of components was developed by eliminating those components not subject to a harsh environment as described in 10CFR50.49(b).
Section b(2) Nonsafety-Related Electrical Equipment Whose Failure Could Pre-vent Satisfactory Accomplishment of Current Safety Functions The Pilgrim Nuclear Power Plant is designed such that failure of nonsafety-related electrical equipment will not prevent satisfactory achievement of the safety actions required to be performed by safety-related equipment.
This design intent is evidenced by several factors as follows:
(1) All safety-related systems are isolable from nonsafety-related systems by at least one isolation valve per interface.
These isolation valves receive power from station emergency power sources.
(2) Electrical independence is assured by powering all essential loads from dedicated buses.
(3) Breaker protection is provided to assure that electrical failures of non-safety-related equipment do not impact safety-related equipment.
(4) The routing of safety and nonsafety-related electrical cable is such that the physical separation and independence required for redundant systems is assured as specified in FSAR Section 8.9.
The question of nonsafety-related equipment impacting safety-related equip-ment at Pilgrim has been reviewed on at least two previous occasions. The first of these reviews was conducted in late 1979 in response to H. Denton's letter " Potential Unreviewed Safety Question on Interaction Between Non-Safety Grade Systems and Safety Grade Systems." The results of that review showed that the only high energy line break which could affect nonsafety equipment and worsen a transient would be a pipe break inside containment.
This could spuriously actuate the reactor vessel head vent valves (the valves are in series), thereby slightly increasing the effective break area.
Note that no cases were identified where equipment relied upon for safe shutdown could be prevented from performing the intended safety function due to the environmentally induced failure of nonsafety systems or components.
The second review was performed in response to IE Bulletin 79-27 to assure that safe shutdown can be achieved in spite of single failures in safety or nonsafety electric systems.
In particular, the review assured that alarms or proceduias exist such that failures of safety or nonsafety equip-ment will not prevent the capability to achieve cold shutdown, nor will such failures lead to operator confusion in carrying out the procedures.
BOSTON EDISON COMPANY Mr. Domenic B. Vassallo, Chief May 17,1983 Page 4 The environmental qualification effort will further assure that redundant environmentally qualified means of achieving safe shutdown are available.
These means of achieving safe shutdown will involve only safety-related equipment and will be independent of nonsafety grade equipment.
Section b(3) Certain Post-accident Monitoring Equipment Appendix C, " Emergency Procedure Display Equipment List," included in Refer-ence 3 provides the list of equipment that is covered under this section.
This list only reflects the existing plant configuration.
Boston Edison is currently assessing Pilgrim for conformance to Generic Ltr. 82-33.
As part of this effort, Regulatory Guide 1.97, Rev. 2 is being reviewed and a com-plete list of instrumentation is being prepared.
In response to Generic Ltr. 82-33, Boston Edison projects a date of April 19, 1985 to accomplish an item-by-f tem comparison between all the requirements of Regulatory Guide 1.97, Rev.
2 and the applicable systems and components at Pilgrim.
Any deviations found will be systematically evaluated and documented to determine if the deviation is justifiable due to plant-specific design, original design bases, or supportive operational requirements. Any deviations not found to be justifiable will be evalue.ted to determine what modifications, if any, are needed to conform to Regulatory Guide 1.97, Rev. 2.
The environmental qualification criteria for equipment covered by Regulatory Guide 1.97 review will depend on the outcome of the Generic Ltr. 82-33 effort.
Boston Edison will endeavor to qualify the instrumentation associated with Regulatory Guide 1.97 in accordance with the following schedule:
o Instrumentation that was identified as part of our earlier submittal (Reference 3, Appendix C) under emergency procedures, and already in operation, will be qualified according to applicable schedules described in Attachment 1.
The number and equipment qualification criteria of this instrumentation may change as a result of our Regulatory Guide 1.97 review for Generic Ltr. 82-33.
o New or upgraded instrumentation required to be qualified under the current Generic Ltr. 82-33 effort will be qualified prior to plant acceptance.
Schedule Constraints Boston Edison has developed an integrated plant modification plan for NRC review and acceptance.
