ML20005A924
| ML20005A924 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/05/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20005A921 | List: |
| References | |
| IEB-79-01B, IEB-79-1B, TAC-42512, NUDOCS 8107060038 | |
| Download: ML20005A924 (42) | |
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SAFETY EVALUATION REPORT BY THE i
0FFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT QUALIFICATION BRANCH FOR FLORIDA-POWER CORPORATION i
CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302 i
T'8107060038 81060 DR ADOCK 05000 p
e 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, Pres are, and Humidity Conditions Outside Containment...................................
4 3.5 Submergence...........................................
5
- 3. 6 Chemical Spray........................................
5 3.7 Aging................................................
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- 3. 8 Radiation.............................................
6 4
Qualificatien of Equipment................................
7 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............................................
9 5
Deferred Requirements......................................
9 6
Conclusions................................................
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l APPENDIX A Equipment Requiring Immediate Corrective Action APPENDIX B Equipment Requiring Additional Information and/or Corrective Action APPENDIX C Equipment Considered Acceptable ar Conditionally Acceptable APPENDIX D Safety-Related Systems List Letter from the Foxboro Company dated March 12, 1981, l
regarding the deficiencies in Model Ell and E13 l
transmitters l
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l SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT JUALIFICATION BRANCH FOR FLCRIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 DOCKET NO. 50-302 1
ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT 1 INTRODUCTION-General Design Criteria 1 and 4 specify that safety-related electrical equip-ment in nuclest 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 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-79-018) form the requirements that licensees must meet regarding environmental qualification of safety-related electrical equipment in order to satisfy those aspects of I
j 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 I
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.
l In addition, the staff issued orders dated August 29, 1980 (amended in September 1E80) and October 24,-1980 to all licensees.
The August order
' required that the licensees provide a report, by November 1, 1980, documenting i
the qualification of safety-related electrical equipment.
The October order i
required the establishment of a central file location for the maintenance of l
all equipment qualification records.
The central file was mandated to be I
r 1
o l
t 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 information through letters dated April 21, June 30, and October 31, 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 any identified deficiencies is provided in this report.
2.2 3 cope The sucpe 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 evaluation of the licensee's response, documented in a technical evaluation report (TER) and (2) an onsite verification inspection of selected safety-related electrical equipment.
Components of the air handling, ventilation and cooling, chemical addition and sampling reactor, makeup and purification, and reactor coolant systems were inspected.
The inspection verified proper installation of equipment, overall interface integrity, location with respect to flood level for equipment inside the containment, 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 inspection is documented in report IE 50-302/80-21 of May 5, 1980.
No deficiencies were noted.
For this review, the documents referenced above have been factored into the overall staff evaluation.
3.1 Completeness of Safety-Related Equipment i
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 HEl8 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 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 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 provides information fc.,
,he 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 subsequent failure will not mislead the operator or adversely affect the mitigation of the consequences of the accident.
The environmental qualifi-l cation of post-accident sampling and monitoring and radiation monitoring i
equipment is closely related to the review of the TMI Lessons-Learned modifications and will be performed in conjunction with that review.
l The licensee identified 37 types of equipment relating to 411 Component Work l
Sheets which were assessed by the staff.
3.2 Service Conditions l
Commission Memorandum and Order CLI-80-21 requiras that the DOR guidelines and l
the "For Comment" NUREG-0588 are to be used as the criteria for establishing l
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 bam o!# plant-specific analysis identified l-in the licensee's Final Safety Analysis Report (FSAR) or based on generic l
profiles using the methods identified in these documents.
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7 On this basis, the staff has assumed, unless otherwise noted, that the analysis for developing the environmental envelopes 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 main-steam-line-break (MSLB) environmental conditions are anveloped 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 00R guidelines.
Equipment submergence has also bees; addressed where the possibility exists that flooding of equipment may result from HELBs.
3.3 Temperature, Pressure, and Humidity Conditions Inside Containment The licensee has provided the results of accident analyses as follows:
Max Temp ( F)
Max Press (psig)
Humidity (%)
LOCA 296 49 100 The staff has concluded that the minimum temperature profile for equipment qualiffi tion purposes should include a margin to account for higher-than-average tempera :res in the upper regions of the containment that can exist due to stratification, especially following a postulated MSLB.
Use of the 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.
l The licensee has specified the use of steam saturation temperatures co: responding l
to total building pressure for qualificatic:1 purposes.
This is consistent I
with the staff's recommendation and is acceptable.
The staff does not agree with the licensee's position that the Bishop Filler Tape, Model No. Biseal 3, Termination Procedure 33-74 (special), pertaining to the reactor coolant pump motors, need be qualified only to environmental parameters outside containment.
If the component is used inside containment, it must be qualified to the service conditions inside containment.
The licensee shouid also clarify where this tape ir. used because the component evaluation sheet indicates outside containment.
i 3.4 Temperature, Pressure, and Humidity Conditions Outside Containment The licensee has provided the temperature, pressure, humidity and applicable environment associated with an HELB in the intermediate building. l
For this review, the staff has accepted the licensee's position that the temperature and pressure remain ambient within the auxiliary building.
- However, the licensee must submit for NRC review the proposed addition of an automatic pressure loss shutoff valve to the auxiliary steam system, scheduled to be installed during the 1981 refueling outage.
The staff review will include verifying that, following the modification, the auxiliary steam system is single-failure proof.
The staff has verified that the parameters identified by the licensee for the MSLB are acceptable.
3.5 Submergence The maximum submergeace 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 the maximum flood level elevation in the reactor building is 99,85 ft.
The licensee states that equipment essential to the safe operation of Crystal River Unit 3 was determined to be above the flood level.
However, the coraponent evaluation sheets indicate that some equipment is at an elevation below or less than 2 in. above the flood level.
These components have been identified in Appendix B to this safety evaluation.
The licensee should address this apparent inconsistency and verify that, in fact, these components are not subject to submergence.
