ML20004C186
| ML20004C186 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/21/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004C182 | List: |
| References | |
| IEB-79-01B, IEB-79-1B, NUDOCS 8106010709 | |
| Download: ML20004C186 (27) | |
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1-i SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT QUALIFICATION BRANCH 4
FOR WISCONSIN ELECTRIC POWER COMPANY POINT BEACH UNITS 1 AND 2 l
DOCKET NO. 50-266/301 l
l 8106 01 o}Q
1 CONTENTS Page 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...................................
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3.5 Submergence...........................................
5 l
3.6 Chemical Spray........................................
5 3.7 Aging.................................................
5 3.8 Radiation (Inside and Outside Containment)............
6 4
Qualification of Equipment................................
6 4.1 Equipment Requiring Immediate Corrective Action.......
7 4.2 Equipment Requiring Additional Information and/or Corrective Action.....................................
7 4.3 Equipment Considered Acceptable or Conditionally Acceptable............................................
8 5
Deferred Requirements......................................
9
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6 Conclusions................................................
9 APPENDIX A Equipment Requiring Immediate Corrective Action..
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APPENDIX B Equipment Requiring Arfditional Information and/or Corrective Action................................
B-1 APPENDIX C Equipeent Considered Acceptable or Conditionally Acceptable.......................................
C-1 APPENDIX 0 Safety-Related Systems List......................
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SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT QUALIFICATION BRANCH FOR WISCONSIN ELECTRIC POWER COMPANY POINT BEACH UNITS 1 AND 2 DOCKET NO. 50-266/301 I
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-rc-lated function under cnvironmental 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 On February 8,1979, the NRC Office of Inspection and Enforcement (IE) issued to all licensees of operating plants (except thoce 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.
l Subsequently, Commission Memorandum and Order CLI-80-21 (issued on May 23, l
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 opera-ting 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 definition 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 licensees.
The August order required that
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the licensees provide a report, by November 1, 1980, documenting the qualifica-I tion 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 equipment be qualified by June 30, 1982.
In response, the licensee submitted l
information through letters dated April 18, September 12, and October 30, 1980.
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2.1 Purpose The purpose of this SER is to identify equipeent whose qualification program does not provide sufficient assurance that the equipment is capable of per-forming the design function in hostile environments.
The staff position relating to 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 the consequences of a loss-of-coolant accident (LOCA) or a high-energy-line-break (HELB) accident, inside or outside containment, while subjected to the hostile environments associated with these accidents.
3 STAFF EVALUATION 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 licensee's qualification program.
The NRC Office of Inspection and Enforcement performed (1) a preliminary l
evaluation of the licensee's response, documented in a technical evaluation j
report (TER) and (2) an onsite verification inspection (April 21, 1980 for i
Units 1 and 2 and October 10, 1980 for Unit 1) of selected safety-related elect >ical equipment. Components of the residual heat removal (RHR) and component cooling water (CCW) systems of Unit 1 were inspected, and components of safety injection systems of Units 1 and 2 were inspected.
The inspection at both units 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 given in the Component Evaluation Work Sheets (CES) of the licensee's report. _The site inspections are documented in letters dated April 24, 1980 from F. J. Jablonski (Region III) to V. D. Thomas (IE) and October 21, 1980 from D. W. Hayes (Region III) to E. L. Jordan (IE). Deficiencies outlined in these letters included a lack of plant equipment identification numbers and nameplate data that did not correspond to the CES. Additionally, pump and valve motors of i
I the safety injection and containment spray systems of both Units 1 and 2 are l
located in the same room without sufficient separation.
The staff believes that this arrangement is not consistent with the separation criteria; therefore, the licensee should address this situation.
For this review, the documents referenced above have been factored into the overall staff evaluation.
l 3.1 Completeness of Safety-Related Equipment In accordance with IEB 79-018, the licensee was directed to (1) establish a list of systems and equipment that are required to mitigate a LOCA and an HELB and (2) identify components needed to perform the function of safety-related display information, post-accident sampling and monitoring, and radiation monitoring.
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e The staff developed a generic mater list based upon a review of plan' safety analyses and emergency procedures.
The 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).
The list of safety-related systems provided by the licensee was reviewed against the staff-developed master list.
