ML20004D788
| ML20004D788 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 06/03/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004D783 | List: |
| References | |
| IEB-79-01B, IEB-79-1B, IEC-78-08, NUDOCS 8106100040 | |
| Download: ML20004D788 (28) | |
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i SAFETY EVALUATION REPORT BY THE l
OFFICE OF NUCLEAR REACTOR REGULATION l
EQUIPMENT QUALIFICATION BRANCH FOR VERMONT YANKEE ATOMIC POWER COMPANY j
VERMONT YANKEE ATOMIC POWER STATION i
DOCKET N0. 50-271 i
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I 8106100040-
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CONTENTS Pane 1
= Introduction...............................................
1 2
Background.................................................
1 2.1 Purpose...............................................
2 2.2 Scope................................................
2 3
Staff Evaluation...........................................
2 3.1 Completeness of Safety-Related Equipment..............
2 3.2 Service Conditions....................................
3 3.3 Temperature, Pressure, and Humidity Conditions Inside Containment....................................
4 3.4 Temperature, Pressure, and Humidity Conditions Outside Containment...................................
4 3.5 Submergence...........................................
4 3.6 Chemical Spray........................................
5 3.7 Aging................................................
5 3.8 Radiation (Inside and Outside Containment).............
5 4
Qualification of Equipment.................................
6 4.1 Equipment Requiring Immediate Corrective Action.......
6 4.2 Equipment Requiring Additional Information and/or Corrective Action.....................................
7 4.3 Equipment Considered Acceptable or Conditionally Acceptable............................................
8 5
Deferred Requirements......................................
8 6
Conclusions................................................
9 APPENDIX A Equipment Requiring Immediate Corrective Action APPENDIX B Equipment Requiring Additional Information and/or Corrective Action APPENDIX C Equipment Considered Acceptable or Conditionally Acceptable APPENDIX D Safety-Related Systems List iii
- o 0-SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT QUALIFICATION BRANCH FOR VERMONT YANKEE ATOMIC POWER COMPANY VERMONT YANKEE ATOMIC POWER STATION DOCKET NO. 50-271 ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT 1 INTRODUCTION General Design Criteria 1 and 4 specify that safety-related electrical equip-ment in nuclear facilities must be capable of performing its safety-related function'under environmental conditions associated with all normal, abnormal, and accident plant operation.
In order to ensure compliance with the cri-teria, the NRC staff required all licensees of operating reactors to submit a reevaluation of the qualification of safety related electrical equipment which may be exposed to a harsh environment.
2 BACKGROUND t
On February 8,1979, the NRC Office of Inspection and Enforcement (IE) issued to all licensees of operating plants (except those included in the systematic evaluation program (SEP)) IE Bulletin IEB 79-01, " Environmental Qualification of Class IE Equipment." This bulletin, together with IE Circular 78-08 (issued on May 31, 1978), required the licensees to perform reviews to assess the adequacy of their environmental qualification programs.
Subsequently, Commission Memorandum and Order CLI-80-21 (issued on May 23, 1980) states that the DOR guidelines and portions of NUREG-0588 (which were issued on January 14, 1980, as enclosures 4 and 5 to IEB-79-01B) form the requirements that licensees must meet regarding environmental qualification of safety-related electrical equipment in order to satisfy those aspects of 10 CFR 50, Appendix A, General Design Criterion (GDC)-4.
This order also requires the staff to complete safety evaluation reports (SERs) for all operating plants by February 1, 1981.
In addition, this order requires that the licensees have qualified safety-related equipment installed in their plants by June 30, 1982.
Supplements to IEB 79-01B were issued for further clarification and definivion of the staff's needs. These supplements were issued on February 29, September 30, and October 24, 1980.
In addition, the staff issued orders dated August 29, 1980 (amended in September 1980) and October 24, 1980 to all licenseee.
The August order required that the licensees provide a report, by November 1, 1980, documenting the qualifi-cation of safety-related electrical equipment.
The October order required the establishment of a central file location for the maintenance of all equipment-qualification records. The central file was mandated to be established by December 1, 1980.
The order also required that all safety-related electrical v
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equipment be qualified by June 30, 1982.
In response, the licensee submitted information through letters dated June 2 and November 1,1980.
2.1 Purpose The purpose of this SER is to identify equipment whose qualification program does not provide sufficient assurance that the equipment is capable of performing the design function in hostile environments. The staff position relating to i
any identified deficiencies is provided in this report.
2.2 Scope The scope of this report is limited to an evaluation of the equipment which must function in order to mitigate tN: consequences of a loss of-coolant accident (LOCA) or a high-energy-line-b'reak (HELB) accident, inside or outside containment, while subjected to the hostile environments associated with these accidents.
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3 -STAFF EVALVATION The staff evaluation of the licensee's response included an onsite inspection of selected Class IE equipment and an examination of the licensee's report for completeness and acceptability. The criteria described in the D0R guidelines and in NUREG-0588, in part, were used as a basis for the staff evaluation of the adequacy of the licer.see's qualification program.
i The NRC Office of Inspection and Enforcement performed (1) a preliminary evaluation of the licensee's response, documented in a technical evaluation report (TER) and (2) an onsite verification inspection (September 29 - October 2, 1980) of selected safety-related electrical equipment.
The main steam and high pressure coolant injection systems were inspected.
