ML20004C167
| ML20004C167 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 05/28/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20004C161 | List: |
| References | |
| RTR-NUREG-0588, RTR-NUREG-588 IEB-79-01, IEB-79-01B, IEB-79-1, IEB-79-1B, IEC-78-08, IEC-78-8, NUDOCS 8106010664 | |
| Download: ML20004C167 (28) | |
Text
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O Safety Evaluation Report By The Office of Nuclear Reactor Regulation
' Equipment Qualification Branch For Baltimore Gas and Electric Company Calvert Cliffs Units 1 and 2 Docket No. 50-317/318 J
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THIS DOCUMENT CONTAINS POOR QUALITY PAGES 8106010hk
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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 Containmer,t...................................
4 3.5 Submergence...........................................
5 3.6 Chemical Spray........................................
5 3.7 Aging.................................................
6 3.8 Radiation.............................................
6 4
Qualification of Equipment.................................
7 4.1 Equipment Requiring Immediate Corrective Action.......
7 4.2 Equipment Requiring Additional Information and/or Corrective Action.....................................
8 4.3 Equipment Considered Acceptable or Conditionally Acceptable............................................
9 5
Deferred Requirements......................................
9 6
Conclusions................................................
10 APPENDIX A Equipment Requiring I7 mediate Corrective Action APPENDIX B Equipment Requiring Additional Information and/or Corrective Action APPENDIX C 2quipment Considered Acceptable or Conditionally Acceptable APPENDIX 0 Safety-Related Systems List iii
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1 SAFETY EVALUATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT QUALIFICATIM BRANCH l
FOR BALTIMORE GAS AND ELECTRIC COMPANY CALVERT CLIFFS UNITS 1 AND 2 DOCKET NO. 50-317/318 ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT 1 INTRODUCTION l
General Design Criteria 1 and 4 specify that safety-related electrical equip-ment in nuclear facilities must be capable of performing its safety-related function under environmental conditions associated with all normal, abnormal, and accident plant operation.
In order to ensure compliance with the cri-teria, the NRC staff required all licensees of operating reactors to submit a reevaluation of the qualification of safety-related electrical equipment which may be exposed to a harsh environment.
2 BACKGROUND 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 nrograms.
l Subsequently, Commission Memorandum and Order CLI-80-21 (issued on May 23, 1980) states that the 00R 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 10 CFR 50, Appendix A, General Design Criterion (GDC)-4. This order also i
requires the staff to complete safety evaluation reports (SERs) for all operating l
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 l
of the staff's needs.
These supplements were issued on February 29, September 30, and L:tober 24, 1980.
i 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 the licensees provide a report, by November 1, 1980, documenting the qualification of safety-related electrical equipment. The October order required the establishment of a central file location for the maintenance of all equipment qualification reccrds.
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.
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response, the licensee subnitted information through letters dated March 3 and 5, April 17, May 17, and October 31, 1930.
2.1 Pt. sose 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 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 ine 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 00R guidelines and in NUREG-0588, in part, were ased as a basis for the staff evaluation of the adequacy of the licensee's qualification program.
The NRC Offic'e 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 (October 27-29, 1980) of selected safety-related electrical equipment. The condensate and feedwater systems were inspected at Unit 1; the compressed air system was inspected at Unit 2.
The inspection at both units verified proper installation of equip-ment, 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 licen-see's report.
The site inspection is documented for Units 1 and 2 in reports IE 50-317/80-20 and 318/80-18, respectively. 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 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.
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 2
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 subraittal, 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) containnant 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 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 riELC 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-cation of post-accident sampling and monitoring and radiation monitoring equipment is closely related to the review of the TMI Lessons-Learned modifications and will be performed in conjunction with that review.
The licensee identified 227 items of equipment which were assessed by the staff.
Because Units 1 and 2 are nearly identical, the review can be per-l formed as one. Differences in the units will be identified by a parenthetical expression, with the applicable unit number enclosed.
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3.2 Service Conditions l
Commission Memorandum and Order CLI-60-21 requires that the 00R guidelines and the "For Comment" NUREG-0588 are to be used as the criteria for establishing the adequacy of the safaty-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.