Based on the licensee's submittal, the staff has concluded that the information on safety-related systems included in the submittal is insufficient to verify that those systems are all the systems 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 significant release of radioactive material to the environment. The staff acknowledges the licensee's effort to include only those safety-related systems located in a potentially harsh environment.
However, this review requires the listing of all safety-related systems, both inside and outside potentially harsh environments. The list of safety-related systems submitted by the licensee is included in Appendix D.
Display instrumentation which provides information for the reactor operators to aid them in the safe handling of the plant was not specifically identified by the licensee. A complete list of all display instrumentation mentioned in the LOCA and HELB emergency procedures must be provided.
Equipment qualifi-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 sub-l sequent failure will not mislead the operator or adversely affect the miti-I gation of the consequences of the accident.
The environmental qualification l
of post-accident sampling and monitoring and radiation monitoring equipment is closely related to the review of the TMI Lessons-Learned mcdifications and will be performed in conjunction with that review.
The licensee ideatified 234 items of equipment which were assessed by the staff.
Because Units 1 and 2 are nearly identical, the review can be per-formed as one. Uhere necessary, differences in the units will be noted for clarity.
3.2 Service Conditions Commission Memorandum and Order CLI-80-21 requires that the 00R 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 in the licensee's Final Safety Analysis Report (FSAR) or based on generic profiles using the methods identified in these documents..
e e
On this basis, the staff has assumed, unless otherwise noted, that the analysis for developing the environmental envelopes for Point Beach Units 1 and 2, 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 Component Evaluation Work Sheets to ensure that the qualification data envelope the specifications 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 main steam-line-break (MSLB) environmental conditions are enveloped by the large-break-LOCA environmental conditions.
The staff assumed, and requires the licensee to verify, that the containment spray system is not subjected to a disabling single-component failure and therefore satisfies the requirements of Section 4.2.1 of the D0R guidelines.
Equipment submergence has also been addressed where the possibility exists that flooding of equipment may result from HELBs.
3.3 Temperature, Pressure, and Humidity Conditions Inside Cont ainment i
The licensee has provided the results of accident analyses as follows:
Max Temp (*F)
Max Press (psig)
Humidity (%)
LOCA 278 53 not provided MSLB not provided not provided not provided The staff has concluded that the minimum temperature profile for equipment qualification purposes should include a margin to account for higher-than-average temperatures in the upper regions of the containment that can exist due to stratification, especially following a postulated MSLB.
Use of the
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steam saturation temperature corresponding to the total building pressure (partial pressure of steam plus partial pressure of air) versus time will provide an acceptable margin for either a postulated LOCA or MSLB, whichever is controlling as to potential adverse environmental effects on equipment.
The licensee's specified temperature (service condition) of 278 F does not satisfy the above requirement. A saturation temperature corresponding to the l
peak profile (301*F peak temperature at 53 psig) should be used instead. The licensee should update his equipment summary tables to reflect this change.
If there is any equipment that does not meet the staff position, the licensee must provide either justification that the equipment will perform its intended function under the specified conditions or propose corrective action.
The licensee has provided service condition pressure and temperature profiles for the containment and an assortment of components.
The staff assumed that the containment service condition prsfiles in the licensee's October 30, 1980 submittal are for a LOCA. However, for this review, the licensee should specify the relative humidity associated with each profile and provide service condition profiles--including pressure, temperature, and humidity--for all areas subject to a potential HELB.
In addition, room numbers or other applicable designation should be used to specify the area to which each profile applies.
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s 3.4 Temperature, Pressure, and Humidity Conditions Outside Containment The licensee should provide service condition profiles for all areas outside containment subject to a potential HELB, as stated in Section 3.3 of this report.
3.5 Submergence 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 criteria as established by Commission Memorandum and Order CLI-80-21.
The licensee's value for maximum submergence is 14 ft 10 in. The licensee has identified three solenoid valves and three limit switches as having the potential for becoming submerged after a postulated event. The licensee stated that this equipment will perform its safety function before becoming submerged.
In this case, the licensee should provide an assessment of the failure modes associated with the submergence of these components. The licensee should also provide assurance that their subsequent failure will not adversely affect any other safety functions or mislead an operator. Additionally, the licensee should discuss operating time, across the spectrum of events, in relation to the time of submergence.
If the results of the licensee's assessment are acceptable, then these components may be exempt from the submergence parameter of qualification.
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 tne CES as appropriate.