The inspection verified proper installation of equipment, overall interface integrity, and manufacturers' nameplate data. The manufacturer's name and model number from the nameplate data were compared to information give in the Component Evt.luation Work Sheets (CES) of the licensee's report.
The site inspection is documented in report IE 50-271/80-13. No deticiencies were noted.
For this review, the documents referenced above have been factored into the overall staff evaluation.
3.1 Completeness of Safety-Related Equipment t
In accordance with IEB 79-01B, the licensee was directed to (1) establish a list of systems and equipment that are required to mitigate a LOCA and an HELB l
and (2) identify components needed to perform the function of safety-related display information, post-accident sampling and monitoring, and radiation monitoring.
The staff developed a generic master list based upon a review of plant safety f
analyses and emergency procedures.
Th instrumentation selected includes parameters to monitor overall plant performance as well as to monitor the per-formance of the systems on the' list.
The systems list was established on the basis of the functions that must be performed for accident mitigation (without regard to location of equipment relative to hostile environments).
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The list of safety-related systems provided by the licensee was reviewed against the staff-developed master list.
i Based upon information in the licensee's submittal, the equipment location references, and in some cases subsequent conversations with the licensee, the staff has verified and determined that the systems included in the licensee's submittal are those required to achieve or support:
(1) emergency reactor shutdown, (2) containment isolation, (3) reactor core cooling, (4) containment heat removal, (5) core residual heat removal, and (6) prevention of signifi-cant release of radioactive material to the environment.
The staff therefore concludes that the systems identified by the licensee (listed in Appendix D) are acceptable, with the exception of those items discussed in Section 5 of this report.
Display instrumentation which provider information for the reactor operators to aid them in the safe handling of the plant was not specifically identified l
by the licensee.
A complete list of all display instrumentation mentioned in the LOCA and HELB emergency procedures must be provided.
Equipment qualiff-cation information in the form of summary sheets should be provided for all components of the display instrumentation exposed to harsh environments.
Instrumentation which is not considered to be safety related but which is mentioned in the emergency procedure should appear on the list.
For these instruments, (1) justification should be provided for not considering the
. instrument safety related and (2) assurance should be provided that its subsequent failure will r.ot mislead the operator or adversely affect the mitigation of the consequences of the accident.
The environmental qualifi-cation of,20st-accident sampling and monitoring and radiation mor.itoring equipment is closely related to the review of the TMI Lescons-Learned i
modifications and will be performed in conjunction with that review.
l The licensee identified 270 items of equipment which were assessed by the staff.
1 3.2 Service Conditions I
Commission Memorandum and Order CLI-80-21 rec,uires that the D0R guidelines and the "For Comment" NUREG-0588 are to be used as the criteria for establishing the adequacy of the safety-related electrical equipment environmental quali-fication program.
These documents provide the option of establishing a bounding pressure and temperature condition based on plant-specific analysis identified i
in the licensee's Final Safety Analysis Report (FSAR) or based on generic profiles using the methods identified in these documents.
On this basis, the staff has assumed, unless otherwise noted, that the analysis for developing the environmental envelopes for Vermont Yankee, relative to the temperature, pressure, and the containment spray caustics, has been performed in accordance with the requirements stated above. The staff has reviewed the qualification documentation to ensure that the qualification specifications envelope the conditions established by the licensee.
During this review, the staff assumed that for plants designed and equipped with an automatic containment spray system which satisfies the single-failure criterion, the mair. team-line-break (MSLB) environmental conditions are enveloped by the large-bro k-LOCA,
environmental conditions. The staff assumed, and requires the licensee to verify, that the containment spray system is not subjected to a disabling r
single-component failure and therefore satisfies the requirements of Section 4.2.1 of the 00R guidelines.
t Equipment submergence has also been addressed where the possibility exists that flooding of equipment may result from HELBs.
t 3.3 Temperature, Pressure, and Humidity Conditions Inside Containment The licensee hr.: provided the results of accident analyses as follows:
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Max Temp (*F)
Max Press (psig)
Humidity (%)
i LOCA 325 44 100 MSLB (not provided)
(not provided) 100 The staff has concluded that the minimum temperature profile for equipment qualification purposes should include a margin to account for analytical uncertainties in the calculated temperature profiles for postulated accio'ents.
A margin of 20*F above steam saturation temperature is considered to be appro-priate for either a postulated LOCA or MSLB, whichever is controlling as to potential adverse environmental effects on equipment.
i The licensee's minimum temperature profile for qualification purposes includes a margin at least as large as would result from the staff's recommendation.
Therefore, the staff concludes that the specified temperature profile is acceptable.
t 3.4 Temperature, Pressure, and Humidity Conditions Outside Containment The licensee has provided the temperature, pressure, humidity and applicable environment associated with an HELB outside containment.
The following areas outside containment have been addressed:
-(1) Steam tunnel
- (2) Torus area (3) Reactor building (4) HPCI oump room (5) RCIC pump room The staff has verified that the parameters identified by the licensea for the MSLB are acceptable.
f 3.5 Submergence r
The maximum submergence levels have been established and assessed by the licensee.
Unless otherwise noted, the staff assumed for this review that the methodology employed by the licensee is in accordance with the appropriate i
criteria as established by Commission Memorandum and Order CLI-80-21.
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The licensee's value for maximum submergence is at elevation 239 ft 8 in.