It is not clear from the information submitted that submergence of safety-related electrical equip-ment outside of the reactor building 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 i
The licensee's submittal references the technical specifications which give l
values for the chemical concentration between 2270 to 2450 ppm boron with an unspecified pH.
Additionally, only one of the submitted documentation references, the March 2, 1978 Rockbestos Co. Test Report, provides the amount of boron in the spray environment and the pH range.
Therefore, for the purpose of this revicw the effects of chemical spray will be conddered unresolved.
The staff will review the licensee's response when it is submitted and discuss the resolution in a supplemental report.
3.7 Aging Section 7 of the D0R guidelines does not require a qualified life to be estab-lished for all safety-related electrical equipment.
However, the following l
actions are required:
(1) Make a detailed comparison of existing equipment and the materials identified in Appendix C of the D0R guidelines.
The first supplement to IEB-79-01B requires licensees to utilize the table in Appendix C and identify any additional materials as the result of their effort.
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(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.
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
- ormation to verify anc 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, in many cases, this phase of the response is out-standing 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.
The licensee states that only aging will be considered for equipment required to operate for one minute or less and that this equipinent is considered as not being exposed to the accident environment.
This position is not acceptable and the licensee should refer to the staff's response to question 12 contained in Supplement No. 2 to IEB 79-018.
3.8 Radiation (Inside and Outside Containment)
The licensee has provided values for the radiation levels postulated to exist following a LOLA.
The application and methodology employed to determine these values were presented to the licensee as part of the NRC staff criteria con-tained in tbc D0R 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 l
ranging between 1 x 104 and 7.9 x 10s rads.
The radiation service condition provided by the licensee is lower than provided in the 00R guidelines (4 x 107) for gamma and beta radiation. The licensee is requested to either provide justification for using lower service condition or use the service condition provided in the D0R guidelines for both gamma and beta radiation.
If the former option is chosen, then the analysis--including the basis, assumptions, and a sample calculation--should t,e provided.
A required value outside containment of 6.1 x 106 rads has been used by the licensee to specify limiting radiation levels within the auxiliary building (decay heat pit, elevation 75 ft 0 in.).
This value appears to consider the
radiation levels influenced by the source term methodology associated with post-LOCA recirculation fluid lines and is therefore acceptable.
4 QUALIFICATION OF EQUIPMENT 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, ;.ne 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 t?oected that when the review of test reports is complete, the environmental quai:f; cation 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-cation or replace the item (s) of cor.cern.
This effort will begin in early 1981.
An appendix for Sach subsection of this report provides a list of equipment for which additional information and/or corrective action it required. Where appropriate, a reference is provided in the appendices to identify deficiencies.
It should be noted, as in the Commission Memorandum and Ordar, that the deficien-cies identified do not necessarily mean that equipment d unqualified.
- However, they are cause for concern and may require further case-by-case evaluation.
4.1 Equipment Requiring Immediate Corrective Actii;g 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 identified valve operators for chemical addition valves CAV 1, 3, 4, and 5 that required immediate corrective action; therefore, a licensee event report (LER) was submitted, dated July 18, 1979.
These valve operators were replaced during an August 1979 outage.
The staff has not identified any other safety related electrical equipment which is not able to perform its intended safety function during the time in which it must operate.
I 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. I
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 containinent not com,qleted QM qualification method RPN - equipment relocation or replacement; adequate schedule not provided s
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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 ?ollowing 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 ar. 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 designate:d equipment that has been adequately qualified and satisfies the single-failure criterion.
(4) Equipment will not he subjected to a harsh environment as a result of the postulate < accident.
The licensee is, therefore, required to supplement the information presented by providing re 41utions to the deficiencies identified; these resolutions should include a description cf the corrective action, schedules for its completion (as applicable), a d so forth. The staff will review the licensee's response, when it is submittec, 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 oy June 30, 1982.
4.3 Equipment Considered Acceptable or Conditionally Acceptable 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-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 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-mitted and' discuss the resolution in a supplemental report.
5 DEFERRED REQUIREMENTS IEB 79-01B, Supplement 3 has relaxed the time constraints for the submission 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, 1981.
The staff 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 are appropriate, except as noted in Section 3 of this report.
Outstanding information identified 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 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 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 this 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 op1 ration 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 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 cr HELB
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(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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i APPENDIX A Equipment Requiring Immedia?? Corrective Action (Category 4.1)
The licensee submitted, on July 18, 1979, a licensee event report (LER) which identified valve operators for valves CAV.1, 3, 4, and 5 as not qualified for the reactor building environment.
These valve operators were replaced during an August 1979 outage.
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APPENDIX B Equipment Requiring Additional Information and/or Corrective Action (Category 4.2)
LEGEND:
Designation for Deficiency 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 nutside 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 cehedule provided Equipment Manufacturer
!lant ID No.
Deficiency
(-
Description Valve Motor Operator Limitorque AHV-1B CS,A,RPS Valve Motor Operator Limitorque AHV-1C CS,A,RPS Valve Motor Operator Limitorque ASV-5 QT,T,P,H,R, A,RPS I'-
Valve Motor Opei ator Limitorque BSV-3 R,A,RPS Valve Motor Operator Limitorque CAV-1 CS,A,S Valve Motor Operator Limitorque CAV-3 CS,A,S
-Valve Motor Operator Limitorque CAV-4 CS,A,S P-1
APPENDIX B (Continued)
Equipment
. Manufacturer Plant ID No.