3.6 Chemical Spray The licensee's values for chemical sprays, as specified on the CES, are 8 B0 -Na0H solution:
pH 7.9-10.0.
For this review, the exact chemical 3 3 concentration of boric acid and sodium hydroxide used in qualification testing should be discussed.
Therefore, the effects of chemical spray will be con-l sidered unresolved.
The staff will review the licensee's response when it is I
submitted and discuss the resolution in a supplemental report.
3.7 Aging Section 7 of the 00R guidelines does not require a qualified life to be estab-lished for alI safety-related electrical equipment. However, the following actions are required:
(1) Make a detailed comparison of existing equipment and the materials identi-fied 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 'nstalled components.
The licensee identified a number of equipment items for which a specified qualified life was established (for example, 7 years, 10 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 identify and verify 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 staff will review the licensee's response when it is submitted md 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 00R guidelines, in NUREG-0588, and in the guidance provided in IEB-79-01B, Supplement 2.
Therefore, for this review, the staff has assumed that, unless otherwise noted, the values provided have been determined in accordance with the prescribed criteria. 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 of 5.8 x 107 rads. This value envelopes the 00R guideline requirements and is therefore acceptable.
A required value outside containment of 6.51 x 106 rads has been used by the licensee to specify limiting radiation levels in the vicinity of the safety injection system in the auxiliary building.
This value appears to consider the radiation levels influenced by the source term methodology associated with recirculation fluid lines and is therefore acceptable.
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4 QUALIFICATION OF EQUIPMENT l
The following subsections present the staff's assessment, based on the licensee'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 valuas 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 nas I
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 will 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-l cation or replace the item (s) of concern. This effort will begin in early 1981.
An appendix for each subsection of this report provides a list of equipment l
for which additional information and/or corrective action is required. Where l
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.
4.1 Equipment Requiring Immediate Corrective Action 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 information 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 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
e 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.
(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 (2b) Subsequent 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) Equipment will not be subjected to a harsh environment as a result of the postulated accident.
The licensee is, therefore, required to supplement the information presented by providing resolutions to the deficiencies identified; these resolutions should include a description of the corrective action, schedules fo" its completion (as applicable), and so forth. The staff will review the scensee's response, when it is nubmitted, and discuss the resolutian in a supplemental report.
It should be noted that in cases where testing is being conducted, a condition I
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 l
Based on the staff review of the licensee's submittal, the staff identified the equipment in Appendix C as (1) acceptable on the basis that the qualifi-i 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 conducted to ensure that l
no known materials susceptible to degradation because of aging have been
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n (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-mitted and discuss the resolution in a supplemental report.
5 DEFERRED REQUIREMENTS IEB 79-01B, Supplement 3 has relaxed the time constraints for the ubmission of the information associated with cold shutdown equipment and TMI lessons-learned modifications.
The staff has required that this information be provided by February 1, '.981.
The staff will provide a supplemental safety evalusi.fon 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 are appropriate, except as noted in Section 3 of this report. Outstandim information identified in Section 3 should be provided within 90 days of receipt of this SER.
I 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 he licensee for this review do not have adequate documentation to ensure that they are capable of withstanding the harsh environmental service conditions.
This review was based on a comparison of the qualification values with the specified environmental values required l
l by the design, which were provided in the licensee's summary sheets.
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Subsection 4.2 identified deficiencies that must be resolved to establish the I
qualification of the equipment; the staff requires that the information lack-ing in this category be provided within 90 days of receipt of this SER.
l 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,
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the licensee must provide justification for operation until such corrective action is complete.
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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 opera-tion of the facility would be impacted in consideration of the dsficiencies.
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 thi:e is reasonable assurance 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 deficient 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 l
reasonably be anticipated during this very limited period would lead to less demanding service conditions for this equipment.
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i APPENDIX A Equipment Reguiring Imediate Corrective Action (Category 4.1) i tquipment Description Manufacturer Component No.
No equipment in this category l
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an A-1
e a
APPENDIX B Equipment Requiring Additional Information and/or Corrective Action (Category 4.2)
LEGEND:
Designation for Deficiency R - Radiation T - Temperature i
QT - Qualification Time RT - Required Time P - Pressure H - Humidity CS - Chemical spray A - Material aging evaluation, reolacement schedule, ongoing equipment surveillance S - Submergence M - Margin I - HELB evaluation outside containment not completed QM - Qualification method RPN - Equipment relocation or replacer.ent, adequate schedule not provided EXN - Exempted equipment justification inadequate SEN - Separate effects qualification justification inadequate QI - Qualification information being developed RPS - Eq':ipment relocation or replacement schedule provided Equipment Description Manufacturer Component No.