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equipment below this level inside the containment has been identified by the licensee.
It is not clear from the information submitted that submergence of safety-related electrical equipment outside of containment was addressed.
The licensee should address this area more specifically in the 90-day response and upgrade the CES as appropriate.
3.6 Chemical Spray The licensee has not identified containment spray as. a safety-related system, i
and credit has not been taken in the analysis.
The system is manually operated and ucas demineralized water.
Because spray is available and could be used, any equipment upon which it impinges must be qualified for the spray parameter.
The licensee should provide additional information to resolve this concern.
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3.7 Section 7 of the 00R guidelines does not require a qualified life to be estab-lished for all safety-related electrical equipment.
However, the following actions are required:
(1) Make a detailed comparison of existing equipment and the materials identi-fled in Appendix C of the 00R guidelines.
The first supplement to IEB-79-018 requires licensees to utilize the table in Appendix C and identify any additional materials as the result of their effort.
(2) Establish an ongoing program to review surveillance and maintenance records to identify potential age-related degradations.
(3) Establish component maintenance and replacement schedules which include considerations of aging characteristics of the installed components.
I The licensee identified a number of equipment items for which a specified qualified life was established (for examples, 5 years, 15 years, or 40 years).
In its assessment of these submittals, the staff did not review the adequacy of the methodology nor the basis used to arrive at these values; the staff has assumed that the established values are based on state-of-the-art technology and are acceptable.
For this review, however, the staff requires that the licensee submit supple-mental information to verify and identify the degree of conformance to the above requirements. The response should include all the equipment identified as required to maintain functional operability in harsh environments.
The licensee indicated that this phase of the response is outstanding and that the review is in progress.
The staff will review the licensee's response when it is submitted and discuss its evaluation in a supplemental report.
3.8 Radiation (Inside and Outside Containment)
The licensee has provided values for the radiation levels postulated to exist following a LOCA.
The application and methodology employed to determine these values were presented to the licensee as part of the NRC staff criteria con-tained in the DOR guidelines, in NUREG-0588, and in the guidance provided in IEB-79-018, Supplement 2.
Therefore, for this review, the staff has assumed,
that, unleas otherwise noted, the values provided have been determined in accordance with the prescribed writeria.
The staff review determined that the values to which equipment was qualified enveloped the requirements identified by the licensee.
The value required by the licensee inside containment is an integrated dose ranging from S.0 x 107 to 1.0 x 10s rads.
This value envelopes the 00R guide-line requirements and is therefore acceptable.
A required value outside containment of 1.6 x 108 rads has been used by the licensee to specify limiting radiation levels around the RHR system in the reactor building. This value appears to consider the radiation levels influenced by the source term methodology associated with post-LOCA recircula-tion fluid lines and is therefore acceptable.
4 QUALIFICATION OF EQUIPMENT The following subsections present the staff's assessment, based on the licen-see's submittal, of the qualification status of safety-related electrical equipment.
The staff has separated the safety related equipment into three categories:
(1) equipment requiring immediate corrective action, (2) equipment requiring additional qualification information and/or corrective action, and (3) equip-ment considered acceptable if the staff's concern identified in Section 3.7 is satisfactorily resolved.
In its assessment of the licensee's submittal, the NRC staff did not review the methodology employed to determine the values established by the licensee.
However, in reviewing the data sheets, the staff made a determination as to the stated conditions presented by the licensee.
Additionally, the staff has not completed its review of supporting documentation referenced by the licen-see (for example, test reports).
It is expected that when the review of test reports is complete, the environmental qualification data bank established by the staff Mill provide the means to cross reference each supporting document to the referencing licensee.
If supporting documents are found to be unacceptable, the licensee will be required to take additional corrective actions to either establish qualifi-cation or replace the item (s) of concern.
This effort will begin in early 1981.
An appendix for each cubsection of this report provides a list of equipment for which additional information and/or corrective action is required.
Where appropriate, a reference is provided in the appendices to identify deficiencies.
It should be noted, as in the Commission Memorandum and Order, that the deficien-cies identified do not necessarily mean that equipment is unqualified.
- However, they are cause for concern and may require further case-by-case evaluation.
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4.1 Equipment Requiring Immediate Corrective Action f
Appendix A identifies equipment (if any) in this category.
The licensee was asked to review the facility's safety-related electrical equipment.
The licensee's review of this equipment has not identified any equipment requiring immediate corrective action; therefore, no licensee event reports (LERs) were submitted.
In addition, in this review, the staff has not identified any safety-related electrical equipment which is not able to perform its intended safety function during the time in which it must operate.
4.2 Equipment Requiring Additional Information and/or Corrective Action Appendix B identifies equipment in this category, including a tabulation of deficiencies.
The deficiencies are noted by a letter relating to the legend (identified below), indicating that the in'ormation provided is not sufficient for the qualification parameter or condition.
Legend R
- radiation T
- temperature QT qualification time RT - required time P
pressure H
- humidity l
CS - chemical spray A
- material-aging evaluation; replacement schedule; ongoing equipment surveillance S
- submergence M
- margin I
- HELB evaluation outside containment not completed QM qualification method RPN - equipment relocation or replacement; adequate schedule not provided EXN - exempted equipment justification inadequate SEN - separate-effects qualification justification inadequate QI qualification information being developed RPS - equipment relocation or replacement schedule provided As noted in Section 4, these deficiencies do not necessarily mean that the equipment is unqualified. However, the deficiencies are cause for concern and require further case-by-case evaluation.