On this basis, the staff has assumed, unless otherwise noted, that the analysis for developing the environmental envelopes for Calvert Cliffs Units 1 l
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and 2, relative to the temperature, pressure, and the containment spray caus-tics, has been performed in accordance with the requirements stated above. The staff has reviewed the qualification documentation to ensure that the quali-fication 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 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 DOR guidelines.
Equipment submergence has also been addressed where the possibility 2xists 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 276 50 100 MSLB 269 44.5 100 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 followir.g 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.
The licensee's specified temperature (service condition) of 276 F does not satisfy the above requirement.
A saturation temperature corresponding to the peak profile (296'F peak temperature at 50 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.
3.4 Temperature, Pressure, and Humidity Conditions Outside Containment The licensee has provided the temperature, pressure, humidity and applicable environment associated with an HELB outside containment.
The following areas outside containment have been addressed:
(1) ECCC pump room (A119)
(2) Containment recirculation pipe tunnel (A122) 4
(3) West penetration room (A221)
(4) Piping area (A224 and A428)
(5) Radiation exhaust ventilation equipment room (A225)
(6) East penetration room (A227).
(7) Main steam piping penetration (A315)
(8) East piping penetration room (A316)
(9) Spent fuel filter room (A328)
The staff has verified that the parameters identified by the licensee for the MSLB are acceptable.
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.
i The licensee's value for maximum submergence is 16 ft 4 in.
Equipment below this level has been identified by the licensee, along with the proposed cor-rective action. The licensee identified five safety-related electrical components for Unit 1 and seven for Unit 2 as having the potential for becom-ing submerged after a postulated event.
As a corrective action, the licensee proposes replacing these components; in some cases, the licensee is consider-ing relocation of the components.
The licensee has replaced the components in Unit 1 and has stated that the components in Unit 2 will be replaced before startup from the current outage.
Based on its review of the licensee's submittal, the staff concurs with the proposed resolution.
In one instance, the licensee stated that the component in question--a l
solenoid valve in Unit 2-performs its function in less than 7 seconds, fails l
closed, and is not required to operate after a LOCA.
In this case, the licensee should provide an assessment of the failure modes associated with the submergence of the solenoid valve. The licensee should also provide assurance that the subsequent failure of this component will not adversely affect any other safety functions or mislead in 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 the solenoid valve may be exempt from the submergence param-eter of qualification.
It is not clear from the information submitted that submergence of safety-related electrical equipoment outside of containment was addressed. The licensee should address this area more specifically in the 90-day response and upgrade the CES as appropriate.
l 3.6 Chemical Spray The licensee's FSAR value for the chemical concentration is 1700 ppm boric acid solution; the exact volume percent used by the vendor for qualification l
testing is being verified by the licensee.
Therefore, for the purpct,a of this review, the effects of chemical spray will be considered unresolved. The staff will re"iew the licensee's response when it is submitted and discuss the resolution in a supplemental report.
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3.7 A_ging Section 7 of the 00R guidelines does not require a qualified life to be estab-lished for all safety-related electrical equipment.
However, the following actions are required:
(1) Make a detailed comparison of existing equipment and the materials identified in Appendix C of the D0R guidelines.
The first supplement to IEB-79-018 requires licensees to utilize the table in Appendix C and identify any additional materials as the result of their effort.
(2) Establish an ongoing program to review surveillance and maintenance records to identify potential age-related degradations.
(3) Establish component maintenance and replacement schedules which include considerations of aging characteristics of the installed components.
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 en state-of-the-art technology and are acceptable.
For this review, however, the staff requires that the licensee submit supple-mental information to verify and identify the degree of conformance to the above requirements.
The response should include all the equipment identified as required to maintain functional operability in harsh environments.
The licensee indicated that this phase of the response is outstanding and that the review is in progress.
The staff will review the licensee's response when it is submitted and discuss its evaluation in a supplemental report.
3.8 Radiation (Inside and Outside Containment)
The licensee has provided values for the radiation levels postulated to exist following a LOCA.
The application and methodology employed to determine these l
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-79-018, Supplement 2.
Therefore, for this review, the staff has assumed l
that, unless otherwise noted, the values provided have been determined in l
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 1 x 108 rads.
This value envelopes the DOR guideline requirements and is therefore acceptable.