Deficiency Description Valve Motor Operator Limitorque CAV-5 CS,A,S Valve Motor Operat,r Limitorque CAV-126 CS,A,5 Valve Motor Operator Limitorque CFV-11 T,P,CS,R, A,RPS Valve Motor Operator Limitorque-CFV-12 T,P,CS,R, A,RPS Valve Motor Operator Limitorque CFV-15 T,P,CS,A, RPS Valve Motor Operator Limitorque CFV-16 T,P,CS,A,-
-Valve Motor Operator Limitorque DHV-5 R,A,RPS Valve Motor Operator Limitorque DHV-6 R,A,RPS Valve Motor Operator Limitorque DHV-34 R,A,RPS Valve Motor Operator Limitorque DHV-35 R,A,RPS Valve Motor Operator Limitorque DHV-110 R,A,RPS Valve Motor Operator Limitorque DHV-111 R,A,RPS
' Valve Motor Operator Limitorque EFV-3 QT,T,P,H,R, A,EXN
- Valve Motor Operator Limitorque EFV-4 QT,T,P,H,R, A,EXN Valve Motor Operator Limitorque EFV-11 QT,T,P,H,R, A,RPS Valve Motor Operator Limitorque EFV-32 QT,T,P,H,R, A,RPS Valve Motor Operator ~
Limitorque EFV-14 QT,T,P,H,R, A,RPS Valve Motor Operator Limitorque EFV-33 QT,T,P,H,R, A,RPS B-2 m
APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Description Valve Motor Operator Limitorque FWV-28 M,P,A
-Valve Motor' Operator Limitorque FWV-33 QT,T,P,H,R, A,RPS
' Valve Motor Operator Limitorque FWV-34 QT,T,P,H,R, A,RPS Valve Motor Operator Limitorque FWV-161 QT,T,P,H,R, A,RPS Valve Motor Operator-Limitorque FWV-162 QT,T,P,H,R, A,RPS Valve Motor Operator Limiterque MSV-55 QT,T,P,H,R, A,RPS Valve Motor Operator Limitorque MSV-56 QT,T,P,H,R, A,RPS Valve Motor Operator.
Limitorque MUV-18 R,A,RPS Valve Motor Operator Limitorque MUV-38 CS,R,A,5, RPS Valve Motor Operator Limitorque_
MUV-39 CS,R,A,S, RPS Valve Motor Operator-Limitorque MUV-40 CS,R,A,S, RPS Valve Motor Operator Limitorque MUV-41 CS,R,A,5, RPS Valve. Motor Operator Limitorque MUV-53 R,A,RPS Valve Motor Operator Limitorque MUV-257 R,A,RPS
~ Valve Motor Operator Limitorque MUV-58 R,A,RPS Valve Motor Operator Limitorque MUV-73 R,A,RPS Valve Motor Operator Limitorque MUV-258 CS,R,A,RPS Valve Motor Operator Limitorque-MUV-259 CS,R,A,RPS B-3
APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Gescription Valve Motor Operator Limitorque MUV-260 CS,R,A,RPS Valve Motor Operator Limitorque MUV-261 CS,R,A,RPS Valve Motor Operator Limitorque RCV-11 P,CS,R,A,RPS Valve' Motor. Operator.'
Limitorque WDV-3 CS,R,A,S,RPS Valve Motor Operator Limitorque WDV-60 CS,A,S Valve Motor Operator Limitorque WDV-94 CS,A,S Valve Motor Operator Limitorque WDV-406 CS,A Local Control Station Field Fab /GE AH-5 QT,T,P,H, R,A,RPS
. Local Control Station Field Fab /GE AH-6 QT,T,P,H,.
R,A,RPS Local Control-Station Field Fab /GE AH-28 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE AH-29 QT,T,P,H, R,A,RPS
' Local Control Station Field Fab /GE AS-1 QT,T,P,H, R,A,RPS Local Control Station Field' Fab /GE CA-1 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE CA-2 QT,T,P,H, R,A,RPS Local' Control _ Station Field Fab /GE CA-3 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE CF-1 QT,T,P,H, R,A,RPS Local Control Station Field Fas/GE CF-5 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE CF-3 QT,T,P,H, R,A,RPS B-4
' APPENDIX B (Continued)
Equipment
' Manufacturer'-
' Plant'ID No.
. Deficiency-Description l
- Local Control Station
- Field Fab /GE
'CI-3' QT,T,P,H, R,A,RPS' t'
Local Control Station-Field Fab /GE CI-4 QT,T,P,H,.
R,A,RPS
. Local Control Station Field Fab /GE CI-5 QT,T,P,H, R,A,RPS
.a.
1
- Local' Contro1 ~- Station '
Field Fab /GE EF-3 QT,T.P,H, R,A,RPS Local Control Station-
- Field' Fab /GE EF-4; QT,T,P,H, R,A,RPS' z,
Local ~ Control Station Field Fab /GE.
FW-5L QT,T,P,H, i
R,A,RPS-Local Control Station <
Field Fab /GE FW-6 QT,T,P,H, i
R,A,RPS LocallControl-Station ~
Field Fab /GE
- FW-11 QT,T,P,H, i
~
~
R,A,RPS Local-Control Station, Field Fab /GE FW-12 QT,T,P,H, R,A,RPS
. Local Control-Station
- Field Fab /GE MS-5 QT,T,P,H, R,A,RPS l
..L'oca1 ' Control : Station L
- Field Fab /GE MS-6 QT,T,P,H,
~
R,A,RPS-
~ Local Control. Station Field Fab /GE MS-7 QT,T,P,H, n
R,A,RPS.
Loca1 Control' Station Field Fab /GE MS-8 QT,T,P,H, 5
R,A,RPS
~ Local' Control Station-Field Fab /GE MS '
QT,T,P,H, R,A,RPS
! Local Control Station Field Fab /GE MS-10 QT,T,P,H, R,A,RPS 1
t g
B-5
,1,-_.,"...
......~.._,_,......_._.w_...,s...-..._...--.__..-.._.,.__-.~..._,,.__..-..-.--._--
E j
APPENDIX B (Continued)
Equipment Menufacturer Plant ID No.
