W3P85-3158, Forwards Response to Generic Ltr 83-28,Items 2.2.1,2.2.2 & 3.2 Re Equipment Classification,Vendor Interface Program & post-maint Testing of safety-related Components, Respectively,Per License Condition 13
| ML20136D439 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 11/15/1985 |
| From: | Cook K LOUISIANA POWER & LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| 10CR50.55E, GL-83-28, W3P85-3158, NUDOCS 8511210303 | |
| Download: ML20136D439 (19) | |
Text
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)OWER & L1GHT New ORLEANS LOUISIANA 70174-6000 9 (504) 300-e345 MIDDLE SOUTH UTIUTIES SYSTEM November 15, 1985 W3P85-3158 A4.05 NQA Director of Nuclear Reactor Regulation Attention:
Mr. G. W. Knighton, Chief Licensing Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555
SUBJECT:
Waterford SES Unit 3 Docket No. 50-382 License Condition No. 13
REFERENCE:
1.)
" Required Actions Based on Generic Implications of Salem ATWS Events" 2.)
Letter W3P84-3344 dated 11/30/84 from K.W. Cook to C. W. Knighton 3.)
Letter W3P85-0245 dated 01/30/85 from K.W. Cook to G. W. Knighton
Dear S,
ir:
Pursuant to the requirement stipulated in License Condition No. 13 of the Waterford 3 Facility Operating License No. NPF-38, Louisiana Power & Light Co.
hereby submits the responses to Items 2.2.1, 2.2.2 and 3.2 of Reference 1.
Attachment I describes the Equipment Classification Program that has been established for all safety-related components at Waterford 3.
The information presented in Attachment 1 is consistent with the prerequisites contained in Itea,2.2.1., addresses the Vendor Interface Program that has been accepted and implemented at Waterford 3 to satisfy the prerequisites of Item 2.2.2. documents LP&L's position in relation to the post-maintenance testing of safety-relsted components, consistent with the actions requested in Item 3.2.
N, LP&L is confident that the programs established in Attachments 1, 2 & 3 adequately satfsfy the guidelines of GL 83-28, Items 2.2.1, 2.2.2 & 3.2, respectively.
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'Mr. G.W. Knighton L
W3P85-3158 I:
Page 2 Completion of the above actions and those discussed in References 2 & 3 satisfies the requirement of License Condition No. 13.
Please contact me or R. J. Murillo at (504) 595-2838 should you require further information regarding.this matter.
Yours-very truly, 68 K. W.' Cook
' Nuclear Support and Licensing Manager KWC/TJG/smb' cc:
B. Churchill, W. M. Stevenson, R. D. Martin, D. M. Crutchfield, J. Wilson, J. Luehman NS20440 l-e nw e.
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ATTACHMENT 1 Equipment Classification Program In compliance with the commitment stipulated in W3P83-3911, Section 2.2.1, LP&L has completed a comprehensive review of the Waterford 3 equipment scheme and subsequently has developed a refined listing of safety-related components through the implementation of the Waterford 3 Master Equipment List / Quality List
.(MEL/Q-List).
The context of the MEL/Q-List is described below as the Waterford 3 Equipment Classification Program for ensuring that components of safety-related systems necessary for. accomplishing required safety functions are identified as safety-related.
The criteria for identifying components that are safety-related is based on the following categories as specified in LP&L Project Management Procedure PMP-321,
" Determination of Safety /Q-Level Components for the MEL/Q-List":
Piping system components designed and installed in accordance with the requirements of the ASME Boiler and Pressure Vessel Code Section III, subsections NB (Safety Class 1), NC (Safety Class 2) or ND (Safety Class 3);
Electrical components designated as IEEE Class IE; Components designated as Seismic Class 1.
Consequently those components in the plant that fall into one of the above categories are designated as safety-related and identified as such in the MEL/Q-List.