This plan will provide safe, reliable, and economic operation of Pilgrim consistent with cost effective implementation of modifications, be they self-imposed or regulator-mandated (such as 10CFR50.49). The implementation schedule projected for each item of unqualified equipment will take into considera-tion the needed integration imposed by this approach.
The integrated approach has been adopted as one of the corporate policies to affect manageability of our resources; with schedules reflecting well thought
CO*;TO N EDISDN COMPANY Mr. Domenic B. Vassallo, Chief May 17,1983 Page 5 out strategies to minimize impact.
It is to this goal that Boston Edison has integrated the equipment qualification effort.
It is evident from a review of the implementation plan provided in Attachment 1 for each category of qualifica-tions, that Boston Edison intends to accomplish that task before March 1985, except in cases where we are as yet unable to fully scope qualification efforts due to the complexity of the work.
Our initial efforts should identify the final process of qualification (i.e., replacement, testing, protection, or upgrading).
At each step of our effort, Boston Edison will ensure that Pilgrim can be safely operated pending completion of equipment qualification.
We will provide the NRC with the needed information as soon as certain initial steps are completed and the scope of qualification is ascertained for the components under these categories. As stated in 10CFR50.49(h), Boston Edison will conform to the 60-day reporting requirement.
Clarifications 1.
Qualification Criteria 10CFR 50.49(k) states that applicants for, and holders of, operating licenses are not required to requalify equipment important to safety to the provisions of this rule if such equipment was previously required to be qualified pur-suant to either the D0R guidelines or NUREG 0588.
From this section, it is our understanding that equipment qualified pursuant to the D0R guidelines or NUREG-0588 by the dates and schedules set forth in 10CFR50.49(g) or the approved extensions, need not be qualified to the provisions of 10CFR50.49.
2.
Replacement Equipment 10CFR50.49(1) states that unless there are sound reasons to the contrary, replacement equipment must be qualified to the provisions of the rule.
The statement of consideratione discusses replacement parts, not replacement equipment.
It is our understanding that the provisions of the rule govern, and the appropriate emphasis is to be placed on replacement equipment and not parts.
Very truly yours, :
10CFR50.49(g) Qualification Plan
a 10CFR50.49(g) Qualification Plan As required by 10CFR50.49(g), Boston Edison provides the following information.
1.
List of Safety-Related Electric Equipment Within the Scope of the Rule, Al-ready Qualifted a) Fully qualified.
- Q101A
- Q101C
- RE1001-606A RE1001-606B
- RE1001-607A
- RElGd1-6078 b) Qualified with the exception of qualified life analysis and integration into plant maintenance program.
- A0220-44 SV5043A SVL53 Splice (600Y Pene)(IC)
SV5043B SYL54 Splice (S0V)(IC)
SV5044A SVL55 SV1301-12 SV5044B SYL56 SV1301-13 SV5065-10 SVL57 SV1301-34 SV5065-11 SYLS8 SV1301-35 SV5065 SVL60 SV1301-71 SV5065-13 SVL62
- SV203-3A SV5065-14 SVL67
- SV203-3B SV5065-15 SVL70
- SV203-3C SV5065-16 SYL79
- SV203-3D SV5065-17
- ZT203-1 SV220-44 SV5065-18
- ZT203-2 SV220-45 SV5065-19
- ZT203-3 SV2301-29 SV5065-20
- ZT203-4 l
SV2301-30 SV5065-21
- ZT203-5 SV2301-64 SV5065-22
- ZT203-6 SV2301-65 SV5065-23 SV2301-9312 SV5065-24 SV2301-9313 SV5065-25 SV2301-94 SV5065-26 SV5033A SV5065-27 SV5033B SV5065-33 l
SV5033C SV5065-34 SV5035A SV5065-37 t
SV5035B SV5065-38 SV5036A SV7011A SV5036B SV7011B SV5040A SV7017A SV5040B SV7017B SV5041A SYL49 l
SV5041B SVL50 SV5042A SVL51 i
SV50428 SVL52
- Categories I.b, II.a, and IV of Reference 1.
Page 1 of 6
c) Qualified with the exception of verifying proper installation interfaces.