Deficiency Description c
Local Control Station Field Fab /GE MU-4 QT,T,P,H, i
R,A,RPS 7
Local Control Station Field Fab /GE MU-5 QT,T,P,H, R,A,RPS I
Local Control Station Fielo Fab /GE MU-7 QT,T,P,H, R,A,RPS
[
Local Control Station Field Fab /GE MU-16 QT,T,P,H, E
R,A,RPS Local Control Station Field Fab /GE SW-3 QT,T,P,H,
[
R,A,RPS Local Control Station Field Fab /GE SW-4 QT,T,P,H,
{
R,A,RPS Local Control Station Field Fab /GE SW-5 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE SW-16 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE SW-6 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE SW-7 QT,T,P,H, E
R,A,RPS Local Control Station Field Fab /GE SW-8 QT,T,P,H, W
R,A,RPS w'
Local Control Station Field Fab /GE SW-9 QT,T,P,H, R,A,RPS a
Local Control Station Field Fab /GE SW-10 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE SW-11 QT,T,P,H, R,A,dPS Local Control Station Field Fab /GE SW-13 QT,T,P,H, R,A,RPS E
Local Control Station Field Fab /GE SW-14 QT,T,P,H, R,A,RPS i
B-6 m
e
APPENDIX B (Continued)'
Equipment Manufacturer Plant ID No.
Deficiency Des'cription Local Control Station Field Fab /GE WD-1 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE WS-1 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE WS-2' QT,T,P,H, R,A,RPS Local-Control Station Field Fab /GE WS-3 QT,T,P,H, R,A,RPS Local Control Station Field Fab /GE' WS-4 QT,T,P,H, R,A,RPS
' Solenoid Valve H. Pratt AHV-1A QT,T,P,H, R,A,RPS Solenoid Valve H. Pratt AHV-1D QT,T,P,H, R,A,RPS
. Solenoid Valve Crane CIV-34 QT,T,P,H, R,A,RPS Solenoid Valve Crane CIV-35 QT,T,P,H, R,A,RPS Solenoid Valve Crane CIV-40 QT,T,P,H, R,A,RPS Solenoid Valve Crane CIV-41 QT,T,P,H, R,A,RPS Solenoid Valve Crane SWV-109 QT,T,P,H, R,A,RPS Solenoid Valve Crane SWV-110 QT,T,P,H, R,A,RPS Solenoid Valve Rockwell CAV-6 QT,T,P,H,R, A,RPS Solenoid Valve Rockwell CAV-7 QT,T,P,H,R, A,RPS B-7 I
APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Description Solenoid Valve Rockwell MSV-411 QT,T,P,H,R, A,RPS Solenoid Valve Rockwell MSV-412 QT,T,P,H,R, A,RPS Solenoid Valve Rockwell MSV-413 QT,T,P,H,R, A,RPS Solenoid Valve Rockwell MSV-414 QT,T,P,H,R, A,RPS Solenoid Valve ASCO CFV-27 QT,T,P,H,R, A,RPS Solenoid Valve ASCO CFV-28 QT,T,P,H,R, A,RPS Solenoid Valve ASCO CFV-25 QT,T,P,H,R, A,RPS Solenoid Valve ASCO CFV-26 QT,T,P,H,R, A,RPS Solenoid Valve ASCO CFV-29 QT,T,P,H,R, A,RPS Solenoid Valve ASCO CFV-42 QT,T,P,H,R, A,RPS Solenoid Valve ASCO MSV-130 QT,T,P,H,R, A,RPS Solenoid Valve ASCO MSV-148 QT,T,P,H,R, A,RPS Solenoid Valve ASCO MUV-49-SV QT,T,P,H,R, A,RPS Solenoid Valve ASCO MUV-64 QT,T,P,H,R, A,RPS Solenoid Valve ASCO MUV-253-SV1 QT,T,P,H,R, A,RPS B-8
i APPENDIX B (Continued)
Equipment Manufacturer Plant ID.No.
Deficiency Description Solenoid Valve ASCO MUV-253-SV2 QT,T,P,H,R, A,RPS Solenoid Valve (p. 2-156)
MUV-25-SV-QT,T,P,H,R,-
A,RPS Solenoid Valve ASCO WSV-3 QT,T,P,H,R, A,RPS Solenoid Valve ASCO WSV-4 QT,T,P,H,R, A,RPS Solenoid Valve ASCO WSV-5 QT,T,P,H,P, A,RPS Solenoid Valve-ASCO WSV-6 QT,T,P,H,R, A,RPS Solenoid Valve GE RCV-10-SV QT,T,P,H,CS, R,A,RPS Solenoid Valve-WEBC0 SW-12 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-35 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-37 QT,T,P,H,R, A,RPS, Solenoid Valve WEBCO SW-39 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-41 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-43 QT,T.P,H,R, A,RPS, Solenoid Valve WEBC0 SW-45 QT,T,P,H,R, A,RPS, Solenoid Valve WEBCO SW-47 QT,T,P,H,R, A,RPS, B-9
APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Dercription
, Solenoid Valve'.
WEBCO.