A required value outside containment of greater than 10 1 rads has been used by the licensee to specify limiting radiation levels within the ECCS pump room of the auxiliary building.
This value does not appear to consider the radiation levels 6
influenced by the source term methodology associated with post-LOCA recircula-tion fluid lines.
The licensee must correct this along with the associated equipment summary sheets.
The licensee stated that this revin was in progress and will be completed by February 1, 1981, and the results submitted to the staff.
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.
l The staff has separated the safety related equipment into three categories:
l (1) equipment requiring immediate corrective action, (2) equipment requiring additional qualification information and/or corrective action, and (3) equip-ment considered acceptable if the staff's concern identified in Section 3.7 is satisfactorily resolved.
In its assessment of the licensee's submittal, the NRC staff did not review the methodology employed to determine the values established by the licensee.
However, in reviewing the data sheets, the staff made a determination as to the stated conditions presented by the licensee.
Additionally, the staff has not completed its review of supporting documentation referenced by the licen-l see (for example, test reports).
It is expected that when the review of test i
reports is complete, the environmental qualification data bank established by the staff will provide the means to cross reference each supporting document I
to the referencing licensee.
If supporting documents are found to be unacceptable, the licensee will be t
l required to take additional corrective actions to either establish qualifi-cation or replace the item (s) of concern.
This effort will begin in early 1961.
An appendix for each subsection of this report provides a list of equipment for which additional information and/or corrective action is required. Where appropriate, a reference is provided in the appendices to identify deficiencies.
It should be noted, as in the Commission Memorandum and Order, that the deficien-cies identified do not necessarily mean that equipment is unqualified.
- However, they are cause for concern and may require further case-by-case evaluation.
l 4.1 Equipment Requiring Immediate Corrective Action i
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.
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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 l
RT - required time P
pressure H
- humidity CS - chemical spray A
- material-aging evaluation; replacement schedule; ongoing equipment surveillance S
- submergence M
- margin I
- HELB evaluation outside containment not completed QM qualification method RPN - equipment relocation or replacement; adequate schedule not provided EXN exempted etsipment 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 mqualified.
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 I
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-l failure criterion.
(4) Equipment will not be subjected to a harsh environment as a result of the postulated accident.
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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 for its completion (as applicable), and so forth. The staff will review the licensee's response, when it is submitted, and discuss the resolution in a supplemental report.
It should be noted that in cases where testing is being conducted, a condition may arise which results in a determination by the licensee that the equipment does not satisfy the qualification test requirements.
For that equipment, the licensee will be required to provide the proposed corrective action, on a timely basis, to ensure that qualification can be established by June 30, t
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 l
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.
t 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-l 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 associateo 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.
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1 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 definea by this SER and has found no outstanding items which would require immediate corrective action to ensure the safety of plant t
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 i
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, l
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 deficiencies.
The licensee has completed a preliminary review of the identified deficiencies and has determined that, after due consideration of the deficiencies and their ramifications, continued safe operation would not be adversely affected.
Based on these considerations, the staff conclude: 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 reasor,able 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-l tive action to assure safety of plant operation l
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(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 re:11t from low probability events; events which might reasonably be anticipated during this very limited period woul.1 lead to less demanding service conditions for this equipment.
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APPENDIX A Equipment Requiring Immediate Corrective Action (Category 4.1)
Equipment Description Manufacturer Component No.
No equipment in this category for Calvert Cliffs Units 1 and 2.
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APPENDIX B Equipment Requiring Additional Information and/or Corrective Action (Category 4.2) i 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, ongaing equipment surveillance 5 - Submergence M - Margin I - HELB evaluation outside containment not completed l
QM - Qualification method RPN - Equipment relocation or replacenant, adequate schedule not provided EXN - Exempted equipment justification inadequate SEN - Separate effects qualification justification inadequate QI - Qualification information being developed RPS - Equipment relocatioa or replacement schedule provided Equipment Description Manufacturer Component No.
Deficiency Solenoid valve ASCO ISV1412 A,CS l
Solenoid valve' ASCO 1SV1411 A,CS Solenoid valve ASCO ISV1410 A,CS Solenoid valve ASCO ISV641 A,CS Solenoid valve ASCO ISV631 A,CS Solenoid valve ASCO ISV621 A,CS l
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APPENDlX B (continued)
Equipment Desc.iption Manufacturer Component No.