DPT1001-650A DPT1001-6508 d) Qualified with the exception of verifying installation interfaces and aging analysis for incorporation into maintenance program.
SY4044A SV4044B Analysis and walkdown verification will be performed to qualify components in Items 1.b, c, and d, above, by March 1985.
2.
Safety-Related Electrical Equipment not Presently Qualified a) Replacement of existing non-qualified equipment by qualified equipment.
- FT1461A
- FT1461B
- FT2358 LS302-82A LS302-828 LS302-82C LS302-82D
- LT263-79 LT646A LT646B PT647A PT647B
- SV302-19A
- SV302-19B This equipment will be replaced and qualified by March,1985.
b) Equipment not included in either Item 1 or Item 2(a) will be categorized l
and qualified by the following methods (to the identified schedule).
b1) The list of equipment provided under this category will be analyzed and qualified for one or more of the following identified deficiencies, o Proving the similarity between the tested model and the installed model.
i l
i o Perfoming temperature, pressure, radiation, operating time, accuracy, and other analyses.
1 o Perfom analysis to prove that the failure of nonsafety-related com-ponents will not affect any safety-related components of that same equipment.
l Completion of the above stated analyses will either qualify the equipment or determine the next course of action (such as replacement, testing, upgrading, or shielding).
Page 2 of 6 l
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The analysis portion of the above effort is scheduled for completion in the early part of 1984. Depending on the outcome of the analysis and findings, Boston Edison will evaluate the qualification plans at that time and establish detailed schedules for final qualification in coordina-tion with Boston Edison's integrated modification plan. Every effort will be made to complete the final qualification by March 1985. However, should our analysis find that the mandated date of March 1985 would be difficult to achieve, Boston Edison may at that time notify the NRC and provide the needed justification for extension to November 1985 or beyond (10CFR50.49(h)).
112 Kerite (IC)
- DPIS 261-12A
- J210 112 Okonite (IC)
- DPIS 261-12B
- J211 112C Anaconda (IC)
- DPIS 261-12C
- J212 212 Kerite (IC)
- DPIS 261-120
- J213 212 Okonite (IC)
- DPIS 261-2A
- J214 212I Anaconda (IC)
- DPIS 261-28
- J215 310 Kerite (IC)
- DPIS 261-2C
- J 216 t
312 Kerite (IC)
- DPIS 261-2D
- LS2301-2351A 312 Okonite (IC)
- DPIS 261-2E
- LS2301-2351B i
312D Anaconda (IC)
- DPIS 261-2F
- PS1001-104A 512 Kerite (IC)
- DPIS 261-2G
- PS1001-104B 5120 Anaconda (IC)
- DPIS 261-2H
- PS1001-104C 512 Okonite (IC)
- DPIS 261-2J
- PS1001-104D l
712 Kerite (IC)
- DPIS 261-2K
- PS1001-83A 712 Okonite (IC)
- DPIS 261-2L
- PS1001-83B 712B Anaconda (IC)
- DPIS 261-2M
- PS1001-83C 912 Kerite (IC)
- DPIS 261-2N
- PS1001-83D
- A0203-2A
- DPIS 261-2P
- PS1001-89A l
- A0203-28
- DPIS 261-?R
- PS1001-89B l
- A0203-2C
- DPIS 261-2S
- PS1001-89C t
- A0203-2D
- DPIS 261-36A
- PS1001-89D l
B7 Kerite (IC)