- Additionally, the equipment in the plant is considered to be one of the following:
an assembly, a component, or a piece part. Cataloging of this equipment has been established at the component level by a Unique Identification (UNID) Numbering Program. This program consists of an alphanumeric identification for each component. Components in the plant are being field verified with a UNID number in accordance with LP&L Project Management Procedure PMP-319. " Component Unique Identification (UNID) Numbering Program".
The components are then cataloged by operational system in a computerized Master Equipment List (MEL) utilizing the Station Information Management System (SIMS) data base. The Q-List is a subset of the MEL consisting of all the safety-related components in the plant. The definition of a component for the MEL is governed by LP&L Project Management Procedure PMP-310, "MEL/Q-List Component Determination";
determination if a component is safety-related and defined as such for the Q-List is governed by LP&L Project Management Procedure PMP-321. Components that have been determined to be safety-related are designated as 'Q-List' in the SIMS data base.
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Development of the Q-List was based on an analysis of operational systems to determine if safety-related components exist in each system. An evaluation was completed for each individual component within those systems determined to be 'Q Systems' or 'I' art-Q Systems'. Those systems that were determined not to contain any safety-related components were identified as Non-Q Systems.
The determination of whether a system was Q, Part-Q or Non-Q was based on a review of controlled design source documents. Documentation of this review is provided by Q System Scoping Forms (QSSF) which identify the source documents used to substantiate the system evaluation.
The basis for determination of the Q-List is an evaluation of each individual component outlined in the QSSF. A review of controlled design source documents identified the Piping code class, electrical designation, and seismic category for each component. Documentation of the evaluation is provided by Q-List Data Forms (QLDF) which are prepared for every component within the system scope and
)
list the source documents utilized in the evaluation.
Assurance that components within the scope of review had been accounted for and none inadvertently excluded from evaluation is documented by a Q System Completion Form (QSCF). The QSCF lists all components that were evaluated against a SIMS printout which contains a list of all components in the operational system.
The Q-List is maintained current by a dedicated staff whose activities are governed by LP&L Project Management Procedure PMP-321. This procedure is currently undergoing revision to include the requirements for Q-List maintenance activities, a summary of which follows. Design changes to the plant are evaluated to incorporate any revisions in the Q-List status of components identified to date. New components, regardless of whether the system was previously determined to be Q, Part-Q or Non-Q, are evaluated and documented by an individual QLDF.
Upon completion of system review, the QSCF is used to verify completion. This procedure revision is expected to be incorporated by February, 1986.
The hard copy file consisting of all documentation is fully maintained and stored by operational system in the LP&L Document Control Center - Project Files to provide auditable documentation of the basis for component evaluation and validation of the SIMS data base.
The Q-List information for components in the plant is entered into the SIMS data base and validated in accordance with LP&L Project Management Procedure PMP-320,
" Data Input and Control".
It is made available to the Plant Staff by on line access to the data base or by computer reports.
i Prior to the implementation of the Q-List, the process by which station personnel determined that an activity was safety-related was governed by Section 3.2 and Table 3.2-1 of the Waterford 3 FSAR. Additionally, various plant procedures such as UNT-5-002 and UNT-8-001 as well as those contained in Appendix A provided guidance to reflect this position.
As a result of the Q-List development, Plant Administrative Procedures UNT-5-002,
" Condition Identification and Work Authorization", and UNT-8-001, " Processing of Procurement Documents", are currently under revision to make reference to the use of the Q-List.
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In addition to the above noted changes, the procedures contained in Appendix A are also under revision to include utilization of the Q-List for determining the specific classification level of safety-related components. The revision consists of the following:
Adding the Q-List Report in the Reference Section of the procedure; Ensuring that the definitions of a Q-List Report and of safety-related components are incorporated into the procedure; and Including a special note in the procedure to not only make reference to the Q-List Report for equipment classification determination but also for identifying equipment qualification requirements.