SW-48 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-49 QT,T,P,H,R,-
A,RPS, Solenoid Valve LWEBCO SW-50 QT,T,P.H,R, A,RPS,
-Solenoid Valve WEBC0 SW-79 QT,T,P,H,R, A,RPS,
? Solenoid Valve-WEBC0-SW-30 QT,T,P,H,R, A,RPS,
-Solenoid Valve WEBC0 SW-81 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SWV-82 QT,T.P,H,R, A,RPS, Solenoid Valve
-WEBC0 SW-83 QT,T,P,H,R, A,RPS, Solenoid Valve WEBCO SW-84 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0' SW-85 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-86 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-151 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-152 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-353 QT,T,P,H,R, A,RPS, Solenoid Valve WEBC0 SW-354 QT,T,P,H,R, A,RPS,
~
B-10
i Y
APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Description Solenoid Valve WEBC0 SWV-355 QT,T,P,H,R, A,RPS, Solenoid Valve Grinnell WDV-4 QT,T,P,H,R, A,RPS, Solenoid Valve Grinnell WDV-61 QT,T,P,H,R, A,RPS, Solenoid Valve Grinnell WDV-62 OT,T,P,H,R, A,RPS, Terminal Box Field Fab / States BS-5 QT,R,A,QI Terminal Box Field Fab / States BS-6 QT,R',A,QI Terminal Box Field Fab / States MU-22 R,A,QI Terminal Box Field Fab / States RC-8 R,A,QI Terminal-Box Field Fab / States SW-6 R,A,QI Terminal Box Field Fab / States SW-7 R,A,QI Terminal Box Field Fab / States SW-8 R,A,QI Terminal Box Field Fab / States SW-9 R,A,QI Terminal Box Field Fab / States SW-14 R,A,QI Terminal Box Field Fab / States SW-15 R,A,QI Terminal Box Field Fab / States WD-3 R,A,QI Terminal Box Field Fab / States WS-2 R,A,QI Terminal' Box Field Fab / States WS-3 R,A,QI Terminal Blocks T&B
'Model No. FI QT,T,P,H,CS, Various Locat'.ons R,A,RPS Terminal Blocks Kulka Model Nos. 7TB &
QT,CS,R,A, STB Various QM,RPS Locations
{
l B-11
[
APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Description Terminal Lugs Burndy Crimp Type QT,T,P,H,CS, Plant Wide R,A,RPS
-Pressure Transmitter L&N BS-PT-16 QT,T,P,H,R, A,RPS Pressure Transmitter L&N BS-PT-17 QT,T,P,H,R, A,RPS Pressure Transmitter BMCo DH-DPT-1 QT,T,P,H,R, A,RPS Pressure Transmitter BMCo DH-DPT-2 QT,T,P,H,R, A,RPS Pressure Transmitter BMCo DH-DPT-38 QT,T,P,H,R, A,RPS Pressure Transmitter BMCo MU-23-dPT-1 QT,T,P,H,R, A,RPS
. Pressure Transmitter BMCo MU-23-dPT-2 QT,T,P,H,R, A,RPS Pressure Transmitter BMCo MU-23-dPT-3 QT,T,P,H,R, A,RPS Pressure Transmitter BMCo MU-23-dPT-4 QT,T,P,H,R, A,RPS Pressure Transmitter BMCo MU-24-dPT QT,T,P,H,R, A,RPS Pressure Transmitter Rosemount RC-3A-PT2 T,CS,A,5 Pressure Transmitter Rosemount RC-3A-PT1 T,CS,A,S Pressure Transmitter Rosemount RC-38-PT1 T,CS,A,S Pressure Transmitter Rosemount RC-38-PT2 T,CS,A,S Pressure Transmitter Rosemount RC-PT-13-.
T,CS,A,5
- See Attachment 1:
Foxboro Letter (3/12/81), " Potential Deficiency Affecting Foxboro Transmitters," for corrective action.
B-12
APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Description
- Pressure Transmitter Foxboro SP-6B-PT-2 CS,R,A,RPS Local Motor Starter Allen-Bradley ASV-5 QT,T,P,H,R, A,RPS Local Motor Starter Allen-Bradley FW-33 QT,T,P,H,R, A,RPS
' Local Motor Starter Allen-Bradley FW-34 QT,T,P,H,R, A,RPS Local Motor Starter Allen-Bradley FW-35 QT,T,P,H,R, A,RPS Local Motor Starter Allen-Bradley FW-36 QT,T,P,H,R, A,RPS Local Motor Starter Allen-Bradley FW-161 QT,T,P,H,R, A,RPS Local Motor Starter Allen-Bradley FW-162 QT,T,P,H,R, A,RPS Local Motor Starter Allen-Bradley MSV-55 QT,T,P,H,R, A,RPS Local Motor Starter Allen-Bradley MSV-56 QT,T,P,H,R, i-f A,RPS f
^$ee Attachment 1:
Foxboro Letter (3/12/81), " Potential Deficiency Affecting Foxboro Transmitters," for corrective action.
l B-13
APPENDIX B (Continued)
. Equipment Manufacturer Plant ID No.
Deficiency Description Motor Starter Allen-Bradley EFV-11 QT,T,P,H,R, A,RPS Motor-Starter Allen-Bradley EFV-14 QT,T,P,H,R, A,RPS Motor Starter Allen-Bradley EFV-32 QT,T,P,H,R, A,RPS Motor Starter.
' Allen-Bradley EFV-33 QT,T,P,H,R, A,RPS Motor Control Center Allen-Bradley MTMC-3 QT, f,P,H,R, A,RPS Motor Control Center Allen-Bradley MTMC-4 QT,T,P,H,R, A,RPS Motor Control Center Allen-Bradley MTMC-5 QT,T,P,H,R, A,RPS Motor Control Center
. Allen-Bradley MTMC-6 QT,T,P,H,R, A,RPS Motor Control Center Allen-Bradley MTMC-7 QT,T,P,H,R, A,RPS Moter Control Center Allen-Bradley MTMC-1 QT,T,P,H,R, A,RPS
. Motor Control Center Allen-Bradley MTMC-2 QT,T,P,H,R, A,RPS
. Motor Control Center Allen-Bradley MTMC-12 QT,T,P,H,A, i
. Motor Control Center Allen-Bradley MTMC-13 QT,T,P,H,A, RPS Motor Starter Gould I-T-E MUV-23 QT,A j
Motor Starter Gould I-T-E MUV-24 QT,A Motor Starter Gould I-T-E MUV-25 QT,A i
B-14 l
APPENDIX B (Continued)
Equipment 1 Description ~
- Manufacturer Plant ID No.
Deficiency.
Motor Starter-Gould I-T-E MUV-26 QT,A e
Electrical Penetration
.Conax-MTBD-2A QT,CS,QM,
-Assembly-R,A,RPS
- Electrical Penetration Conax MTBD-28 QT,CS,QM, Assembly R,A,RPS Electrical Penetration-Conax MTBD-2C QT,CS,QM,
~ Assembly l R,A,RPS Electrical Penetration Conax~
MTBD-8A QT,CS,QM, p
-Assembly.