- DPIS 261-36B
- PS1001-90A B7A Anaconda (IC)
- DPIS 261-37A
- PS1001-90B B8 Kerite (IC)
- DPIS 261-37B
- PS1J01-90C 88 Okonite (IC)
- DPIS 261-38A
- PS1001-900 89 Okonite (IC)
- DPIS 261-38B
- PS1001-93A
- TE9019
- DPIS 261-39A
- PS1001-938
- TE9044
- DPIS 261-398
- PS1001-93C l
C118 DPIS 5040A
- PS1001-930 C119 DPIS 5040B
- PS1360-9A
- C68 FS2301-2354
- PS1360-9B
- C69
- HPCI TURB Cont 1
- PS1360-9C CV9068A
- HPCI TURB Cont 2
- PS1360-9D CV9068B
- HPCI TURB Cont 3
- PS1451A
- DPIS1001-79A
- HPCI TURB Cont 4
- PS1451B
- DPIS1001-79B
- HPCI TURB Cont 5
- PS1464A
- DPIS 1243
- HPCI TURB Cont 6
- PS1464B
- DPIS 1244 HPCI TURB Cont 7
- PS2301-2368A
- DPIS 1360-1A
- HPCI TURB Cont 8
- PS2301-2368B
- DPIS 1360-1B
- HPCI TURB Cont 9
- PS2301-2389A
- DPIS 2301-2352
- J208
- PS2301-23838
- DPIS 2301-2353
- J 209
- PS2301-2389C (IC):
Inside Containment Page 3 of 6
- PS2301-2389D
- SY302-20B
- PS2360-1 SVL77 4
- PS261-23A SVL78
- PS261-23B
- TS1291-14C
- PS263-49A
- TS1291-14D
- PS263-498
- TS1291-14E
- PS263-50A
- TS1291-14F
- PS263-508
- TS1291-14G
- PS263-52A
- TS1291-14H
- PS263-52B
- TS1291-14J
- PS263-53A
- TS1291-14K
- PS263-53B
- TS1360-14C PS263-55A
- TS1360-14D PS263-55B
- TS1360-15A
- PS263-55C
- TS1360-15B
- PS263-550
- TS1360-15C PS3447
- TS1360-15D PS3457
- TS1360-16C 2
PS3467
- TS1360-16D PS503A
- TS1360-17A PS503B
- TS1360-17B PS503C
- TS1360-17C PS503D
- TS1360-17D
- PS512A
- TS2370C
- PS512B
- TS23700
- PSS12C
- TS2371A
- PSS12D
- TS2371B
- PS8135
- TS2371C
- PS8136
- TS2371D
- PT654
- TS2372C
- Q100A
- TS2372D
- Q100B
- TS2373A
- Q100C
- TS23738
- Q1000
- TS2373C
- Q100E
- TS2373D
- Q103B
- TS261-15A
Q104A
- TS261-15B
- Q104B
- TS261-15C
- Q104C
- TS261-150
- Q104D
- TS261-16A
- Q104E
- TS261-16B
- Q104F
- TS261-16C
- Q104G
- TS261-16D
- Q104H
- VAC204A
- Q104J
- VAC204B
- Q202A
- VAC204C
- Q202B
- VAC204D
- SC16-Rockbestos (IC)
- VGTF201A SI57275 (IC)
- VGTF201B
- SI57279 (IC)
- HPCI TURB Control
- S0117
- S0118
- SV302-20A Page 4 of 6
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b2) Under this category, the equipment identified requires a record search and/or possible field walkdown to verify nameplate data, installation interfaces, cable and termination manufacturer, flooding, pipe whip zone of influence on equipment, etc. Completion of the record search /walkdown will detemine whether the equipment is qualified or requires replacement, further analysis, or testing in order to qualify them. Boston Edison will make every effort to complete the final qualification by March 1985. How-ever, should our evaluation at the completion of the walkdown determine a final qualification schedule that goes beyond March 1985, Boston Edison will submit an extension to the current qualification schedule of March 1985, per 10CFR50.49(h).
Some of the equipment listed in this category will be inspected during normal plant operation, but the equipment that requires a plant outage for accessibility and ALARA considerations will be inspected in the next refueling outage, starting in January 1984.