The above mentioned revisions to Procedures UNT-5-002, UNT-8-001 and those contained in Appendix A will be incorporated by November 30, 1985.
Based on the information provided in the aforementioned procedures, plant personnel can then request data information on a specific component or obtain computer reports for the component in question.
Waterford 3 Administrative Procedure UNT-1-002, " Procedure Classification, Numbering and Format", identifies that if a procedure affects, or could potentially affect, safety-related activities, components, structures or systems, the words " Safety Related" are prominently displayed (stamped) on the title page. A list of procedures that apply to safety-related components for maintenance, surveillance, parts replacement, etc., is provided in APPENDIX C.
The management controls established for activities related to the development, validation and maintenance of the Q-List are governed by procedures and instructions which are prepared, reviewed, and approved in accordance with LP&L Project Management Procedure PMP-001, " Preparation and Revision of Project Management Procedure / Instructions". The management controls established for activities related to the routine utilization of the Q-List are governed by
.Waterford 3 Administrative Procedures UNT-1-002 and QP-5-001, " Instructions, Procedures and Drawings".
The current Waterford 3 Plant Procurement specifications are used for design verification and qualification testing in the procurement of safety-related components. These Procurement specifications include qualification testing for expected safety service conditions and provide support for the receipt of testing documentation to support the limits'of life recommended by the supplier.
The Waterford 3 procedure that governs the Plant's Procurement process is UNT-8-001 entitled, " Processing of Procurement Documents".
Specifications imposed upon the vendor are referenced on the Purchase Order Requisition based on either previous orders for the same equipment or specifications supplied by Engineering.
Standard Clauses in UNT-8-001 are used to ensure that technical and quality requirements are specified consistently for safety and quality related equipment orders.
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Design control and process controls are assured by specifying equipment as indicated on the updated design documents from vendors with a 10 CFR 50 Appendix B QA Program. Any exceptions noted by the vendor must be reviewed and approved by Engineering, in accordance with the applicable regulatory requirements.
Qualification testing is specified by citing the original equipment specifications and by including in the requisition the standard clauses as contained in UNT-8-001, on seismic and envfronmental qualification specifications. Exceptions noted by the vendor are reviewed and approved by Engineering by one of the following methods:
UNT-8-001 for a major exception; or UNT-7-021 entitled, " Spare Parts Equivalency Evaluation" by a Spare Parts Equivalency Evaluation Request (SPEER).
PE-2-006 entitled, " Plant Engineering Station Modifications" Parts received that do not meet purchase order requirements are identified on discrepancy notices which are resolved in a similar manner as the vendor exceptions mentioned above.
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g 4-APPENDIX A*
'Affected Procedures Where Safety Determination Is Reflected UNT-1-002 UNT-7-003'
-UNT-7-010-UNT-7-014 UNT-7-021 UNT-7-022 UNT-7-023 PE-1-001 PE-2-005 PE-2-006-l l.
See APPENDIX B for List of Procedure Designations b
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APPENDIX B LIST OF PROCEDURE DESIGNATIONS ME Electrical Maintenance Department Procedures ME Surveillance Procedures ME System Maintenance Procedures ME Calibration Procedures ME Testing Procedures MM Mechanical Maintenance Department Procedures MM Surveillance (Technical Specification Req.) Procedures MM Repair (Corrective Maintenance) Procedures MM Refueling Procedures MI Instrumentation and Control Department Procedures MI Administrative Procedures MI Surveillance Procedures MI Preventive Maintenance Procedures MI Calibration Procedures MI Installation Procedures MI Technical Procedures OP System Operation Procedures OP Instrumentation and Control Procedures OP Electrical Procedures OP Safety Systems Procedures OP - 901 -
0FF - Normal Operating Procedures OP - 902 -
Emergency Operating Procedures OP - 903 -
Operation Group Surveillance Procedures PE Plant Engineering Procedures PE Administrative Procedures PE Engineering Procedures PE Surveillances Procedures UNT Waterford 3 Administrative Procedures UNT Waterford 3 SES Procedural Program UNT Plant Operations and Maintenance Procedures UNT Engineering Controls and Communications Procedures UNT Budget, Procurement and Material Controls Procedures QP Plant Quality Administrative Procedure E
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1 APPENDIX C*
SAFETY-RELATED PROCEDURES UNT-7-003-ME-4-155 MI-5-206 MI-5-262
, UNT-7-014 ME-4-703' MI-5-207-MI-5-263 UNT-7-021-ME-4-809 MI-5-208 MI-5-264 MI-5-209 MI-5-265
-OP-4-003 ME-7-002 MI-5-210 MI-5-266 OP-4-004
.ME-7-003 MI-5-211 MI-5-267 OP-4-006' ME-7-004 MI-5-212 MI-5-268
- OP-4-008.