Deficiency Solenoid valve ASCO ISV611 A,CS Solenoid valve ASCO ISV661 A,CS Soleonid valve ASCO ISV648 A,CS Solenoid valve ASCO 1SV638 A,CS Solenoid valve ASCO ISV628 A,CS Solenoid valve ASCO ISV618 A,CS Solenoid valve ASCO 1SV2085 A,CS Solenoid valve (1)
ASCO ISV5465 A.S,RPN Solenoid valve (1)
ASCO 1SV5466 A,S,RPN Solenoid valve (1)
ASCO 1SV5467 A,S,RPN Solenoid valve (2)
ASCO 2SV5465 A,5,RPN Solenoid valve (2)
ASCO 2SV5466 A,5,RPN Solenoid valve (2)
ASCO 2SV5467 A,S,RPN Solenoid valve (2)
ASCO 2SV506 A,S,RPN Connector Bendix CONXXX-3902-1 R,T,QT,RT, CS,A,QM,QI Connector Kings CONXXX-KC59-503 R,T,QT,RT,H CS,A,QM,QI Connector Kings CONXXX-KM5905 T;QT,RT,H, CS,A,S,M,QI Connector AmPhenol CONXXX-82-320-1004 R,T,QT,RT,H, CS,A,QM,QI Connector ITT CANNON CONXXX-19457 R,T,QT,RT, (GREMAR)
H,CS,A,QM,QI Connector ITT CANNON CONXXX-279-75 T,QT,RT,CS,A (GREMAR)
QM,M,QI J
Connector AmPhenol CONXXX-531000 R,T,QT,RT, CS,A,QM,QI (1) Unit 1 (2) Unit 2 B-2
APPENDIX B (continued)
Equipment Description Manufacturer Component No.
Deficiency Motor-Operated Valve Limitorque IMOV5463 QT,A,QM Motor-0perated Valve Limitorque 1M0V5462 QT,A,QM i
Motor Johnson 1M05439 QT,RT,A,QM Motor Reliance 1M0448 QT,RT,A,QM Motor General 1M0403 T,QT,RT,H Electric A,QM Motor-0perated Valve Limitorque IMOV6903 QT,RT,A Motor-Operated Valve Pratt IMOV6902 T,QT,RT,A,QM Motor-Operated Valve Limitorque IMOV6901 QT,RT,A Motor-Operated Valve Limitorque IMOV6900 T,QT,RT,A,M Heater Westinghouse lQ04 QT,RT,CS,A Heater Westinghouse lQ08 QT,RT,CS,A Motor Johnson 1M05437 QT,RT,A,QM Motor Reliance 1M1448 QT,RT,A,QM Motor-0perated Valve Limitorque IMOV644 QT,RT,A,M Motor-Operated Valve Limitorque IMOV634 QT,RT,A,M Motor-Operated Valve Limitorque IMOV624 QT,RT,A,M Motor-0perated Valve Limitorque IMOV614 QT,RT,A,M Motor-Operated Valve Limitorque IMOV656 QT,RT,A,QM Motor-Operated Valve Limitorque IMOV660 QT,RT,A,Qir Motor-Operated Valve Limitorque IMOV659 QT,RT,A,QM Motor-0perated Valve Limitorque IMOV4145 QT,RT,A Motor-0perated Valve Limitorque IMOV4144 QT,RT,A B-3
APPENDIX B (continued)
Equipment Description Manufacturer Component No.