R,A,RPS Electrical Penetration Conax MTBD-8B QT,CS,QM,-
. Assembly:
R,A,RPS
- Electrical. Penetration Conax MTBD-8C QT,CS,QM, Assembly.
R,A,RPS Electrical-Penetration Conax.
MTBD-8D QT,CS,QM,.
Assembly R,A,RPS Electrical Penetration Conax MTBD-9A QT,CS,QM,
" Assembly R,A,RPS
-Electrical Penetration.
Conax MTBD-9B QT,CS,QM, Assembly-R,A,RPS Electrical Penetration Conax' MTBD-9C QT,CS,QM, Assembly R,A,RPS i
. Electrical Penetration Conax MTBD-90 QT,CS,QM, Assembly R,A,RPS Electrical Penetration Conax MTBD-11A QT,CS,QM, Assembly R,A,RPS i
.. Ele'ctrical. Penetration Conax MTBD-11B QT,CS,QM, Assembly ^
R,A,RPS Pump Motor Westinghouse BSP-1A QT,T,P,H,R, A,RPS t
Pump Motor Westinghouse BSP-1B QT,T,P,H,R, A,RPS t
B-15
o APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Description Pump Motor
. estinghouse
'DHP-1A QT,T,P,H,R, W
A,RPS Pump Motor.
Westinghouse DHP-1B QT,T,P,H,R, A,RPS Pump Motor Westinghouse MUP-1A QT,T,P,H,R, A,RPS Pump Motor Westinghouse MVP-1B QT,T,P,H,R, A,RPS Pump Motor-Westinghouse MVP-1C QT,T,P,H,R, A,RPS Pump Motor GE DCP-1A QT,T,P,H,R, A,RPS Pump. Motor GE DCP-1B QT,T,P,H,R, A,RPS Pump Motor Electric Machinery EFP-1 QT,T,P,H,R, A,RPS Pump Motor Electric Machinery RWP-2A QT,T,P,H,R, A,RPS Pump Motor Electric Machinery RWP-28 QT,T,P,H,R, l
A,RPS Pump Motor Electric Machinery RWP-3A QT,T,P,H,R, A,RPS Pump Motor Electric Machinery RWP-3B QT,T,P,H,R, A,RPS
-Pump Motor Electric Machinery SWP-1A QT,T,P,H,R, l.
A,RPS Pump Motor Electric Machinery SWP-1B QT,T,P,H,R, A,RPS Level Transmitter Bailey MU-14-LT1 QT,T,P,H,R, l
A,RPS r
I l
B-16 L-L
.~
' APPENDIX B (Continued) 4
- EquipmentI
- Manufacturer Plant ID No.
Deficiency.
l Description-Level'Transmitte'r Bailey.
.MU LT2 QT,T,P,H,R, A,RPS~
. Level Transmitter.
' Rosemount
.RC-DPT-1 T,CS,S,A Leve1' Transmitter
' Rosemount
- RC-DPT-2
.T,CS,S,A
- Level Transmitter
' Rosemount RC-DPT-3 T,CS,S,A Level Transmitter-
- BMCo SP1A-LT1 QT,T,CS,A 5,RPS Level Transmitter BMCo-SP1B-LT1 QT,T,CS,A 5,RPS 1
Level-Transmitter _
BMCo SPlA-LT2-QT,T,P,H,CS, R,A,5,RPS
. Level Transmitter BMCo LSP1A-LT3 QT,T,P,H,CS, I
R,A,S,RPS Level Transmitter.
BMCo-SP1B-LT2 QT,T,P,H,CS, R,A,S,RPS Level Transmitter BMCo SP1B-LT3 QT,T,P,H,CS, R,A,S,RPS
- Level Transmitter.
BMCo SP1A-LT4 QT,T,CS,A, S,RPS i
i Level Transmitter BMCo SPlA-LT5 QT,T,CS,A, S,RPS l-Level' Transmitter' BMCo SPlB-LT4 QT,T,CS,A,
[
S,RPS l
Level Transmitter BMCo' SP18-LT5 QT,T,CS,A, l-5,RPS
~
Level Transmitter Fisher WD-LT-26 QT,T,P,H,CS, R,A,5,RPS-
- Level Transmitter-Fisher WD-LT-222 QT,T,P,H,CS, R,A,5,RPS L
I l
B-17
APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Description Fan Motor Westinghouse AHF-1A QT,CS,A,RPS Fan Motor-Westinghouse AHF-1B QT,CS,A,S, RPS Fan Motor.
Westinghouse AHF-1C QT,CS,A,S, RPS Fan Motor Century Electric AHF-15A QT,T,P,H, R,A,RPS Fan Motor Century Electric AHF-15B QT,T,P,H, R,A,RPS Pressure Switch Static-0-Ring BS-PS-25 QT,T,P,H, R,A,RPS Pressure Switch Static-0-Ring BS-PS-62 QT,H,R,A, RPS
. Pressure Switch Static-0-Ring MS-92-PS1 QT,T,P,H,R, A,RPS Pressure Switch-Square-D BS-PS-18 QT,T,P,H,R, A,RPS Pressure Switch Cabinet Hoffman Co.
PS Cab. -3Al QT,T,P,H, R,A,RPS Pressure Switch Cabinet Hoffman Co.
PS Cab. -3A2 QT,T,P,H, R,A,RPS Pressura Switch Cabinet Hoffman Co.
PS Cab. -3A4 QT,H,R,A, RPS
' Flow Indicator Switch Bart SS-79-FIS QT,T,P,H, R,A,RPS Flow Indicator Switch Bart BS-80-FIS QT,T,P,H, R,A,RPS Flow Indicator Switch Bart DH-43-FIS QT,T,P,H, R,A,RPS Flow Indicator Switch Bart DH-44-FIS QT,T,P,H, R,A,RPS B-18
APPENDIX B (Continued)
Equipment Manufacturer Flant ID No.