ME-7-007 MI-5-213 MI-5-269
-- OP-4-012 MI-5-214 MI-5-270:
MI-1-004 MI-5-215 MI-5-271
- OP-6-001-MI-1-005 MI-5-216 MI-5-272 OP-6-003 MI-5-217 MI-5-273 ALL MI 3's MI-5-218 MI-5-274
- OP-9-007' MI-5-219 MI-5-275 MI-4-137 MI-5-220 MI-5-276 OP-901-011 MI-4-302
.MI-5-221 MI-5-277 OP-901-053 MI-4-303 MI-5-223 MI-5-278 MI-4-304-MI-5-224 MI-5-279 OP-902-001 MI-4-307-MI-5-231 MI-5-280 OP-902-008 MI-4-308 MI-5-232 MI-5-281 MI-4-309 MI-5-233 MI-5-282 OP-903-005 MI-4-310 MI-5-235 MI-5-299 OP-903-006 MI-4-313 MI-5-240 MI-5-306 OP-903-102 MI-4-314 MI-5-251 MI-5-402 MI-4-315 MI-5-254 MI-5-427 MM-8-011 MI-4-316 MI-5-255 MI-5-428
. MM-8-040 MI-5-256 MI-5-436 MM-8-041 MI-5-201 MI-5-257 MI-5-465 MM-8-042 MI-5-202 MI-5-258 MI-5-501 MI-5-203 MI-5-259 MI-5-502 ME-4-141 MI-5-204 MI-5-260 MI-5-503 NE-4-145 MI-5-205 MI-5-261 MI-5-504 Continued on next page
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- See APPENDIX B for List of Procedure Designations
APPENDIX C*
SAFETY-RELATED PROCEDURES MI-5-506 MI-5-558 MI-12-020 MI-5-507 MI-5-561.
MI-5-508 MI-5-563 MI-13-121 MI-5-511 MI-5-566 MI-13-522 MI-5-512 MI-5-569' MI-13-523 MI-5-514-MI-5-571 MI-5-518 MI-5-573 PE-1-001 MI-5-519 MI-5-574 PE-1-003 MI-5-520 MI-5-575 PE-1-004
'MI-5-521 MI-5-576 PE-1-006 MI-5-524 MI-5-581
-MI-5-525 MI-5-582 PE-2-005 MI-5-526 MI-5-585 PE-2-006 MI-5-527 MI-5-587 MI-5-528 MI-5-588 ALL PE 5's MI-5-529 MI-5-591.
MI-5-530 MI-5-592 MI-5-532 MI-5-593 MI-5-534 MI-5-594
.MI-5-535 MI-5-595 MI-5-536 MI-5-596 MI-5-537 MI-5-614 MI-5-538 MI-5-621 MI-5-539 MI-5-622 MI-5-541 MI-5-624 MI-5-542 MI-5-629 MI-5-545 MI-5-634 t
MI-5-551 MI-5-708 MI-5-552 MI-5-709 MI-5-554 MI-5-556 MI-12-012 I
t
- See APPENDIX B for List of Procedure Designations l
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L ATTACHMENT 2
. Vendor Interface Program L
Por the specific purpose of defining an appropriate vendor interface program, LP&L_ participated.in the Nuclear Utility Task Action Committee (NUTAC) which was formed on September 1, 1983. As stipulated in W3P83-3911 LP&L committed to the implementation of such a program based on the results of-the NUTAC recommendations.