Deficiency Motor-Operated Valve Limitorque IMOV652 QT,RT,A,M Motor-Operated Valve Limitorque 1MOV651 QT,RT,A Motor-0perated Valve Limitorque IMOV625 QT,RT,A Motor-0perated Valve Limitorque IMOV615 QT,RT,A Motor General 1MA404 QT,RT,A,QM Electric Motor General 1MA104 QT,RT,A,QM Electric Motor-0perated Valve Limitorque IMOV626 QT,RT,A,QM Motor-0perated Valve Limitorque IMOV616 QT,RT,A,QM Motor-0perated Valve Limitorque 1M0V627 QT,RT,A,QM Motor-Operated Valve Limitorque IMOV617 QT,RT,A,QM l
Motor General 1MA110 QT,RT,A,QM Electric Motor General 1MA408 QT,RT,A,QM Electric Motor General 1MA108 QT,RT,A,QM Electric Motor-Operated Valve Limitorque 1MOV654 QT,RT,A,QM i
Motor-Operated Valve Limitorque IMOV655 QT,RT,A,QM Motor-0perated Valve Limitorque IMOV653 QT,RT,A,QM Motor Allis-Chalmers 1MA407 QT,RT,A,QM Motor Allis-Chalmers IMA107 QT,RT,A,QM Solenoid Valve ASCO 1SV4151 RT,A Solenoid Valve ASCO 1SV4150 RT,A B-4 l
l
APPENDIX B (continued)
Equipment Description Manufacturer Component No.
Deficiency Radiation Monitor Westinghouse 1RE5316 0 R,T,QT,RT,P, CS,A,QM Radiation Monitor Westir.ghouse 1RE5316 C R,T,QT,RT,P, j
CS,A,QM Radiation Monitor Westinghouse 1RE5316 B R,T,QT,RT,P, CS,A,QM Radiation Monitor Westinghouse 1RE5316 A R,T,QT,RT,P, CS,A,QM Motor-Operated Valve Limitorque 1M0V6579 QT,A Proportional Counter Reuter Stokes 1NI004 (P)
R,QT,RT,CS,A,QM Propertional Counter Reuter Stokes 1NI002 (P)
R,QT,RT,CS,A,QM Proportional Counter Reuter Stokes 1NI001 (P)
R,QT,RT,CS,A,QM Preamplifier Gulf Atomic IPA 604 R,T,QT,RT,H,CS, A,QM Preamplifier Gulf Atomic 1PA603 R,T,QT,RT,CS, A,QM Fission Chamber Westinghouse 1NIG01 (F)
QM Fission Chamber Westinghouse 1NI002 (F)
R,QT,RT,H,I Fission Chamber Westinghouse 1NI003 (F)
R,QT,RT,H,CS,A, QM Fission Chamber Westinghouse 1NI004 (f)
R,QT,RT,H,CS,A, QM Preamplifier Gulf Atomic IPA 601 R,T,QT,RT,H,CS, A,0M Preamplifier Gulf Atomic IPA 602 R,T,QT,RT,H,CS, A,QM l
B-5 l
L
AFPENDIX B (continued)
Equipment Description Manufacturer Component No.
Deficiency Connector AmPhenol CONXXX-30576-A QT,RT,CS,A,M Terminal Lug Thomas & Betts LUGXXX-53000 R,QT,RT,P,H,CS, Series A,QM Terminal Lug Thomas & Betts LUGXXX-34000 QT,RT,CS,A,QM Series Terminal Block Buchanan TBXXXX-B112 QT,RT,CS,A, QM Terminal Block Westinghouse TBXXXX-542247 R,QT,RT,CS,A, QM,M Terminal Block Marathon TBXXXX-1600 QT,RT,CS,A,M Series Cable Rockbestos QT,RT,CS,A Cable Hatfield QT,RT,CS,A,M Cable Lewis Engrg. Co.
QT,RT,A,M Cable Xerite QT,RT,CS,A,M Cable Cerro QT,RT,A, Cable Boston Insul.,
QT,RT,CS,A,M Wire Cable Continental QT,RT,CS,A,M Cable Boston Insul.,
QT,RT,CS,A Wire Cable Raychchem QT,RT,H,CS,A Cable Okonite QT,RT,CS,A Cable Anaconda QT,RT,CS,A Cable Anaconda QT,RT,A B-6
APPENDIX B (continued)
Equipment Description Manufacturer Component No.