Deficiency 480 Motor AC Westin3 house 1-P14A A,QT,T 480 Motor AC Westinghouse 1-P148 A,QT,T 480 Motor AC Westinghouse 2-P14A A,QT,T t
480 Motor AC Westinghouse 2-P14B A,QT,T 4160 Motor AC Westinghouse 1-P15A A,QT,T 4160 Motor AC Westinghouse 1-P15B A,QT,T 4160 Motor AC Westinghouse 2-P15A A,QT,T 4160 Motor AC Westinghouse 2-P15B A,QT,T Valve Motor Limitorque 1-S1851A A,QT,T B-1 I
a APPENDIX B (Continued)
Equipment Description Manufacturer Component No.
Deficier.cy Valve Motor Limitorque 1-51851B A,QT,T Valve Motor Limitorque 2-S1851A A,QT,T Valve Motor Limitorque 2-518518 A,QT,T Valve Motor Limitorque 1-51871A A,T Valve Motor Limitorque 1-51871B A,T Valve Motor Limitorque 2-51871A A,T Valve Motor Limitorque 1-51871B A,T Valve Motor Limitorque 1-51860A A,T Valve Motor Limitorque 1-S18608 A,T Valve Motor Limitorque 2-51860A A,T Valve Motor Limitorque 2-518608 A,T Valve Motor Limitorque 1-S1852A A,T,P,H Valve Motor Limitorque 1-S1852B A,T,P,H Valve Motor Limitorque 2-51852A A,T,P,H l
Valve Motor Limitorque 2-518528 A,T,P,H Valve Motor Limitorque 1-518788 A,T,P,H Valve Motor Limitorque 1-S18780 A,T,P,H Valve Motor Limitorque 2.-51878B A,T,P,H Valve Motor Limitorque 2-518780 A,T,P,H Electro-Pneumatic Fisher Co.
1-S1836A QT,A Transducers Electro-Pneumatic Fisher Co.
1-S1836B QT,T,H,A Transducers Electro-Pneumatic Fisher Co.
2-51836A QT,T,H,A Transducers B-2
APPENDIX B (Continued) i Equipment Description Manufacturer Component No.
Deficiency Electro-Pneumatic Fisher Co.
2-S1836B QT,T,H,A Transducers Limit Switch NAMCO (D2400X) 1-S1836A RPN,A Limit Switch NAMC0 (02400X) 1-51836B RPN,A Liinit Switch NAMCO (02400X) 2-S1836A RPN,A 4
Limit Switch NAMCO (02400X) 2-S1836B RPN,A Pressure Transmitter Foxboro (511GM) 1-PT922 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT923 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT922 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT923 RPN,A Flow Transmitters Barton (333) 1-FT924 RPN,A Flow Transmitters Barton (333) 1-FT925 RPN,A Flow Transmitters Barton (333) 2-FT924 RPN,A Flow Transmitters Barton (333) 2-FT925 RPN,A Flow Transmitters Barton (295) 1-FT928 RPN,A Flow Transmitters Barton (295) 2-FT928 RPN,A j
Level Transmitters Barton (332) 1-LT931 RPN,A Level Transmitters Barton (332) 2-LT931 RPN A l
Level Switches Magnetrol 1-LC942A RPN,A (A153) i Level Switches Magnetrol 1-LC942B RPN,/.
(A153)
Level Switches Magnetrol 1-LC943A RPN,A (A153)
Level Switches Magnetrol 1-LC943B RPN,A (A153) l B-3
- +, - - -
y
_,_,,,,v v.- _,
..4 4
m --
.~..