I the NRC of the formation and function of the Committee. The NRC concurred In a letter to the'NRC (Griffing to Eisenhut dated 09/15/83), NUTAC advised with the Committee's position and announced the appointment of a NRC Project
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Coordinator to participate in the NUTAC matters (as documented in a letter to NUTAC from Eisenhut to Griffing dated 09/28/83).
The NUTAC completed its work in March 1984 and published its report as the' Institute of Nuclear Power Operations (INPO) document 84-010. LP&L, acting-as a participating member, voted to approve the NUTAC final report and thereby l
endorsed the logic and methodology of that program to satisfy the requirements of Section 2.2.2 of GL 83-28.
Implementation of specific items presented in the NUTAC Report entitled the
" Vendor Equipment Technical Information Program" is discussed below. Additionally, LP&L's position and/or status of each item is provided for clarification.
SECTION 4.1: " RESPONSIBILITIES FOR IMPLEMENTATION" RECARDING SECTION 4.1.1.1: " Existing Programs" NSS VENDOR CONTACT LP&L has in place a continuously active, two-way technical information exchange and direct contact with its NSSS supplier, Combustion Engineering.
NPRDS/SEE-IN
'LP&L continues to be an active participant in both the Nuclear Plant Reliability Data System'(NPRDS)~and the'Significant Event
- Evaluation and Information Network (SEE-IN) Programs. LP&L can access the NPRDS data base information to assist in the preparation and planning activities that are currently in progress at Waterford 3.
Currently, the NPRDS data base contains engineering / test information
.forfsystems and components of various plants in the industry which includes Waterford 3. -Through constant participation in the NPRDS, LP&L l
is able to submit. failure reports in a timely manner.
The internal procedures needed to receive, analyze, control and disseminate information, whether it is to retrieve such information from or to enter it into the NPRDS and SEE-IN Programs, are complete 1
and functional. LP&L Project Management Procedure PMP-504, " Operations Assessment and Information Dissemination Group", provides the necessary instructions for evaluating material received from the SEE-IN Program and for disseminating such information to plant personnel and other utilities. LP&L Plant Administrative Procedure PE-01-010. " Nuclear Plant Reliability Data System (NPRDS) Data Submission and Retrieval", provides the necessary information for submitting or retrieving data from the NPRDS.
It is the intent of LP&L to continue its active involvement in the NPRDS and SEE-IN Programs and to incorporate, as appropriate and reasonable, any future revisions to these Programs.
OTHER VENDORS In the past and present circumstances, LP&L has never hesitated to seek assistance and Equipment Technical Information (ETI) from vendors of safety-related equipment. LP&L will continue to make use of this practice as recommended in the NUTAC Report and will also generate the appropriate reports through the use of the NPRDS and SEE-IN Programs.
INTERNAL HANDLING OF ETI As noted above, the LP&L internal administrative procedures for the NPRDS and SEE-IN Programs are complete and functional. The controls stipulated in the aforementioned procedures (PMP-504, PE-01-010) provide for the processing of incoming ETI such that the objectives outlined in the NUTAC Report are achieved.
INTERNAL RANDLING OF VENDOR SERVICES LP&L has Plant Procedures that provide for the internal control of vendor services. These controls include the provisions outlined in the NUTAC Report and also provide for the assurance that ETI furnished in conjunction with the performance of Vendor Services is handled in the same manner as other incoming ETI. LP&L Management Procedure PMP-004,
" Control of Vendor Information", establishes the methods for receiving, logging, indexing, tracking, reviewing, controlling and distributing vendor information related to Waterford 3.