Deficiency EPA Type 3A AmPhenol SAMS 1ZWE9 QT,RT,CS,A,M Penetration Assembly i
EPA Type 3A AmPhenol SAMS lZWE3 Q T, RT,CS, A,M Fenetration Assembly EPA Type 3A AmPhenol SAMS 1 ZEE 9 QT,RT,CS,A,M Penetration Assembly EPA Type 3A AmPhenol SAMS lZWE4 QT,RT,CS,A,M Penetration Assembly EPA Type 3D AmPhenol SAMS lIWE7 QT,RT,CS,A,M Penetration Assembly EPA Type 3D AmPhenol SAMS 1ZWG1 QT,RT,CS,A,M Penetration Assembly EPA Type 3D AmPhenol SAMS 12EE1 QT,RT,CS,A,M Penetration Assembly EPA Type 3D AmPhenol SAMS lZEE1 QT,RT,CS,A,M Penetration Assembly Solenoid Valve ASCO ISV3830 QT,RT,A,QM Solenoid Valve ASCO 1SV3828 QT,RT,A,QM l
Solenoid Valve ASCO ISV4160 RT,A Solenoid Valve ASCO ISV4159 RT,A Motor Reliance 1MB414 QT,RT,CS,A,M Motor Reliance 1M8402 QT,RT,CS,A,M i
B-7
APPENDIX B (continued)
Equipmer.t Description Manufacturer Component No.
Deficiency Motor Reliance 1MB114 QT,RT,CS,A,M Motor Reliance 1MB102 QT,RT,CS,A,M Motor Reliance 1MB121 QT,RT,CS,A,M Motor Reliance 1MB405 QT,RT,CS,A,M Motor Reliance 1MB105 QT,RT,CS,A,M Motor-Operated Valve Limitorque 1MOV2080 H,A Motor-Operated Valve Limitorque 1MOV4516 QT,RT,A l
Motor-Operated Valve Limitorque 1MOV4517 QT,RT,A 1
l EPA Type 2D AmPhenol SAMS 1ZEC4 QT,RT,CS,A,M t
Assembly EPA Type 2C AmPhenol SAMS 1ZEC1 QT.RT,CS,A,M i
Penetration Assembly EPA Type 28 AmPhenol SAMS 12EB6 QT,RT,CS,A,M Penetration Assembly EPA Type 28 AmPhenol SAMS 1ZEB3 QT,RT,CS,A,M Penetration Assembly i
EPA Type 28 AmPhenol SAMS 1ZEB1 QT,RT,CS,A,M Penetration Assembly EPA Type 2A AmPhenol SAMS 1ZEA7 QT,RT,CS,A,M Penetration Assembly l
EPA Type 2A AmPhenol SAMS 1ZEA4 QT,RT,CS,A,M Penetration Assembly EPA Type ~'
AmPhenol SAMS IZWC6 QT,RT,CS,A,M l
Penetration Assembly B-8
APPENDIX B (continued)
Equipment Description Manufacturer Component No.
Deficiency EPA Type 20 AmPhenol SAMS 1ZWC4 QT,RT,CS,A,M Penetration Assembly EPA Type 2C AmPhenol SAMS 1ZWC1 QT,RT,CS,A,M Penetration Assembly EPA Type 28 AmPhenol SAMS 1ZWB7 QT,RT,CS,A,M Penetration Assembly EPA Type 28 AmPhenol SAMS 1ZWB2 QT,RT,CS,A,M Penetration Assembly EPA Type 28 AmPhenol SAMS 1ZWB1 QT,RT,CS,A,M Penetration Assembly EPA Type 2A AmPhenol SAMS 12WA6 QT,RT,CS,A,M Penetration Assembly EPA Type 2A AmPhenol SAMS lZWA3 QT,RT,CS,A,M Penetration Assembly EPA Type 2C AmPhenol SAMS 1ZEC9 QT,RT,CS Penetration Assembly EPA Type 2D AmPhenol SAMS 1ZEC6 QT,RT,CS,A,M Penetration Assembly Solenoid Valve Dragon 1SV6540F R,T,QT,RT,CS, A,QM,RPN Solenoid Valve Dragon 1SV6540E R,T,QT,RT,CS, A,QM,RPN Solenoid Valve Dragon 1SV65400 R,T,QT,RT,CS, A,QM,RPN Solenoid Valve Dragon 1SV6540C R,T,QT,RT,CS, A,QM,RPN B-9
APPENDIX B (continued)
Equipment Descriptico Manufacturer Component No.