APPENDIX B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Level Switches Magnetrol 2-LC942A RPN,A (A153)
Level Switches Magnetrol 2-LC9428 RPN,A (A153)
Level Switches Magnetrol 2-LC943A RPN,A (A153)
Level Switches Magnetrol 2-LC943B RPN,A (A153)
Oil (51 Motors)
American Oil 1-P15A QT,H,A Co. (#35)
Oil (51 Motors)
American Oil 1-P15B QT,H,A Co. (#35)
Oil (S1 Motors)
American Oil 2-P15A QT,H,A Co. (#35)
Oil (S1 Motors)
American Oil 2-P158 QT,H,A Co. (#35)
Pump Motors Westinghouse 1-P10A QT,A,H Pump Motors Westinghouse 1-P108 QT,A,H Pump Motors Westinghouse 2-P10A QT,A,H Pump Motors Westinghouse 2-P108 QT,A,H Pump Motors Westinghouse 1-P11A QT,H,R,A,T Pump Motors Westinghouse 1-P11B QT,H,R,A,T Pump Motors Westinghouse 2-P11A QT,H,R,A,T Pump Motors Westinghouse 2-P118 QT,H,R,A,T Valve Motor Limitorque 1-AC738A QT,A Valve Motor Limitorque 1-AC7388 QT,A Valve Motor Limitorque 2-AC738A QT,A Valve Motor Limitorque 2-AC738B QT,A B-4 I
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APPENDIX B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Electro-Pneumatic Fisher (546) 1-AC624 QT,H,A Transducers Electro-Pneumatic Fisher (546) 1-AC625 QT,H,A Transducers Electro-Pneumatic Fisher (546) 2-AC624 QT,H,A Transducers l
Electro-Pneumatic Fisher (546) 2-AC625 QT,H,A Transducers Electro-Pneumatic Fisher (546) 1-AC626 QT,H,A Transducers Electro-Pneumatic Fisher (546) 2-AC626 QT,H,A t
Transducers Limit Switches NAMCO (D2400X) 1-AC624 RPN,A Limit Switches NAMCO (D2400X) 1-AC625 RPN,A Limit Switches NAMC0 (02400X) 2-AC624 RPN,A Limit Switches NAMCO (D2400X) 2-AC625 RPN,A Limit Switches NAMCO (D2400X) 1-AC626 RPN,A Limit Switches NAMCO (D2400X) 2-AC626 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT628 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT629 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT628 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT629 RPN,A ilow Transmitter Foxboro (6130M) 1-FT626 RPN,A Flow Transmitter Foxboro (613DM) 2-FT626 RPN,A Flow Transmitter Foxboro (613DM) 1-FT619 RPN,A Flow Transmitter Foxboro (613DM) 2-FT619 RPN,A 8-5
APPENDIX B (Continued)
Equipment Description Manufacturer Component No.
Deficiency 011 (Pump)
American Oil 1-P11A QT,H,A
(#21)
Oil (Pump)
American Oil 1-P118 QT,H,A
(#21)
Oil (Pump)
American Oil 2-P11A QT,H,A
(#21)
Oil-(Pump)
American Oil 2-P118 QT,H,A
(#21)
Level Transmitter Foxboro (613DM) 1-LT106 RPN,A Level Transmitter Foxboro (613DM) 1-LT172 RPN,A Level Transmitter Foxboro (613DM) 1-LT190 RPN,A Level Transmitter Foxboro (613DM) 2-LT106 RPN,A Level Transmitter Foxboro (613DM) 2-LT172 RPN,A Level Transmitter Foxboro (613DM) 2-LT190 RPN,A Level Transmitter Foxboro (613DM) LT102 RPN,A Level Transmitter Foxboro (613DM) LT171 RPN,A Level Transmitter Foxboro (613DM) LT189 RPN,A Level Transmitter Foxboro (613DM) 1-LT426 RPN,A i
Level Transmitter Foxboro (613DM) 1-LT427 RPN,A Level Transmitter Foxboro (613DM) 1-LT428 RPN,A Level Transmitter Foxboro (6130M) 1-LT433 RPN,A Level Transmitter Foxboro (613DM) 2-LT426 RPN,A Level Transmitter Foxboro (613DM) 2-LT427 RPN,A l
Level Transmitter Foxboro (613DM) 2-LT428 RPN,A Level Transmitter Foxboro (613DM) 2-LT433 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT429 RPN,A B-6 t
