ML19341C045
| ML19341C045 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 02/11/1981 |
| From: | Novak T Office of Nuclear Reactor Regulation |
| To: | Abel J COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8102280511 | |
| Download: ML19341C045 (49) | |
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i NUCLEAR REGULATORY COMMISSION
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February 11,1981 Dockets Nos. 50-295 and 50-304 c
A Mr J. S. Abel 3
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Director of Nuclear Licensing pO 2 7193Isii:-
Commonwealth Edison Company C
Post Office Box 767 Q%g
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Dear Mr. Abel:
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SUBJECT. ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT RE:
Zion Station, Unit No.1, Facility Operating License No. DPR-39 Zion Station, Unit No. 2. Facility Operating License No. DPR-48
Reference:
Order for Modification of License Concerning the Environmental Qualification of Safety-Related Electrical Equipment, October 24, 1980.
This letter transmits the preliminary results of our review of environmental cualifications of safety-related electrical equipment at your facilities.
This evaluation was based on your submittals received ovor the past months.
The facilities' licenses were modified by the referenced Order of October 24, 1980, to require that all safety-related electrical equipment be qualified to l
soecified requirements not later than June 30, 1982.
In addition, the Order l
noted that a licensee is obligated to modify or replace inadequate equipment promptly.
t T"e staff's review of your submittals has resulted in our identifying a number of potential equipment deficiencies involving a lack of proper l
documentation, inadequate justification of assumed environmental conditions l
following an accident, and/or inadequate environmental testing of equipment, l
such that-conformance to the D0R guidelines, as required by the Order, cannot be demonstrated. You are requested to review our identified defi-l ciencies, and their ramifications, and provide us your overall finding l
regarding continued safe operation of your facilities. Accordingly, in order l
to determine whether your licenses should be modified or suspended, you are required pursuant *a 10 CFR 50.54(f), to provide within 10 days of receipt of this letter, a written statement, signed under oath or affirmation sup-porting the safe operation of your facilities, that takes into account the HRC staff's preliminary list of deficiencies.
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b 2-The purpose of this statement is to provide the NRC with needed ass'urance, by the licensee, regarding the continued safety of the facilities until you can provide an item-by-item reevaluation in a detailed documented manner at i.later date. A negative finding on your part concerning the safety of cer.tinued operation would result in a unit shutdown, and should be reported as a Licensee Event Report (LER) within twenty-four (24) hours of the deter-
.-/ ation to the appropriate NRC Regional Office.
Include in the LER the actions you have taken for the.immediate resolution of the matter.
A copy c' any such LER should be sent to the Director, Division of Licensing, Office c' Nuclear Reactor Regulation.
- lease submit a copy of your reply to us via telecepy.
Sincerely, Db Thomas M. Novak, Assistant Director for Operating Reactors Division of Licensing I :*esure:
E.z'.ua-icn Report
'er. closure:
3es ext page e
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s Mr. J. S. Abel Commonwealth Edison Company cc:
Robert J. Vollen, Esquire 109 North Dearborn Street Chicago, Illinois 60602 Dr. Cecil Lue-Hing Director of Research and Development Metropolitan Sanitary District of Greater Chicago 100 East Erie Street Chicago, Illinois 60611
-Zion-Benton Public Library District 2600 Emmaus Avenue Zion, Illinois 60099 Mr. Phillip P. Steptoe
-Isham, Lincoln and Beale Counselors at Law One First National Plaza 42nd Floor Chicago, Illinois 60603 Susan _ N. Sekuler, Esquire Assistant Attorney General Environmental Control Divisicn 188 West Randolph-Street, Suite 2315 Chicago, Illinois 60601 U. S. Nuclear Regulatory Commission Resident Inspectors Office 105 Shilch 21vd.
Zion, Illinois 60099 p
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Partial Review EGUIPMENT EV ALUATION REPORT BY THE OFFICE OF NUCL,E AR RE ACTOR REGULATION EQUIPMENT GU ALIFICATION BR ANCH FOR COMMONWEALTH EDISON CO.