Deficiency Description Flow Switch Cleveland AH-552-dPS QT,T,P,H, R,A,RPS
- Flow Switch Cleveland AH-551-dPS QT,T,P,H, R,A,RPC Flow Transmitter BMCo
'RC-14A-DPT-1 M,T,CS,A, 5,RPS Flow Transmitter BMCo RC-14A-DPT-2 M,T,CS,A, S,RPS Flow Transmitter BMCo RC-14B-DPT-1 M,T,CS,A, S,RPS Flow Transmitter BMCo
~ RC-14B-DPT-2 M,T,CS,A, S,RPS Termination Procedure Kerite Model No. T-1NS-HT QT,T,P,H, Outside Containment R,A,RPS
~ Termination Procedure Kerite Model.No. T-5NS-HT QT,T,P,H, Outside Containment R,A,RPS
. Termination Procedure-Kerite Model No. 39-69 CS,A Inside Containment Temperature Element Bailey DH-2-TE-1 QT,T,P,H,R, A,RPS Temperature Element Bailey DH-2-TE-2 QT,T,P,H,R, A,RPS Temperature Element Bailey DH-6-TE-1 QT,T,P,H,R, A,RPS Temperature _ Element Bailey DH-6-TE-2 QT,T,P,H,R, A,RPS Temperature Element Rosemount RC-4A-TE4 QT,CS,R,A, RPS Temperature Element Rosemount RC-4A-TE1 QT,CS,R,A, RPS B-19
~.. -
APPENDIX B (Continued)
Ekuipment Manufacturer Plant ID No.
Deficiency Description Temperature Element Rosemount RC-4B-TE1 QT,CS,R,A, RPS Temperature Element Rosemount RC-48-TE4 QT,CS,R,A, RPS Temperature Element Rosemount RC-5A-TE1 QT,CS,R,A, RPS Temperature Element Rosemount RC-5A-TE2 QT,CS,R,A, RPS
-Temperature Element Rosemount RC-5A-TE3 QT,CS,R,A, RPS Temperature Element Rosemount RC-5A-TE4 QT,CS,R,A, RPS Temperature Element Rosemount RC-53-TEl QT.CS,R,A, RPS
- Temperature Element Rosemount RC-58-TE2 QT,CS,R,A, RPS 4
Temperature. Element Rosemount RC-5B-TE3 QT,CS,R,A, RPS Temperature Element Rosemount RC-58-TE4 QT,CS,R,A, APS Filler Tape Bishop Model No. Biseal 3 QT,T,P,H, Outside Containment R,A,RPS Insulating / Filler Tape Bishop Model No. W962 QT,T,P,H, Inside Containment CS,R,A,RPS Insulating Tape 3M Model No. Scotch QT,T,P,H, 130C Inside Con-CS,R,A,RPS tainment 4 -
Glass Electrical Tape 3M Model No. Scotch 27 QT,T,P,H, Inside Containment CS,R,A,RPS Vinyl Electrical Tape 3M liodel No. Scotch 33+ QT,T,P,H, Outside Containment R,A,RPS B-20
APPENDIX B (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Description Silicone Rubber Tape 3M Modei No. Scotch 70 QT,T,P,H, Inside Centainment CS,R,A,RPS Temperature Switch Penn' Controls AH-315-TS QT,T,P,H, R,A,RPS Temperature Switch Penn Controls AH-410-TS QT,T,P,H, R,A,RPS Wall Mounted Starter Allen-Bradley MTMC-.4 QT,T,P,H, A,RPS Wall Mounted Starter
. Allen-Bradley MTMC-5 QT,T,P,H, A,RPS Wall Mounted Starter Allen-Bradley MTMC-7 QT,T,P,H,R, A,RPS Limit Switches NAMC0 FW-39 QT,T,P,H,R, A,RPS Limit Switches NAMCO FW-40 QT,T,P,H,R, A RPS Limit Switches NAMC0 SW-47 QT,T,P,H,R, A,RPS Limit Switches NAMCO SW-48 QT,T,P,H,R, A,RPS Limit SwitJ1es NAMC0 SW-49 QT,T,P,H,R, A,RPS timit Switches NAMCO SW-50 QT,T,P,H,R, A,RPS Control Cabinet Johnson Control Control Cab 16A QT,T,P,H, R,A,RPS Control Cabinet Johnson Control Control Cab 16B QT,T,P,H, R,A,RPS Splice Terminal Burndy Model No. Insulink QT,T,P,H, Plant Wide CS,R,A,RPS B-21
APPENDIX B (Continued)
Equipment Manufacturer-Plant ID No.
Deficiency Description
~ Power / Control Cable' Kerite Mode! Nos. FR & HT.QT,CS,M,A Plant Wide Control / Thermocouple Rockbestos Model No. Silicone CS,A Extension Cable Rubber,-Plant Wide ~
Instrument / Thermocouple Continental Wire Model No. Silicone T,P,A Extension Cable and Cable Rubber Ins. #CC-2193 Plant Wide Valve Motor Operator Limitorque CDV-43 EXN Valve Motor Operator-Limitorque CDV-44 EXN Valve Motor Operator Limitorque WDV-407 EXN Pressure Transmitter L&N' FW-38-PT EXN Pressure Transmitter L&N FW-39-PT EXN Pressure Transmitter BM SP-8A-DPT-1 EXN Pressure Transmitter BM SP-8A-DPT-2 EXR Pressurc Transmitter BM SP-8A-DPT-3 EXN Pressure Transmitter BM SP-88-DPT-1 EXN Pressure Transmitter BM SP-8B-DPT-2 EXN Pressure: Transmitter BM SP-88-DPT-3 EXN Motor Control Center-Allen-Bradley MTMC-14 EXN I'
~ MTMC-15 EXN Motor Control Center Allen-Bradley
-Radiation Monitor Trap RM-Al EXN Radiation Monito-Trap RM-A6 EXN Radiation Monicor Trap RM-A12 EXN Temperature Recorder D or C LR-7-TR EXN B-22
. =.
b APPENDIX C Equipment Considered Acceptable or Conditionally Acceptable (Category 4.3)
LEGEND:
Designation for Deficiency R-Radiation T-Temperature QT - Qualification time RT - Required time P-Pressure H-Humidity CS'-
Chemical spray A-Material aging evaluation, replacement schedule, c.' going equipment a
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
. Manufacturer Plant ID No.