LP&L Plant Administrative Procedure QP-007-001, " Control of Purchased Material, Equipment and Services", describes the acceptable methods to be utilized by the Plant Staff in controlling suppliers of purchased material, quality related material, equipment and services, to include the monitoring and acceptance of the items and services.
REGARDING SECTION 4.1.1.2: " Enhanced Programs" As previously noted, it is the intent of LP&L to continue its active participation in the NPRDS and SEE-IN Programs and to incorporate, as appropriate and reasonable, any future revisions or enhancements to the Programs. LP&L recognizes that incorporation of such enhancements could involve revisions to existing administrative programs, procedures, training or other related activities.
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SECTION 4.2: " SCHEDULE FOR IM'LEMENTATION" REGARDING SECTION 4.2.1: " Existing Programs"
'The LP&L internal procedures as described above incorporate and achieve the guidance and recommendation of the NUTAC Report, particularly that of Sections 3.1 and 4.1.1.1.
Future revisions, found to be necessary as the result of extensive usage, will be incorporated on a timely basis.
REGARDING SECTION 4.2.2: "Enchancements to Existing Programs" As recommended and discussed under Sections 3.2 and 4.1.1.2 of the Report, LP&L will incorporate enhancements to the existing programs on a timely basis. Such incorporation will be implemented 6 months af ter promulgation by INPO.
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ATTACHMEh"r 3 Post-Maintenance Testing Review LP&L has conducted a comprehensive review of the Waterford 3 test and maintenance precedures and Technical Specifications (TSs) to assure that post-maintenance operability testing of all safety-related equipment is required to be conducted, and that the testing does demonstrate that the equipment is capable of performing its safety functions prior to being returned to service.
The results of the TSs review revealed that post-maintenance testing, when required, is adequate to demonstrate operability. The results of the test and maintenance procedure review concluded that the procedures which require testing will adequately assure the operability of safety-related components before being returned to service. A list of these procedures is provided in Appendix D.
In the course of the review, eight (8) procedures were found that require enhancement to demonstrate operability. Consequently, ti1 procedures contained in Appendix E are under revision to include post-maintenance testing. These revisions are expected to be incorporated by November 30, 1985.
In conjunction with the above review, the TSs which required post-maintenance testing were also evaluated to identify those testing requirements which degrade rather than enhance safety. LP&L has concluded that as a result of the evaluation, no post-maintenance testing actually degraded rather than enhanced safety.
Also completed was a check of vendor and engineering recommendations to ensure that appropriate post-maintenance test guidance, where required, is included in the test and maintenance procedures and TSs mentioned above.
It was concluded that the existing procedures (See APPENDIX D) implement the post-maintenance guidance. Three (3) Electrical Maintenance Procedures (ME-5-004, ME-7-002 and MM-7-006) are under revision to include recommended test guidance. Revisions are expected to be incorporated by November 30, 1985.
While researching the aforementioned procedures the following observations were noted:
Information for specific equipment models was available and retrievable for approximately 95% of the safety-related components; Guidance applicable to the same component type (i.e., relay, transmitter, etc.) and supplied by the same manufacturer is included in the test and maintenance procedures.
Based on the information provided above, LP&L is confident that the program implemented at Waterford 3 to address post-maintenance testing is adequate for all safety-related components.
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APPENDIX D*
j' PROCEDURES THAT WILL ADEQUATELY ASSURE OPERABILITY OF SAFETY-RELATED EQUIPMENT ME-3-001 ME-4-121 ME-4-452 ME-5-100 ME-3-002 ME-4-131 ME-4-458 ME-5-101 ME-3-003 ME-4-141 ME-4-476 ME-5-102 ME-3-005 ME-4-145 ME-4-479 ME-5-105 ME-3-010 ME-4-146 ME-4-480 ME-5-106 ME-3-025 ME-4-151 ME-4-485 ME-5-107 ME-3-030.