Deficiency Solenoid Valve Dragon 1SV6507B QT,RT,A,QM,RPN Solenoid Valve Dragon 1SV6507C QT,RT,A,QM,RPN Solenoid Valve Dragon 1SV65070 QT,RT,A,QM,RPN Solenoid Valve Dragon 1SV6507E QT,RT,A,QM,RPN Solenoid Valve Dragon 1SV6507F QT,RT,A,QM,RPN Solenoid Valve Dragon 1SV6507G QT,RT,A,QM,RPN Solenoid Valve Dragon 1SV6540A R,T,QT,RT,CS, A,QM,RPN Solenoid Valve Dragon 1SV65408 R,QT,RT,CS,A, QM,RPN Solenoid Valve Dragon 1SV6507A QT,RT,A,QM, RPN Solenoid Valve Dragon 1SV6540G R,T,QT,RT,CS, A,4M,RPN Flow Transmitter Fischer & Porter 1FT6901 QT,RT,A,QM,RPN Solenoid Valve ASCO ISV5292 R,T,QT,A,QM,RPN Pressure Trans;nitter Fischer & Porter 1PT1020 QT,RT,CS,A,QM,RPN Pressure Transmitter Fischer & Porter 1PT102C QT,RT,CS,A,QM,RPN Pressure Transmitter Fischer & Porter 1PT1028 QT,RT,CS,A,QM,RPN Pressure Transmitter Fischer & Porter 1PT102A QT,RT,CS,A,QM,RPN i
Pressure Transmitter Fischer & Porter 1PT103-1 QT,RT,CS,A,QM,RPN Pressure Transmitter Fischer & Porter 1PT103 QT,RT,CS,A,QM,RPN RTD*
Rosemount 1TE122CD R,QT,RT,CS,A,QM, M,RPN l
RTD Rosemount 1TE122CB R,QT,RT,CS,A,QM, i
M,RPN j
B-10
APPENDIX B (continued)
Equipment Description Manufacturer Component No.
Deficiency RTD Rosemount 1TE122CC R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE122CA R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE122HD R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE122HC R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE122HB R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE122HA R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE112CD R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE112CB R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE112CC R,QT,RT,CS,A,QM, M,RPN RTD Rosemount ITE112CA R,QT,RT,CS,A,QM, M,RPN l
1 RTD Rosemount 1TE112HD R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE112HC R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE112HB R,QT,RT,CS,A,QM, M,RPN RTD Rosemount 1TE112HA R,QT,RT,CS,A,QM, M,RPN Pressure Transmitter Fischer & Porter 1PT10230 QT,RT,CS,A,QM,RPN Pressure Transmitter Fischer & Porter 1PT1023C QT,RT,CS,A,QM,RPN B-11
APPENDIX B (continued)
Equipment Description Manufacturer Component No.
Deficiency Pressure Transmitter Fischer & Porter 1PT10238 QT,RT,CS,A,QM,RPN Pressure Transmitter Fischer & Porter 1PT1023A QT,RT,CS,A,QM,RPN Pressure Transmitter Fischer & Porter 1PT10133 QT,RT,CS,A,QM,RPN Pressure Transmitter Fischer & Porter 1PT10138 QT,RT,CS,A,QM,RPN Pressure Transmitter Fischer & Porter 1PT1013A QT,RT,CS,A,QM,RPN Solenoid Valve ASCO ISV4013 R,T,QT,RT,P,H,CS, A,QM,RPN Solenoid Valve ASCO 1SV4012 R,T,QT,RT,P,H,CS, A,QM,RPN Solenoid Valve ASCO ISV4011 R,T,QT,RT,P,H,CS, A,QM,RPN Solenoid Valve ASCO ISV4010 R,T,QT,RT,P,H,CS, A,QM,RPN Solenoid Valve ASCO ISV1589 R,T,QT,RT,P,H,A, QM,RPN i
Solenoid Valve ASCO ISV1591 R,T,QT,RT,P,H,A, QM,RPN Solenoid Valve ASCO 1SV1581 R,T,QT,RT,P, H,A,QM,RPN Solenoid Valve ASCO 1SV1583 R,T,QT,RT,P, H,A,QM,RPN Solenoid Valve ASCO ISV1590 R,T,QT,RT,P, I
H,A,QM,RPN Solenoid Valve ASCO ISV1582 R,T,QT,RT,P, H,A,QM,RPN Solenoid Valve ASCO 1SV3833 R,T,QT,RT,P, H,A,QM,RPN Solenoid Valve ASCO ISV3832 R,T,QT,RT,P, H,A,QM,RPN B-12
APPENDIX B (continued)
Equipment Description Manufacturer Component No.