IION NUCLEAR POWER STATION, UNIT NO.1 DOCKET NO. 50-295 ENVIRONMENT AL QU ALIFICATION OF S AFETY-REL ATED ELECTRICAL EQUIPMENT 3.0 STAFF EV ALUATION The staff's evaluation of the Licensee's responses was accompanied by performing an on-site inspection of selected Class IE ecuipment an'd by examining the Licensee's report for completeness and accept-ability. The criteria described in the DOR Guicelines and NUREG-0588, in part, were used as a basis for the staff's evaluation of the adequacy
- " : e.':ensee qualifi:ation program.
During the week of J une 2,1980, NRC and FRC re:resentatives visited the lien plant site, inspe::ed safety-related systes a : ecuipment, identified and taculated safety-e' ate: components througn d's:ussions with plant ersonnel, and concu::ed a general review of CE:2's su -it:al Of May 2, 1980.
ine inspe:: ion verifie: prc:er installation of e:vi:nen:, overalL interface integrity, and manuf acturers nameplate data. The manufacturer and model number f rom the nameplate data was compared to informatien given in the Licensee's succittal.
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The following evaluation incorporates the CECO submittal and the Franklin Research Center technical evaluation report (TE R).
3.1 COMPLETENESS OF SAFETY-RELATED EQUIPMENT In accordance with the DOR guidelines, the licensee was directed to establish a list of systems and display instrumentation needed to mitigate the consequences of a LOCA or HEL8, inside or outside con-tainment, and reach safe shutdown. The lists of safety related systems and display instrumentation were developed from a review of plant safety analyses and emergency procedures. The display instrumentation selected includes parameters to monitor overall plant performance as well as to monitor performance of the systems on the list. The-systems list was established on the basis of the functions that must be performed for
.itigation of the consequences of a LOCA or HELS without regard to location of equipment relative to a potentially hostile environment.
The staf f has determined and verified that the system considered by the licensee are those required to achieve or support: (1 ) emergency reactor shutdown, (2) containment isolation, (3 ) reactor core cooling, (4) con-tainment heat removal, (5) core recidual heat removal, and (6) prevention of significant release of radioactive material to the environment. The staff concludes that the systems identified by the licensee are accept-able. The systems and instrumentation list is contained in Appendix 0.
The licensee submitted an extensive list of safety-related electrical
- equipment. This list was evaluated and identical components witnin 2
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e a plant area exposed to the'same environment were grouped; 102 item types of equipment were identified and assessed by the staff. Items with exceptions are discussed in section 5.0 of this report.
3.2 Service Conditions The commission Memorandum and Order (CLI-80-21), dated May 23,1980 requires that the DOR Guidelines and the "For Comment" NUREG-0588 are to be used as the criteria for establishing the adequacy of the safety related electrical equipment environmental qualification program. These documents. provide the option of establishing a bounding pressure and temperature condition based on plant specific analysis identified in the licensees -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. Zion 1 relative to the temperature, pressure, and the-containment spray caustics, have been' performed in accordance with the acove stated requirments.
For this review the staff reviewed the qualification documentation to ensure that the qualification specifications envelete the conditions established by_the-licensee. During this review the sta'f assumed that for plants, designed and equipped with an automatic containment spray system, which satisfies the single failure criterion, the main steam line break environmental conditions are enveloped by the large break LOCA environmental conditions. The staff assumed and requires that the licensee verifies, that the containment spray system is not subjected to a disabling single component failure and therefore satisfies the 00R Guideline requirements of Section 4.2.1.
Equipment submergence has also been addressed where the possibility exists that flooding of equipment may result f rom high energy line breaks (HELB).
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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 271 47 100%
MSLB N/A N/A N/A 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 Jdue 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.
The licensee's specified temperature (service condition) of 271 F does not satisfy the above requirement. A saturation temperature corresponding to the pressure profile (295 F peak temperature at 47 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 environmental values associated with a HELB outside containment in the following plant areas:
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Upper Safety Valve Room
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Lower Safety Valve Room 3.