The staff has determined that an acceptable basis to exempt equipment from qualification, in whole or part, can be established provided the following can be established and verified by the licensee:
(1) Equipment does not perform essential safety functions in the harsh environ-ment, and equipment failure in the harsh environment will not impact safety related functions or mislead an operator.
i (2a) Equipment performs its function before its exposure to the harsh environ-ment, and the adequacy for the time margin provided is adequately justified, and i
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(2b) Subs"1uent failure of the equipment as a result of the harsh environment does not degrade other safety functions or mislead the operator.
(3) The safety-related function can be accomplished by some other designated equipment that has been adequately qualified and satisfies the single-failure criterion.
(4) Equipmint will not be subjected to a harsh environment as a result of the postulated accident.
The licensee is, therefore, required to supplement the informatica presented by providing resolutions to the deficiencies identified; these resolutions should include a description of the corrective action, schedules for its completion (as applicable), and so forth. The staff will review the licensee's response, when it is submitted, and discuss the resolution in a supplemental report.
It should be noted that in cases where testing is being conducted, a condition may arise which results in a determination by the licensee that the equipment does not satisfy the qualification test requirements.
For that equipment, the licensee will be required to provide the proposed corrective action, on a timely basis, to ensure that qualification can be established by June 30, 1982.
4.3 Equipment Considered Acceptable or Conditionally Acceptable Based on the staff review of the licensee's schmittal, the staff identified the equipment in Appendix C as (1) acceptable on the basis that the qualifi-cation program adequately enveloped the specific environmental plant parameters, or (2) conditionally acceptable subject to the satisfactory resolution of the staff concern identified in Section 3.7.
For the equipment identified as conditionally acceptable, the staff determined that the licensee did not clearly (1) state that an equipment material evaluation was condu;ted to ensure that no known materials susceptible to degradation because of aging have been
- used, (2) establish an ongoing program to review the plant surveillance and main-tenance records in order to identify equipment degradation which may be age related, and/or (3) propose a maintenance program and replacement schedule for equipment identified in item 1 or equipment that is qualified for less than the life of the plant.
The licensee is, therefore, required to supplement the information presented for equipment in this category before full acceptance of this equipment can be established.
The staff will review the licensee's response when it is sub-i mitted and discuss the resolution in a supplemental report..
5 DEFERRED REQUIREMENTS-IEB 79-01B, Supplement i has relaxed the time constraints for the submission of the information associated with cold shutdown equipmi A and TMI lessons-learned modifications.
The nraff has required that this information be provided by February 1,1981.
The storf will provide a supplemental safety evaluation addressing these concerns.
6 CONCLUSIONS The staff has determined that the licensee's listing of safety-related systems and associated electrical equipment whose ability to function in a harsh environment following an accident is required to mitigate a LOCA or HELB is complete and acceptable, except as noted in Section 3 of this report.
The staff has also determined that the environmental service conditions to be met by the electrical equipment in the harsh accident environment ar.' appropriate, except as noted in Section 3 of this report. Outstanding information identi-fled in Section 3 should be provided within 90 days of receipt of this SER.
The staff has reviewed the qualification of safety-related electrical equip-ment to the extent defined by this SER and has found no outstanding items which would require immediate corrective action to ensure the safety of plant operation. However, the staff has determined that many items of safety-related electrical equipment identified by the licensee for this review do not have adequate documentation to ensure th=t they are capable of withstanding the ha.'sh environmental service conditions.
This review was based on a comparison of the qualification values with the specified environmental values required by the design, which were provided in the licensee's summary sheets.
Subsection 4.2 identified deficiencies that must be resolved to establish the qualification of the equipment; the staff requires that the information lack-ing in this category be provided within 90 days of receipt of tnis SER.
Within this period, the licensee should either provide documentation of the missing qualification information which demonstrates that such equipment meets the 00R guidelines or NUREG-0588 or commit to a corrective action (requalifi-cation, replacement, relocation, and so forth) consistent with the requirements to establish qualification by June 30, 1982.
If the latter option is chosen, the licensee must provide justification for operation until such corrective action is complete.
Subsection 4.3 identified acceptance and conditional acceptance based on noted deficiencies.
Where additional information is required, the licensee should respond within 90 days of receipt of this SER by providing assurance that these concerns will be satisfactorily resolved by June 30, 1982.
The staff issued to the licensee Sections 3 and 4 of this report and requested, under the provisions of 10 CFR 50.54(f), that the licensee review the deficien-cies enumerated and the ramifications thereof to determine whether safe operation of the facility would be impacted in consideration of the deficiencies.
The licensee has completed a preliminary review of the identified deficiencies and has determined that, after due consideration of the deficiencies and their ramifications, continued safe operation would not be adversely affected.
Based on these considerations, the staff concludes that conformance with the above requirements and satisfactory completion of the corrective actions by June 30, 1982 will ensure compliance with the Commission Memorandum and Order of May 23, 1980. The staff further concludes that there is reasonable assur-ance of continued safe operation of this facility pending completion of these corrective actions. This conclusion is based on the following:
(1) that there are no outstanding items which would require immediate correc-tive action to assure safety of plant operation (2) some of the items found deficiont have been or are being replaced or relocated, thus improving the facility's capability to function following a LOCA or HELB (3) the harsh environmental conditions for which this equipment must be qualified result from low probability events; events which might reasonably be anticipated during this very limited period would lead to less demanding service conditions for this equipment.