Deficiency Description Valve Motor Operator Limitcrque BSV-4 A
Valve Motor Operator Limitorque BSV-16 A
Valve Motor Operator Limitorque BSV-17 A
Valve Motor Operator Limitorque BSV-36 A
Valve Motor Operator Limitorque BSV-37 A
Valve Motor Operator Limitorque DHV-11 A
Valve Motor Operator Limitorque DHV-12 A
C-1
~
~... -
.o APPENDIX C (Continued)
Equipment Manufacturer Plant ID No.
Deficiency Description Valve Motor Operator Limitorque DW-160 A
Valve Motor Operator Limitorque EFV-7 A
Valve Motor Operator Limitorque EFV-8 A
Valve Motor Operator-Limitorque FW-14 A
Valve Motor Operator Limitorque FW-15 A
Valve Motor Operator Limitorque FW-29 A
Valve Motor Operator Limitorque FW-30 A
Valve Motor Operator
.Limitorque FW-31 A
Valve Motor Operator Limitorque FW-32 A
Valve Motor Operator Limitorque MUV-23 A
Valve Motor Operator Limitorque MUV-24 A
Valve Motor Operator Limitorque MUV-25 A
Valve Motor Operator Limitorque MUV-26 A
Valve Motor Operator Limitorque MUV-27 A
Valve Motor Operator Limitorque MUV-112 A
Valve Motor Operator Limitorque WDV-405 A
Solenoid Valve Target Rock CAV-2 A
Terminal Box Field Fab / States AH-23 A
Terminal Box Field Fab / States AH-24 A
Terminal Box Field Fab / States AS-1 A
Terminal Box Field Fab / States CA-1 A
Terminal Box Field Fab / States CA-2 A
Terminal Box Field Fab / States CA-3 A
C-2
APPENDIX C (Continued)
Equipment Manufacturer Plant 10 No.
Deficiency Description Terminal Box Field Fab / States' CF-1 A
Terminal Box Field Fab / States CF-3 A
Terminal' Box Field Fab / States CF-4 A
Terminal Box Field Fab / States CF-2 A
Terminal Box Field Fab / States CI-2 A
Terminal Box Field Fab / States CI-3 A
Terminal Box
. Field Fab / States CI-4 A
Terminal Box-Field Fab / States CI-9 A
Terminal Box Field Fab / States EF-3 A
Terminal Box Field Fab / States EF-4 A
Terminal Box Field Fab / States FW-3 A
,~
Terminal. Box-Field Fab / States FW-4 A
Terminal Box Field Fab / States FW-11 A
Terminal Box Field-Fab / States FW-20 A
Terminal Box ~
Field Fab / States FW-22 A
Terminal Box Field Fab /Sta+es MS-5 A
Terminal Box Field Fab / States MS-6 A
Terminal Box Field Fab / States MS-7 A
Terminal Box Field Fab / States MS-8 A
' Terminal Box Field Fab / States MS-17 A
Terminal Box Field Fab / States MS-18 A
Terminal Box Field Fab / States MU-4 A
Terminal Box Field Fab / States MU-5 A
C-3 L
I F
APPENDIX C (Continued)
Equipment-Manufacturer Plant'ID No.
Deficiency
. Description Terminal Box Field Fab / States MU-11' A
-Terminal Sox Field Fab / States MU-21 A
Terminal Box Field Fab / States SW-3 A
Terminal Box Field Fab / States SW-4 A
. Terminal Box Field Fab / States.
SW-5 A
' Terminal Box Field Fab / States SW-19 A
-Tarninal Box Field Fab / States SW-10 A
Terminal Box Field Fab / States SW-11 A
Terminal Box Field Fab / States SW-12 A
Terminal Box Field Fab / States SW-13 A
Terminal Box
. Field Fab / States SW-18 A
L L
l I
I l'
C-4
_.. - ~,, -,.,...
APPENDIX D Safety-Related Systems Listi Function System-
-Emergency Reactor.Shetdown Reactor Coolant Engineered Safeguards Actuation (1)
. Reactor Protection (2)
Chemical Addition'and Sampling.
IContain.ent Isol'ation Main Steam -
Auxiliary Steam Feedwater=
Emegency Feedwater Decay Heat Removal Makeup and Purification Reactor Building Spray Chemical Addition and Sampling Nuclear Service and Decay Heat Sea Water-Nuclear Services Closed Cycle Cooling Waste Disposal Radwaste Demineralized Water H
Industrial Coolers
'The NRC staff recognized that there are differences in nomenclature of the
. 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.
(1) Components controlled by systems included in submittal.
l.(2), Components included as part of reactor coolant system.
D-1
y =
?..
APPENDIX D (Continued)
Function System Reactor Core Cooling Makeup and Purification (High Pressure Injection)
Decay Heat Removal (Low Pressure Injection)
Core Flooding (Accumulators)
Containment Heat Removal Reactor Building Spray Decay Heat Removal i
(Recirculation Mode)
V Air Handling Core Residual Heat Removal Decay Heat Removal Power Operated Relief Valve
.(Part of Reactor Coolant)
Feedwater Emergency Feedwater Main Steam Decay Heat Closed Cycle Cooling Nuclear Services and Decay Heat Sea Water Nuclear Services Closed Cycle Cooling Prevention of Significant Air Handling l
Release of Radioactive j
Material to Environment Hydrogen Purge Radiation Monitoring
. Supporting Systems Air Handling, Ventilation and Cooling Electrical Power Distribution l
l D-2 l
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