APFENDIX B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Pressure Transmitter Foxboro (611GM) 1-PT430 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT431 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT449 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT429 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT430 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT431 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT449 RPN,A Pressure Transmitter Barton (332) 1-PT945 RPN,A Pressure Transmitter Barton (332) 1-PT946 RPN,A Pressure Transmitter Barton (332) 2-PT945 RPN,A Pressure Transmitter Barton (332) 2-PT946 RPN,A Pressure Transmitter Barton (332) 1-PT947 RPN,A Pressure Transmitter Barton (332) 1-PT948 RPN,A Pressure Transmitter Barton (332) 2-PT947 RPN,A Pressure Transmitter Barton (332) 2-PT948 RPN,A Prescure Transmitter Barton (332) 1-PT949 RPN,A Pressure Transmitter Barton (332) 1-PT950 RPN,A l
Pressure Transmitter Barton (332) 2-PT949 RPN,A l
Pressure Transmitter Barton (332) 2-PT950 RPN,A Pressure Transmitter Foxboro (611GH) 1-PT420 RPN,A Pressure Transmitter Foxboro (611GH) 2-PT420 RPH,A Level Transmitter Foxboro (613HM) 1-LT461 RPN,A Level Transmitter Foxboro (613HM) 1-LT462 RPN,A Level Transmitter Foxboro (613HM) 1-LT463 RPN,A B-7 L
e O
APPENDIX B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Level Transmitter Foxboro (613HM) 2-LT461 RPN,A Level Transmitter Foxboro (613HM) 2-LT462 RPN,A Level Transmitter Foxboro (613HM) 2-LT463 RPN,A Level Transmitter Foxboro (613HM) 1-LT471 RPN,A Level Transmitter Foxboro (613HM) 1-LT472 RPN,A Level Transmitter Foxboro (613HM) 1-LT473 RPN,A Level Transmitter Foxboro (613HM) 2-LT471 RPN,A Level Transmitter Foxboro (613HM) 2-LT472 RPN,A Level Transmitter Foxboro (613HM) 2-LT473 EPN,A Level Transmitter Foxboro (613HM) 1-LT460 RPN,A Level Transmitter Foxboro (613HM) 1-LT470 RPN,A Level Transmitter Foxboro (613HM) 2-LT450 RPN,A Level Transmitter Foxboro (613HM) 2-LT470 RPN,A Pressure Transmitter Foxbo^o (611GM) 1-PT468 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT469 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT482 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT468 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT469 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT482 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT478 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT479 RPN,A Pressure Transmitter Foxboro (611GM) 1-PT483 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT478 RPN,A Pressure Transmitter Foxboro (611GM) 2-PT479 RPN,A B-8
APPENDIX B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Pressure Transmitter Foxboro (611GM) 2-PT483 RPN,A Flow Transmitter Foxboro (630) 1-FT464 RPN,A Flow Transmitter Foxboro (630) 1-FT465 RPN,A Flow Transmitter Foxboro (630) 1-FT474 RPN,A Flow Transmitter Foxboro (630) 1-FT475 RPN,A Flow Transmitter Foxboro (630) 2-FT464 RPN,A Flow Transmitter Foxboro (630) 2-FT465 RPN,A Flow Transmitter Foxboro (630) 2-FT474 RPN,A Flow Transmitter Foxboro (630) 2-FT475 RPN,A 480 VAC Motor Westinghouse 1-W1A1 QT,T,A 480 VAC Motor Westinghouse 1-W181 QT,T,A 480 VAC Motor Westinghouse 1-W1C1 QT,T,A 480 VAC Motor Westinghouse 1-W1D1 QT,T,A 480 VAC Motor Westinghouse 2-W1A1 QT,T,A 480 VAC Motor Westinghouse 2-W181 QT,T,A 480 VAC Motor Westinghouse 2-W1C1 QT,T,A 480 VAC Motor Westinghouse 2-W1D1 QT,T,A Cable Splice Westinghouse 1-W1A1 QT,A,QM l
Cable Splice Westinghouse 1-W181 OT,A,QM Cable Splice Westinghouse 1-WIC1 QT,A,QM Cable Splice Westinghouse 1-W101 QT,A,QM Cable Splice Westinghouse 2-W1A1 QT,A,QM Cable Splice Westinghouse 2-W181 QT,A,QM Cable Splice Westinghouse 2-W1C1 QT,A,QM B-9 s
=.
j APPENDIX B (Continued)
Equipment Description Manufacturer Component No.