ME-4-155 ME-4-501 ME-5-108 ME-3-050 ME-4-161 ME-4-541 ME-5-525 ME-3-100 ME-4-172 ME-3-110 ME-4-175 ME-5-001 ME-7-001 ME-3-120 ME-4-177 ME-5-002 ME-7-002 ME-3-200 ME-4-201 ME-5-003 ME-7-003 ME-3-210 ME-4-213 ME-5-004 ME-7-005 ME-3-220 ME-4-231 ME-5-005 ME-7-006 ME-3-300 ME-4-235 HE-5-031 ME-7-008 ME-3-306 ME-4-237 ME-5-033 ME-7-009 ME-3-308 ME-4-246 ME-5-051 ME-7-013 ME-3-310 ME-4-252 ME-5-052 ME-7-014 ME-3-311 ME-4-254 ME-5-053 ME-7-026 ME-3-312 ME-4-261 ME-5-062 ME-7-030 ME-3-314' ME-4-271 ME-5-063 ME-7-031 ME-3-315 ME-4-345-ME-5-067 ME-7-032 ME-3-316 HE-4-346 ME-5-070 ME-7-033 ME-3-318 ME-4-351 ME-5-072 ME-7-035 ME-3-319 ME-4-355 ME-5-077 ME-7-036 ME-3-325 ME-4-356 ME-5-084 ME-7-037 ME-3-327 ME-4-361 ME-5-085 ME-7-060 ME-3-330 ME-4-365 ME-5-086 ME-3-410 ME-4-371 ME-5-087 ME-4-385 ME-5-089 ME-4-081 ME-4-406 ME-5-094 ME-4-085 ME-4-421 ME-5-099 Continued on next page
- See APPENDIX B for List of Procedure Designations l
APPENDIX D*
PROCEDURES THAT WILL ADEQUATELY ASSURE OPERABILITY OF SAFETY-RELATED EQUIPMENT MM-3-015 MI-3-124 MI-3-368 MI-3-434 MM-3-017 MI-3-140 MI-3-370 MI-3-435 MM-3-027 MI-3-208 MI-3-371 MI-3-436 MM-3-028 MI-3-220 MI-3-372 MI-3-437 MM-3-032 MI-3-317 HI-3-374 MI-3-438 MI-3-318 MI-3-376 MI-3-439 MM-6-001 MI-3-319 MI-3-377 MI-3-441 MM-6-002 MI-3-320 MI-3-378 MI-3-456 MM-6-003 MI-3-321 MI-3-380 MI-3-457 MM-6-005 MI-3-323 MI-3-382 MI-3-458 MM-6-006 MI-3-324 MI-3-383 MI-3-459 MM-6-008 MI-3-325 MI-3-384 MI-3-460 MM-6-009 MI-3-326 MI-3-385 MI-3-461 MM-6-011 MI-3-331 HI-3-386 MI-3-462 MM-6-014 MI-3-332 MI-3-387 MI-3-463 MM-6-016 MI-3-334 MI-3-388 MI-3-464 MM-6-019 MI-3-335 MI-3-389 MI-3-466 MM-6-020 MI-3-340 MI-3-390 MI-3-468 MM-6-102 MI-3-341 MI-3-391 MI-3-469 MM-6-105 MI-3-342 MI-3-395 MI-3-470 MI-3-343 MI-3-396 MI-3-471 MM-8-002 MI-3-344 MI-3-400 MI-3-472 MM-8-003 MI-3-345 MI-3-401 MI-3-473 MM-8-012 MI-3-346 MI-3-409 MI-3-513 MM-8-035 MI-3-350 MI-3-422 MI-3-514 MI-3-352 MI-3-424 HI-3-515 MI-3-358 MI-3-425 MI-3-111 MI-3-360 MI-3-426 MI-3-112 MI-3-362 MI-3-427 MI-3-113 MI-3-364 MI-3-430 MI-3-114 MI-3-365 MI-3-431 HI-3-115 MI-3-366 HI-3-432 l
l Continued on next page
- See APPENDIX B for List of Procedure Designations