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APPENDIX A Equipment Requiring Immediate Corrective Action (Category 4.1)
No equipment in this category.
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APPENDIX B Equipment Requiring Additional Information and/or Corrective Action (Category 4.2)
LEGEND:
R - Radiation T - Temperature
-QT - Qualification time RT - Required time P - Pressure H - Humidity CS - Chemical spray A - Material aging evaluation, replacement schedule, ongoing equipment i
surveillance S - Submergence M - Margin I - HELB evaluation outside containment not completed QM - Qualification method RPN - Equipment relocation or replacement, adequate schedule not provided EXN - Exempted equipment justification inadequate SEN - Separate effects qualification justification inadequate QI - Qualification information being developed RPS - Equipment relocation or replacement schedule provided l
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Equipment Description Manufacturer Component No.
Deficiency l
Motor Operator Limitorque MOV-70-19A QI Motor Operator Limitorque MOV-70-198 QI Motor Operator Limitorque MOV-70-19C QI i
Solenoid Oper. Valve Target Rock VG-23 QM,QT,H,A Solenoid Oper. Valve Target Rock VG-9A QM,QT,H,A t
Solenoid Oper. Valve Target Rock VG-12A QM,QT,H,A i
Solenoid Oper. Valve
. Target Rock VG-22A QM,QT,H,A Solenoid Oper. Valve Target Rock VG-33 QM,QT,H,A Solenoid Oper. Valve Target Rock VG-26 QM,QT,H,A Solenoid Oper. Valve Target Rock VG-98 QM,QT,H,A i
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Appendix B (Continued)
Equipment Description Manufacturer Component No.
Deficiency i
Solenoid Oper. Valve Target Rock VG-128 QM,QT,H,A Solenoid Oper. Valve Target Rock VG-22B QM,QT,H,A Solenoid Oper. Valve Target Rock VG-34 QM,QT,H,A Solenoid Oper. Valve Target Rock VG-75A3 QM,QT,H,A Solenoid Oper. Valve Target Rock VG-11A QM,QT,H,A Solenoid Oper. Valve Target Rock VG-13A QM,QT,H,A Solenoid Oper. Valve Target Rock VG-24 QM,QT,H,A Solenoid Oper. Valve Target Rock VG-75A4 QM,QT,H,A Solenoid Oper. Valve Target Rock VG-118 QM,QT,H,A Solenoid Oper. Valve Target Rock VG-138 QM,QT,H,A Solenoid Gper. Valve Target Rock VG-25 QM,QT,H,A Solenoid Oper. Valve Atkomatic F50-109-7581 QM,qT,T,P, H,A Solenoid Oper. Valve Atkomatic FS0-109-75C1 QM,QT,T,P, H,A Solenoid Oper. Valve Atkomatic FS0-109-75D1 QM,QT,T,P, H,A Solenoid Oper. Valve Atkomatic FS0-109-7582 QM,QT,T,P, H,A Solenoid Oper. Valve Atkomatic FS0-109-75C2 QM,QT,T,P, H,A Solenoid Oper. Valve Atkomatic F50-109-7502 QM,QT,T,P, H,A
, Pressure Transmitter Rosemount PT-VG-4A QM,QT,A Pressure Transmitter Rdsemount PT-VG-4B QM,QT,A l
H Analyzer Delphi SAH-VG-5 QM,QT,A,T 2
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Appendix B (Continued)
Equipment I
Description Manufacturer Component No.
Deficiency Solenoid Oper. Valve Atkomatic FS0-109-75A1 QM,QT,T,P, H,R,A Solenoid Oper. Valve Atkomatic FS0-109-75A2 QM,QT,T,P, H,R,A Motor GE P46-1A QI i
Motor GE P46-1B QI Motor Operator Limitorque MOV-14-11A QI L
Motor Operator Limitorque MOV-14-118 QI Motor Operator Limitorque MOV-14-12A QI Motor Operator Limitorque MOV-14-12B QI Motor Operator Limitorque MOV-14-26A QI Motor Operator Limitorque MOV-14-26B QI Motor Control Center Westinghouse MCC-8E QI Motor Control Center Westinghouse MCC-90 QI Motor Control Center ITE MCC-89A QI Motor Contcol Center ITE MCC-89B QI Uninterruptible Power Sys.
Exide UPS-1A QI Uninterruptible Power Sys.