Deficiency Cable Splice Westinghouse 2-W1D1 QT,A,QM Solenoid Valve ASCO 1-CV1296 RPN,A (LBX831614)
Solenoid Valve ASCO 2-CV1296 RPN,A (LBX831614)
Solenoid Valve ASCO 1-HC3200C RPN,A (HB8302C25)
Solenoid Valve ASCO 2-HC3200C RPN,A (HB8302C25)
Solenoid Valve ASCO 1-HV3213 RPN,A (8320A7)
Solenoid Valve ASCO 1-HV3245 RPN,A
^ '
(8320A7)
Solenoid Valve ASCO 2-HV3213 RPN,A (8320A7)
Solenofd Valve ASCO 2-HV3245 RPN,A (8320A7)
Limit Switch NAMCO 1-CV1296 QM,A,T,P,H,5 (EA180-11302) 4 Limit Switch NAMC0 2-CV1296 QM,A,T,P,H,5 (EA180-11302)
Limit Switch NAMCO 1-HV32000 QM,A,T,P,H (EA180-11302)
Limit Switch NAMC0 2-HV3200C QM,A,T,P,H (EA180-11302)
Limit Switch NAMC0 1-HV3213 QM,A,T,P,H (EA180-11302)
Limit Switch NAMCO 1-HV3245 QM,A,T,P,H (EA180-11302)
' MMC 0 2-HV3213
. QM,A,T,P,H (iA180-11302)
B-10 t
k
_._-..-,..m.-,---
,._,--_,-,,-.m.,,
APPENDIX B (Continued)
Equipment Description Manufacturer Componant No.
Deficiency Limit Switch IIAMCO 2-HV3245 QM,A,T,P H (EA180-11302)
Liquid Level Foxboro (613DM) LT-4025 RPN,A Liquid Level Foxboro (613DM) LT-4031 RPN,A Power Cable Kerite (600VAC) Generic
Generic
- R,T,QT,P,H,CS,A Power Cable Okonite Generic
- R,T,QT,P,H,A (5000VAC)
Instrument Cable Okonite Generic
- R,T,QT,P,H,A I
Power Cable Rome (600V)
Generic
- R,T,QT,P,H,A Electrical Penetration Crause Hinds /
Generic
- R,A,QT,T,P Assembly Westinghouse l
l l
"The qualification reference in the qualification column was not part of the data package the reviewer had.
I B-11
a APPENDIX C Equipment Considered Acceptable or Conditionally Acceptable (Category 4.3)
Equipment Description Manufacturer Component No.
Deficiency Resistance Temp.
Foxboro 1-TE627 A
Elements Resistance Temp.
Foxboro 1-TE630 A
Elements Resistance Temp.
Foxboro 2-TE627 A
Elements Resistance Temp.
Foxboro 2-TE630 A
Elements Resistance Temp.
Foxboro 1-TE621 A
Elements Resistance Temp.
Foxboro 2-TE621 A
Elements Valve Motor Operator Limitorque 1-MS2019 A
Valve Motor Operator Limitorque 1-MS2020 A
Valve Motor Operator Limitorque 2-MS2019 A
Valve Motor Operator Limitorque 2-MS2020 A
Grease Chevron 1-W1A1 A
(BRB-2)
Grease Chevron 1-W181 A
(BRB-2)
Grease Chevron 1-WIC1 A
(BRB-2) l Grease Chevron 1-W101 A
(BRB-2)
Grease Chevron 2-W1A1 A
(BRB-2) l l
C-1 l
APPENDIX C (Continued)
Equipment Description Manufacturer Component No.
Deficiency Grease Chevron 2-W181 A
(BR8-2)
Grease Chevron 2-WIC1 A
(BRB-2)
Grease Chevron 1-W101 A
l (BR8-2)
Grease American Oil General A
(Amolith #2)
Grease American Oil Valve Motor A
(Amolith #1)
Operator Grease Mobil Oil Valve Motor A
(#28)
Gears Oil American Oil Pump and Motor A
i (Rykon #15)
Bearing Cable Splice Bechtel/Raychem Generic A
(SK-E-165) l l
C-2 i
1
APPENDIX 0 4
Safety-Related Systems Listi Safety Injection Aux'liary Coolant Chemical and Volume Control Reactor Control and Protection Reactor Coolant Main Feedwater (instrumentation only)
Main Steani (instrumentation only)
Containment Air Recirculation Cooling Containment Isolation Auxiliary Feedwater
(
l l
'As submitted by the licensee D-1 f
i