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APPENDIX D*
PROCEDURES THAT WILL ADEQUATELY ASSURE OPERABILITY OF SAFETY-RELATED EQUIPMENT MI-4-303 MI-5-233 MI-5-524 MI-5-576 MI-4-304 MI-5-235 MI-5-525 MI-5-581 MI-4-308 MI-5-251 MI-5-526 MI-5-582 MI-4-309 HI-5-254 MI-5-527 MI-5-583 HI-4-310 MI-5-299 HI-5-528 MI-5-584 MI-4-313 MI-5-306 MI-5-529 MI-5-586 MI-4-314 MI-5-402 MI-5-530 MI-5-587 MI-4-315 MI-5-425 MI-5-532 MI-5-588 MI-4-317 HI-5-426 MI-5-533 MI-5-590 MI-5-427 MI-5-534 MI-5-591 MI-5-160 MI-5-428 MI-5-535 MI-5-592 MI-5-201 MI-5-461 MI-5-536 MI-5-593 MI-5-202 MI-5-470 MI-5-537 MI-5-594 MI-5-203 MI-5-471 MI-5-538 MI-5-595 MI-5-204 MI-5-472 MI-5-539 MI-5-596 MI-5-205 MI-5-473 MI-5-541 MI-5-598 MI-5-206 MI-5-475 MI-5-545 MI-5-599 MI-5-207 MI-5-501 MI-5-551 MI-5-600 MI-5-208 MI-5-502 MI-5-552 MI-5-602 MI-5-209 MI-5-503 MI-5-554 MI-5-605 MI-5-210 MI-5-504 MI-5-556 MI-5-609 MI-5-211 MI-5-506 MI-5-557 MI-5-610 MI-5-212 MI-5-507 MI-5-558 MI-5-613 MI-5-213 MI-5-508 MI-5-561 MI-5-614 MI-5-214 MI-5-510 MI-5-563 MI-5-619 MI-5-215 MI-5-511 MI-5-566 MI-5-621 MI-5-216 MI-5-512 HI-5-569 MI-5-622 MI-5-217 MI-5-513 MI-5-571 MI-5-623 MI-5-220 MI-5-514 MI-5-572 HI-5-624 MI-5-221 MI-5-518 MI-5-573 MI-5-626 MI-5-223 MI-5-519 MI-5-574 MI-5-628 MI-5-224 MI-5-520 MI-5-575 MI-5-632 Continued on next page
- See APPENDIX B for List of Procedure Designations L.
o APPENDIX D*
PROCEDURES THAT WILL ADEQUATELY ASSURE OPERABILITY OF SAFETY-RELATED EQUIPMENT MI-5-634 MI-5-643 MI-5-644 MI-5-645 HI-5-648 MI-5-650 MI-5-702 MI-5-703 MI-5-704 MI-5-705 MI-5-708 MI-5-709 MI-5-900 MI-5-902 MI-5-904 MI-5-910 MI-5-913 MI-5-918 MI-5-919 MI-5-920 MI-5-923 HI-5-947 MI-12-011 MI-12-012 MI-12-013 HI-12-020 MI-13-522 MI-13-523 MI-13-524
- Sco APPENDIX B for List of Procedure Designations
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l APPENDIX E*
L PROCEDURES UNDER REVISION TO INCORPORATE RETEST OPERABILITY REQUIREMENT MI-5-218 MI-5-219 MI-5-232 MI-5-430 MI-5-460 MI-5-542 MI-5-601 4 MI-13-004 l
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- See APPENDIX B for List of Procedure Designations l
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