Exide UPS-1B QI Power Palel GE PP-89 QI I
Motor Generator Set GE MG-2-1A QI Motor Ccntrol Center Westinghouse MCC-98 QI Motor Cuntrol Center Westinghouse DC-2A QI Motor Control Center Westinghouse DC-1A QI Motor Control Center Westinghouse DC-18 QI Motor Control Center' Westinghouse DC-2B QI B-3
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Appendix B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Power Panel Westinghouse LT-ITA QI Motor Allis-Chalmers RRU-5 QM,QT,T,P,H,R,A Motor Allis-Chalmers RRU-7 QM,QT,T,P,H,R,A Motor Allis-Chalmers RRU-8 QM,QT,T,P,H,R,A Motor Allis-Chalmers RRU-6 QM,QT,T,P,H,R,A Motor Operator Limitorque MOV-23-15 QM,QT,T,P,H,R,A Motor Operator Limitorque MOV-23-16 QI Motor Operator Limitorque MOV-23-19 QI Pressure Switch Barksdale PS-23-68A QM,QT,R,A Pressure Switch Barksdale PS-23-688 QM,QT,R,A Pressure Switch Barksdale PS-23-68C QM,QT,R,A Pressure Switch Barksdale PS-23-68D QM,QT,R,A i
Flow Transmitters GE/MAC PT-23-82 QM,QT,H,R,A Pressure Switch Barksdale PS-23-84 QM,QT,R,A Pressure Switch Barksdale PS-23-97A QM,QT,R,A Pressure Switch Barksdale PS-23-978 QM,QT,R,A Local Controls Terry QI i
Motor Operator Limitorque MOV-23-14 QI Motor Operator Limitorque MOV-23-24 QI Motor Operator Limitorque MOV-23-17 QI Motor Operator Limitorque MOV-23-57 QI Motor Operator Limitorque H0V-23-20 QI Motor Operator Limitorque MOV-23-58 QI Motor Operator Limitorque MOV-23-21 QI l
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Appendix B (Continued)
Equipment Descriptioq_____
Manufacturer Component No.
Deficiency Solenoid Valve ASCO 23-50A RPN Motor Operated Valve Limitorque MOV-2-74 QM,QT,R,A Pressure Switch Barksdale PS-2-3-52A QM,QT,,R,A Pressure Switch Barksdale PS-2-3-52C QM,QT,R,A Pressure Switch Barksdale PS-2-3-53A QM,QT,R,4 Pressure Switch Barksdale PS-2-3-538 QM,QT,R,A Relief Valve Pos. Mon.
GE DWG #11201043G005 QI Pressure Switch Static-0-Ring PS-2-71A QI Pressure Switch Static-0-Ring PS-2-72B QI Pressure Switch Static-0-Ring PS-2-73C QI Pressure Switch Static-0-Ring PS-2-72A QI Pressure Switch Static-0-Ring PS-2-738 QI Pressure Switch Static-0-Ring PS-2-710 QI Pressure Switch Static-0-Ring PS-2-73A QI Pressure Switch Static-0-Ring PS-2-71C QI Pressure Switch Static-0-Ring PS-2-720 QI Pressure Switch Static-0-Ring PS-2-718 QI Pressure Switch Static-0-Ring PS-2-72C QI Pressure Switch Static-0-Ring PS-2-730 QI Thermocouple Assembly Thermoelectric TE-16-19-30 QI Acoustic Transmitter B&W QI Acoustic Accelerometer B&W QI Radiation Detector Victoreen RD-16-19-1A QI Radiation Detector Victoreen RD-16-19-1B QI B-5 1
i Appendix B (Continued)
Equipment
'Jescription Manufacturer Component No.
De*iciency Level Transmitter GE LT-16 '.9-38A QI Level Transmitter GE LT-16-19-388 QI Temperature Element The rmo-TE-16-19-33A QI Electric Temperature Element Thermo-TE-16-19-33C QI Electric i
Pressure Transmitter GE PT-6-53A QM,QT,R,A Pressure Transmitter GE PT-6-538 QM,QT,R,A Level Transmitter Rosemount LT-16-19-10A QM,QT,R,A Level Transmitter Rosemount LT-16-19-10B QM,QT,R,A Level Switch Yarway LITS-2-3-73A QM,QT,A Level Switen Yarway LITS-2-3-73B QM,QT,A Pressure Transmitter GE PT-16-19-23 QI Temperature Element Thermo-TE-16-19-34 QI Electric Pressure Transmitter GE PT-16-19-36 QI Temperature Element Thermo-TE-1-149-1 QI Electric Solenoid Oper. Valve ASCO FCV-2-39 QM,QT,A Solenoid Oper. Valve ASCO FCV-2-40 RPN Solenoid Pilot Valve ASCO 16-19-11A RPN Solenoid Pilot Valve ASCO 16-19-118 RPN Pressure Switch Barton dPIS-16-19-32A QM,QT,A Pressure Switch Barton dPIS-16-19-32B QM,QT,A Sensor GE 17-430A QI Sensor GE 17-430B QI B-6 l
e
'O Appendix B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Sensor GE 17-431A QI Sensor GE 17-4318 QI Motor Operator Limitorque MOV-13-15 QM,QT,R,A Motcr Operator Limitorque MOV-13-16 QI Pressure Switch Barksdale PS-13-72A QM,QT,R.A Pressure Switch Barksdale PS-13-67A QM,QT,R,A Pressure Switch Barksdale PS-13-728 QM,QT,R,A Pressure Switch Barksdale PS-13-678 QM,QT,R,A Pressure Switch Barksdale PS-13-87A QM,QT,R,A Pressure Switch Barksdale PS-13-878 QM,QT,R A Pressure Switch Barksdale PS-13-87C QM,QT,R,A Pressure Fwitch Barksdale PS-13-870 QM,QT,R,A Flow Transmitter GE FT-13-58 QI Local Controls Terry QI Motor Operator Limitorque MOV-2-53A QM,QT,R,A Motor Operator Limitorque MOV-2-53B QM,QT,R,A Motor Operator Limitorque MOV-2-54A QM,QT,R,A Motor Operator Limitorque MOV-2-54B QM,QT,R,A Motor Operator Limitorque MOV-2-66A QM,QT,R,A Motor Operator Limitorque MOV-2-668 OMfT,R,A Motor Operator Limitorque MOV-12-15 QM,QT,R.A Motor Operator Limitorque MOV-12-18 R,A Mott,r Operator Limitorque MOV-10-18 QM,QT,R,A Motor Operator Limitorque MOV-10-32 QM,QT,R,A B-/