112 Kerite (OC)
- C152
- CX2 Rockbestos 112 Okonite (0C)
- C153
- D7 210 Kerite (OC)
- C154
- D8 212 Kerite (OC)
- C155
- 09 212 Okonite (OC)
- C156 DPT1001-604A 310 Kerite (OC)
- C157 DPT1001-604B 312 Kerite (0C)
- C158 HPCI TURB CONT-RAMP GEN 312 Okonite (OC)
- C159
- LIS263-57A 410 Kerite (OC)
- C163
- LIS263-57B 412 Kerite (OC)
- C172
- LIS263-58A 412 Okonite (OC)
- C173
- LIS263-58B 512 Okonite (0C)
- C2201
- LIS263-72A 512 Kerite (OC)
- C2205A
- LIS263-72B 712 Kerite (0C)
- C2205B
- LIS263-72C 712 Okonite (OC)
- C2206A
- LIS263-72D 912 Kerite (0C)
- C2206B
- LITS 263-59A Al Kerite (OC)
- C2207A
- LITS 263-598 A1 Okonite (0C)
- C2207B M01001-16A A2 Kerite (OC)
- C2250A M01001-16B A2 Okonite (OC)
- C2250B M01001-18A A3 Kerfte (OC)
- C2251A M01001-18B A4 Kerite (0C)
- C2251B M01001-19
- A0203-1A
- C2256A M01001-21
- A0203-1B
- C2256B
- M01101-23A
- A0203-1C
- C2257A
- M01001-238
- A0203-10
- C2257B
- M01001-26A B1 Kerite (OC)
- C2260
- M01001-268 B2 Kerite (OC)
C2303 M01001-28A B3 Kerite (OC)
C513A M01001-288 B4 Kerite (00)
C513B M01001-29A B5 Kerite (0C)
C513C M01001-298 B65 Okonite (OC)
C5130 M01001-32 87 Kerite (OC)
C513E M01001-34A 88 Kerite (OC)
C513F M01001-34B 88 Okonite (OC)
C513G M01001-36A C12 Kerite (OC)
C513H M01001-36B
- C129A C68C M01001-37A
- C129B C69C (0C): Outside Containment Page 5 of 6
M01001-37B
- Q103A SV5081B M01001-43A
- Q105A SV5082A M01001-43B
- Q105B SV5082B M01001-43C
- Q106B SV5083A M01001-43D
- S1 SV50838 M01001-47 S3 SV5084A M01001-60
- SC16-Rockbestos (OC)
SV5084B M01001-7A SI57279 (0C)
SV5085A M01001-78 SV5065-11A SV5085B M01001-7C SV5065-13B SV5086A M01001-70 SV5065-14A SV6086B M01201-5 SV5065-158 SV5087A M01201-80 SV5065-18A SV5087B M01301-17 SV5065-208 SV5088A M01301-25 SV5065-21A SV5088B M01301-26 SV5065-22B SV9007A M01301-60 SV5065-24A SV9007B
- M01400-24A SV5065-25B SV9008A
- M01400-24B SV5065-26A SV9008B
- M01400-25A SV5065-27B SVL71
- M01400-25B SV5065-31 SYL72 M01400-3A SV5065-31B SVL73 M01400-3B SV5065-32 SVL74 M01400-4A SV5065-33A
- T1 M01400-4B SV5065-35 TE5021-02A M02301-10 SV5065-358 TE5022-04B Terminations (4 KV)
M02301-14 SV5065-36 M02301-3 SV5065-37A
- Terminations (less than M02301-35 SV5065-63 4KV)
M02301-36 SV5065-64
- TSD43 M02301-5 SV5065-65
- TSD44 M02301-8 SV5065-66
- TSD45 M02301-9 SV5065-67
- TSD46 M0261-2 SV5065-68
- TSD47 M04002 SV5065-69
- TSD48 M04010A SV5065-70 VAC201A M04010B SV5065-71 VAC201B M04060A SV5065-72
- VEX 210A M04060B SV5065-73
- VEX 210B M04085B SV5065-74
- B17
- P203A SV5065-75
- B18
- P203B SV5065-76
- B20
- P203C SV5065-77
- C61A l
- P203D SV5065-73
- C61B
- P215A SV5065-79 M01001-50
- P215B SV5065-80 M01001-63 l
PT1001-600A SV5065-81 M01201-2 PT1001-600B SV5065-82 M01301-16 PT1001-601A SV5065-83 M0202-5A PT1001-601B SV5065-84 M0202-5B
- Q101B SV5065-85 M02301-4
- Q102A SV5065-86 M0261-1
- Q102B SV5081A MON 109 MON 113 Page 6 of 6
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