Main Steam & Feedwater Pipe Tunnel 4.
Tendon Tunnel 5.
Aux. building (elev. 579 feet) 6.
Aux. building (elev. 592 feet) 7.
Seal. water heat exchanger rooms.
8.
Pipe tunnels and penetration areas 9.
Centrifugal charging pump rooms 10.
RHR heat exchanger rooms 11. Boric acid evaporator and RAD waste rooms The staf f 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. The staff assumed for this review, unless, otherwise noted, that the methodology employed by the licensee is in accordance with the appropriate criteria as established by the Commission Memor-andum and Order CCLI-80-21), dated May 23, 1980. The licensee's value for maximum submergence is 3.5 feet (elev. 581.5 f eet).
The licensee has icentified 4 equipment items models below this level.
The staff concurs with the Licensee's position as presented in the TER, 4
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i (1 ) operation is not required post LOCA and is therefore exempt from qualification, one item, and (2) f ailure due to submergence does not result in degradation of the capability to attain safe shutdown, one item.
Based on the TER the staff has determined that qualification is required for two items; interim justification for continued operation has been provided by the Licensee.
The Licensee should provide an assessment of the failure modes associated with the submergence of equipment. Assurance should also be provided that the subsequent failure of this equipment will not adversely affect any other safety functions or mislead an operator.
Additionally, the Licensee should discuss operating time, across the spectrum of events, in relation to the time of submergence. If the results of the licensee's assessment are acceptable, then the equipment may be exempt from the submergence parameter of qualification.
3.6 Chemical Spray The Licensee's FS AR value for the chemical concentration is 2500-3000 PPM boric acid solution. The exact volume percent used by the vendors for qualification testing should be verified by the Licensee. Therefore, for the purpose of this review the effects of chemical spray will'be considered unresolved.
3.7 Aging The 00R Guidelines, section 7, does not require a qualified life to be established for aLL safety related electrical equipment, however the
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following actions are required:
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Detailed comparison of existing equipment to the materials identifed in Appendix C of the DOR guidelines. The first supplement to IEB-79-01B t'equires the licensees to utilize the table and identify any additional materials as a result of their effort.
2.
Establish an ongoing program to review surveillance and maintenance records to identify potential age related degradations.
3.
Establish comp'onent maintenance and replacement schedules which include considerations of aging characteristics of the installed components.
For this review the staff requires that the licensee submit supplemental information to verify and identify their degree of conformance to the above requirements. The response should be inclusive of all the equipment identified a's required to maintain their functional operability in harsh environments.
The staff will review the licensees response, when submitted, and report its evaluation in a supplemental report.
3.8 R ADIATION (INSIDE AND OUTSIDE CONTAINMENT)
The licensee has provided values for radiation levels postulated to exist following a LOCA event. The application anc metnodology employed to determine these values have been presented to the licensee as part of the NRC staff criteria contained in the DOR Guidelines, NUREG-0588 and the guidance provided in IEB-79-018, supplement 2.
The value required by the 6
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8 Licensee inside containment is an integrated dose of 1 x 10 RADS.
This value envelopes the D0R Guideline requirements and is therefore 7
acceptable. A required value cLtside containment of 2 x 10 RADS has been used by the licensee to specify limiting radiation levels within the centrifugal charging pump rooms of the auxiliary building. This value appears to consider the radiation levels influenced by the source term methodology associated with Post-LOCA recirculation fluid lines and is there-fore acceptable.
4.0 QUALIFICATION OF EQUIPMENT The following subsections are the staff's assessment, based on the licensee's subnittal, and the Franklin TER of the qualification status of safety-related electrical equipment.
T e staff has separated the safety-related equipment into three categories (1) equipment recuiring immediate corrective action, (2) equipment requiring additional qualification information and/or corrective action, and (3) equio-ment considered acceptable conditioned only on the satisfactory resolution of I
tne staff's concern identified in Section 3.7.