i Appendix B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Motor Operator Limitorque MOV-10-27A QM,QT,R,A Motor Operator Limitorque MOV-10-31A QM,QT,R,A Motor Operator Limitorque MOV-10-13C QM,QT,R A Mo+.or Operator Limitorque MOV-10-15C Qw,QT,R,A Motor Operator Limitorque MOV-10-278 QM,QT,R,A Motor Operator Limitorque MOV-10-31B QM,QT,R,A Motor Operator Limitorque MOV-10-13D QM,QT,R,A Motor Operator Limitorque MOV-10-15D QM,QT,R,A Motor Operator Limitorque MOV-10-26A QM,QT,R,A Motor Operator Limitorque MOV-10-13A QM,QT,R,A Motor Operator Limitorque MOV-10-15A QM,QT,R,A Motor Operator Limitorque MOV-10-268 QM,QT,R,A Motor Operator Limitorque MOV-10-138 QM,QT,R,A Motor Operator Limitorque MOV-10-158 QM,QT,R,A Motor GE P10-1A QM,QT,T,P,H,R,A Motor GE P10-18 QM,QT,T,P.H,R,A Motor GE P10-1C QM,QT,T,P,H,R,A Motor GE P10-10 QM,QT,T,P,H,R,A Motor Westinghouse P8-1A QM,QT,T,A Motor Westinghouse P8-1B QM,QT,T,A Motor Westinghouse P8-1C QM,QT,T,A Motor Westinghouse P8-1D QM,QT,T,A s
Motor Operator Limitorque MOV-10-25A QM,QT,R,A Motor Operator Limitorque MOV-10-25B QM,QT,R,A 1
,i B-8 i
t
i Appendix B (Continued)
(
Equipment Description Manufacturer Component No.
Deficiency i
Motor Operator Limitorque MOV-10-17 QI Motor Operator Limitorque MOV-10-38A QM,QT,R,A Motor Operator Limitorque MOV-10-57 QM,QT,R,A i
Motor Operator Limitorque MOV-10-89A QM,QT,R,A l
Motor Operator Limitorque MOV-10-38B QM,QT,R,A Motor Operator Limitorque MOV-10-65A QM,QT,R,A Motor Operator Limitorque MOV-10-898 QM,QT,R,A Motor Operator Limitorque MOV-10-39A QM,QT,R,A Motor Operator Limitorque MOV-10-658 QI,QT,R,A Motor Operator Limitorque MOV-10-183 QM,QT,R,A Motor Operator Limitorque MOV-10-39B QM,QT,R,A Motor Operator Limitorque MOV-10-66 QM,QT,R,A I
Motor Oper.cor Limitorque MOV 184 QM,QT,R,A t
Fan Moto -
Allis-Chalmers REF-2A QI t
Fan Motor Allis-Chalmers REF-28 QI Solenoid ASCO SB-2A RPN Solenoid ASCO SB-2B RPN I
Solenoid ASCO SB-3A RPN Solenoid ASCO SB-3B RPN Solenoid ASCO SB-4A RPN Solenoid ASCO SB-4B RPN Solenoid ASCO SB-5 RPN Limit Switch NAMCO A0V-2-86A QM,QT,A 1
Limit Switch NAMCO A0V-2-86B QM,QT,A B-9 i
Appendix B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Limit Switch NAMCO A0V-2-86C QM,QT,A Limit Switch NAMCO A0V-2-860 QM,QT,A Thermocouple Lewis TE-16-19-30 QM,QT,T,A Engineering Power Cable Rome Cable Generick QM,QT,A Penetration Assembly GE Generick QM,QT,A Terminal Blocks Buchanan Generick QM,QT,A Power Cable Rome Cable XLP/PVC QM,QT,T,P,H,R,A Power Cable Kerite Generick QM,QT,A Power Cable Collyer P46-1A QM,QT,T,P,H,R,A Power Cable Collyer P46-1B QM,QT,T,P,H,R,A Control Cable Rome XLP/PVC/PVC QM,QT,T,P,H,R,A Terminal Block States Type NT QM,QT,R,A Terminal Block States A0V-2-86A QM,QT,R,A Terminal Bicek States A0V-2-86B QM,QT,R,A Terminal Block States A0V-2-86C QM,QT,R,A Terminal Block States A0V-2-86D QM,QT,R,A Instrument Cable Boston Generick QM,QT,T,P,H,R,A Insulated Wire Co.
i w
f B-10 i
e
APPENDIX C Equipment Considered Acceptable or Conditionally Acceptc51e (Category 4.3)
LEGEND:
R - Radiation T Temperature QT Qualification time RT Required time P Pressure H Humidity CS Chemical spray A Material aging evaluation, replacement schedule, ongoing equipment surveillance S Submergence M Margin I HELB evaluation outside containment not completed QM Qualification method RPN Equipment relocation or replacement, adequate schedule not provided EXN Exempted equipment justification inadequate SEN Separate effects qualification justification inadequate QI Qualification information being developed RPS Equipment relocation or replacement schedule provided Equipment Description Manufacturer Component No.