Deficiency Level Transmitter Fischer & Porter 1LT1113A R,QT,RT,CS,A QM,RPN Level Transmitter Fischer & Porter 1LT11138 T,QT,RT,CS,A QM,RPN Level Transmitter Fischer & Porter 1LT1113C R,QT,RT,CS,A QM,RPN Level Transmitter Fischer & Porter 1LT1113D R,QT,RT,CS,A QM,RPN Level Transmitter Fischer & Porter 1LT1123A R,QT,RT,CS,A QM,RPN Level Transmitter Fischer & Porter 1LT11238 R,QT,RT,CS,A QM,RPN Level Transmitter Fischer & Porter 1LT1123C R,QT,RT,CS,A QM,RPN Level Transmitter Fischer & Porter ILT1123D R,QT,RT,CS,A QM,RPN Solenoid Valve Republic 1SV404?.
R,T,QT,RT,H,A, Teldyne QM,RPN Solenoid Valve Republic 1SV4045 R,T,QT,RT,H,A, Teldyne QM,RPN Solenoid Valve Republic 1SV4043 R,T,QT,RT,H,A, Teldyne QM,RPN Solenoid Valve Republic 1SV4044 R,T,QT,RT,H,A, Teldyne QM,RPN Solenoid Valve Republic 1SV4046 R,T,QT,RT,H,A, Teldyne QM,RPN Solenoid Valve Republic 1SV4052 R,T,QT,RT,H,A, Teldyne QM,RPN Solenoid Valve Republic 1SV4047 R,T,QT,RT,H,A, Teldyne QM,RPN B-13
~. - -
APPENDIX C Equipment Considered Acceptable Or Conditionally Acceptable (Category 4.3)
Equipment Description Manufacturer Component No.
Deficiency Solenoid Valve ASCO 1SV1413 A
Solenoid Valve ASCO ISV517 A
Solenoid Valve ASCO 1SV5291 A
Solenoid Valve ASCO ISV643 A
Solenoid Valve ASCO 1SV633 A
Solenoid Valve ASCO ISV623 A
Solenoid Valve ASCO ISV613 A
i Solenoid Valve ASCO ISV516 A
Solenoid Valve ASCO ISV515 A
Solenoid Valve ASCO 1SV519 A
Solenoid Valve ASCO 1SV518 A
C-1
APPENDIX 0 Safety-Related Systems Listi Function System Emergency Reactor Shutdown Chemical Volume and Control Reactor Coolant Safeguards Actuation (Part of Reactor Coolant)
Containment Isolation Chemical and Volume Control Compressed Air Condensate and Feedwater Cooling Water Main Steam Plant Heating Reactor Coolant and Waste Process Sample Safety Injection and Containment Spray Samplir.g Waste Processing 1
I Reactor Core Cooling Safety Injection and Containment Spray Containment Heat Removal Safety Injection and Containment Spray Containment Air Recirculation and Cooling l
t LThe NRC staff recognized that there are differences in nomenclature of systems because of plant vintage and engineering design, consequently, some systems performing identical or similar functions may have different names.
In those instances, it was necessary to verify the function of the system (s) with the responsible IE regional reviewer and/or the licensee.
0-1
..,. ~. _ - _
APPENDIX 0 (continued)
Function System Core Residual Heat Removal (Residual Heat Removal 3)
Auxiliary Feedwater2 Condensate and Feedwater Main Steam Cooling Water Safety Injection and Containment Spray Prevention of Significant Containment Air Recirculation and Release of Radioactive Cooling Material to Environment Radiation Monitoring Sampling Supporting Systems Electrical Ventilation 2 Covered as part of TMI-2 Lessons Learned; does not appear in systems list.
3 Residual heat removal is performed by a number of systems.
Some components are being addressed as part of TMI-2 Lessons Learned.
0-2
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