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The NRC staff in its assessment of the licensees submittal and the TER l
did not review the methodolngy employed to determine the values estab-l l
Lished by the licensee. However, in reviewing the TER a determination f
was made by the staff as to the stated condition presented by the licensee. Additionally, the detailed review of supporting documentation referenced by the licensee (e.g., test reports) has been completed by FRC.
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The environmental qualification data bank to be established by the staff wiLL provide the means to cross reference each supporting docu-cent to the referencing Licensee.
Where supporting documents were found to be unacceptable, the Licensee wiLL be required to take additional corrective actions to either establish qualification or replace the item (s) of concern. An appendix.for each subsection is attached which provides a list of equip-cent which requires additional information and/or corrective action.
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Where appropriate, a reference is provided in the appendices to identify
, ceficiencies. It should be noted, as in the Commission Memorandum and Order, that the deficiencies identified do not necessarily mean that equipment is uncualified. However, they are cause for concern and may require further case-by-case evaluations.
4.1 EQUIPMENT REQUIRING IMMEDI ATE CORRECTIVE ACTION G
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4.2 EQUIPMENT REQUIRING ADDITIONAL INFORMATION AND/OR CORRECTIVE ACTION Appendix B identifies equipment in this category including the tabulation of their deficiencies. The deficiencies are noted by a letter relating to the Legend, identified below, including that insufficient information has been provided for the qualification parameter or condition.
R - Radiation T - Temperature QT - Qualification Time RT - Required Time P - P ressure H - Humidity CS - Chemical Spray A - Material Aging Evaluation, Replacement Schecule, ongoing Equipment Surveillance S - Submergence M - Margin I - HELB Evaluation Outside Containner.- 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 GI - Qualification Information Being Developed l
RPS - Equipment Relocation or Replacement Schedule Provided.
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i As noted in Section 4.0, these deficiencies do not necessarily mean that the equipment is unqualified. However, they are cause for concern and require further case-by-case evaluations. 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 estab-lished and verified by the licensees:
(1 )
Equipment does not provide essential safety functions in the harsh environment and failure of it in the harsh environment will not impact safety related functions or mislead an operator.
(2a)
Equipment performs its function prior to its exposure to the harsh environment and the adequacy for the time margin provided is adequately justified, and (2 b)
Subsequent failure of the equipment as a result of the harsh environment does not degrade other safety functions or mislead the operator..
(3 )
The safety-related function can be accomplished by some other designated equipment that has been adequately qualified and satisfies the single failure criteria.
(4)
Equipment not subjected to a harsh environment as a result of the postulated accident.
The licensee is therefore required to supplement the information presented by providing their resolutions to the deficiencies identified which should include a description of the corrective action and schedules for its completion (as applicable), etc. The staf f will review the licensees response, when submitted, and report on the resolution in a supplemental report.
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It should be noted that where testing is presently being conducted, a l
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 their proposed corrective action, on a timely basis, to assure that qualifi-cation can be established by June 30, 1982.
4.3 EQUIPMENT CONSIDERED ACCEPTABLE OR CONDITIONALLY ACCEPTABLE Based on 'the staffs review of the licensees submitta! and the TER the staff identified the equipment in Appendix C as (1) acceptable on the basis that the qualification program adequately enveloped the specific environ-mental plant parameters, or (2) conditionally acceptable subject to the satis-factory resolution of the staff concern identified in Section 3.7.
For the equipment identified as conditionally acceptable the staff deter-mined that the licensee did not clearly:
(1) state that a material evaluation on their equipment was conducted to. assure. that no known materials susceptible to degradation due to aging have been used in their equipment.
(2) establish an ongoing program to review the surveillance and naintenance records of their plant in order tc fdentify 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 licensees response, when submitted, and report on the resolution in a supplemental report.
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f 5.0 DEFERRED REQUIREMENTS IE Bulletin 79-018, Supplement 3 has relaxed the time constraints for the submission 'of the information associated with cold shutdown equipment and TMI Lessons Learned modificatiorts. To permit a uniform program schedule the SEP plant reviews have been amended. The staff will require that this information be provided by February 1,1981. The staf f will provide a supplemental safety evaluation addressing these concerns.