Deficiency Solenoid Oper. Valve ASCO RV-2-71A A
Solenoid Oper. Valve ASCO RV-2-718 A
Solenoid Oper. Valve ASCO RV-2-71C A
Solenoid Oper. Valve ASCO RV-2-710 A
Temperature Switch Fenwall TS-23-101A A
Temperature Switch Fenwall TS-23-102A A
Temperature Switch Fenwall TS-23-103A A
Temperature Switch Fenwall TS-23-104A A
Temperature Switch Fenwall TS-23-101-B A
Temperature Switch Fenwall TS-23-102-B A
C-1 k
Appendix 0 (Continued)
Equipment i
Description Manufacturer Component No.
Deficiency Temperature Switch Fenwall TS-23-103-B A
Temperature Switch Fenwall TS-23-104-8 A
Temperature Switch Fenwall TS-23-101-C A
Temperature Switch Fenwall TS-23-102-C A
Temperature Switch Fenwall TS-23-103-C A
Temperature Switch Fenwall TS-23-104-C A
Temperature Switch Fenwall TS-23-101-D A
I Temperature Switch Fenwall TS-23-102-D A
Temperature Switch Fenwall TS-23-103-D A
i Temperature Switch Fenwall TS-23-104-0 A
~
Solenoid Oper. Valve ASCO A0V-2-80A A
Solenoid Oper. Valve ASCO A0V-2-80B A
Solenoid Oper. Valve ASCO A0V-2-80C A
Solenoid Oper. Valve ASCO A0V-2-80D A
Solenoid Oper. Valve ASCO A0V-2-86A A
Solenoid Oper. Valve ASCO A0V-2-86B A
Solenoid Oper. Valve ASCO A0V-2-86C A
Solenoid Oper. Valve ASCO A0V-2-860 A
Pressure Switch Barton PS-2-3-52B A
Pressure Switch Barton PS-2-3-520 A
l Level Transmitter Rosemount LT-2-3-72A A
Level Transmitter Rosemount LT-2-3-728 A
Level Transmitter Rosemount LT-2-3-72C A
l Level Transmitter Rosemount LT-2-3-72D A
i C-2
Appendix C (Continued).
Equipment Description Manufacturer Component No.
Deficiency Temperature Switch Fenwall TS-13-79-A A
Temperature Switch Fenwall TS-13-80-A A
Temperature Switch Fenwall TS-13-81-A A
Temperature Switch Fenwall TS-13-82-A A
Temperature Switch Fenwall TS-13-79-B A
Temperature Switch Fenwall TS-13-80-B A
Temperature Switch Fenwall TS-13-81B A
Temperature Switch Fenwall TS-13-828 A
Temperature Switch Fenwall TS-13-79C A
Temperature Switch Fenwall TS-13-80C A
Temperature Switch Fenwall TS-13-81C A
Temperature Switch Fenwall TS-13-82C A
Temperature Switch Fenwall TS-13-790 A
Temperature Switch Fenwall TS-13-800 A
Temperature Switch Fenwall TS-13-81D A
Temperature Switch Fenwall TS-13-820 A
Differential PIS Barton dPIS-13-83 A
Differential PIS Barton dPIS-13-84 A
Limit Switch NAMCO A0V-2-80A A
Limit Switch NAHC0 A0V-2-80B A
Limit Switch NAMCO A0V-2-80C A
Limit Switch NAMCO A0V-2-80D A
Control Cable Rockbestos A0V-2-80A A
Control Cable Rockbestos A0V-2-808 A
C-3
Y Appendix C (Continued)
Equipment Description Manufacturer Component No.
Deficiency Control Cable Rockbestos A0V-2-80C A
Control Cable Rockbestos A0V-2-800 A
\\
1 l
i C-4 1
APPENDIX D Safety-Related Systems Listl Function System l
Emergency Reactor Shutdown Reactor Protection Engineered Safeguards Actuation Standby Liquid Control
(
Containment Isolation Main Steam Reactor Water Cleanup Primary Containment Atmospheric Control Sampling Residual Heat Removal Drywell Sump Discharge Peactor Core Isolation Cooling Containment Isolation 2 t
Reactor Core Cooling High Pressure Coolant Injection Low Pressure Coolant Injection Automatic Depressurization Core Spray "antainment Heat Removal Containment Spray Residual Heat Removal Service and Cooling Water Core Residual Heat Removal Residual Heat Removal Reactor Core Isolation Cooling Service and Cooling Water Standby Coolant Supply Prevention of Significant Containment Atmospheric Dilution Release of Radioactive Post Accident Monitoring Material to Environment Post Accident Sampling Standby Gas Treatment Primary Containment and Atmospheric Control Supporting Systems Emergency Power Heating and Ventilation 1The NRC staff recognized that there are differences in nomenclature of systems because of plant vintage and engineering design; consequently some systems performing identical or similar functions may have different names.
In those instances it was necessary to verify the system (s) function with the responsible IE regional reviewer and/or the licensee.
20ther systems with isolation valves covered by engineered safeguards actuation system.
D-1 p
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