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APPENDIX B List of Equipment in Section 4.2, Equipment Requiring Additional Informatten And/0r Corrective Action LEGEND:
Designatior, for Deficiency R - Radiation M - Margin T - Temperature I - HELB Evaluation Outside GT - Qualification Time Containment Not Completed RT - Required Time QM - Qualification Method P - Pressure RPN - Equipment Relocation or Replacement, H - Humidity' Adequate Schedule Not Provided CS - Chemical Spray EXN - Exempted Equipment J ustification A - Material Aging Evaluation, Inadequate Replacement Schedule, Ongoing SEN - Separate Ef f ects Qualification Equipment Surveillance Justification Inadequate S - Submergence QI - Qualification Information Being Developed RPS - Equipment Relocation or Replacement Schedule provided TER EQUIPMENT MODEL /
ITdM NC.
DESCRIPTION MANU FACTURER TYPE DE FICIENCIES 20 Junction box U NK EB-215 QM,3I,S,CS 21 Junction box U NK EB-214 QM,GI,5,CS 22 Junction box UNK EM-47150 QM,QI,S,CS 23 Junction box UMC UNK Q M,31,S, CS 38 J unction box UNK EM-47150 QM,GI,S,CS Terminal block Marathon 6000 QM,GI,S,CS 50 Junction box UNK EM-47150 QI,S,CS,A Terminal block Marathon 6000 QI,S,CS,A 51 Junction box UNK EB-214 QI,S,CS,A Terminal block Marathon 6000 QI,5,CS,A
-55 Junction box UNK EM-47L50 QI,S,CS,A B-1 b
APPENDIX B (CONTINUED)
TER EQUIP PENT MODEL/
ITEM NO.
DESCRIPTION MANU F ACTURER TYPE DE FICIENCIES 71 Junction box UNK EB-215 QI,S,CS,A Terminal block Marathon 6000 72 J unction bor UNK EM-47150 QI,S,CS, A Terminal block Marathon 6000 73 Junction box UNK EB-215 QI,S,CS,A Terminal block Marathon 6000 74 J unction box UNK E9-214 QI,S,CS,A Terminal block Marathon 6000 48 J unction box UNK E M-47150 QI,5,CS,A Terminal block Marathon 6000 7
SOV operator.
R,M,GM,QT 53 SOV operator ASCO H'X-8320 A25 GI,A,T,R LB-33146 LE-831654 H3X-8320 A26 66 SUV operator.
ASCO 8316E34 QI,A,T,R 68 Level switch Magnetrol 82-1212-002 QI 37 Remote shutdown UNK UNK QI,A panel 34 Electrical Westinghouse VX-252 Q I, A,T,P,R,M,G M indicators QT 6
Motor Westinghouse 585.5 CSP Q I, A,Q M 42 Motor UNK 36MP /184 A,R 56 Motor Westinghouse HSDP GI,A.
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Appendix B, Continued l
TER EQUIPMENT MODEL /
ITEM NO.
DESCRIPTION M ANU F A CTURER TYPE DE FICIEN CIES 16 Electrical D.G. O'Brien Type 4.1 A,CS,R penetrations 17 Electrical D.G. O'Brien Type 3.1 A,CS,R penetrations 18 Electrical D.G. O'Brien Types 2.1,
A,CS,R penetrations 2.2, 2.3 19 Electrical D.G. O'Brien Type 5.1 A,CS,R penetrations
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39A MOV Limitorque SMB-3-100 Q I, A,T,P,R, M,G T 1A MOV Limitorque SMB-3 QI,A,T 52C MOV Limitorque SMB-1 QI,QM,A,T,P,R,M, QT 52D MOV Limitorque SMB-0 QI,Q M, A,T,P,GT,R,
M 52E MOV Limitorque SMS-00 QI,GM,A,T,P,GT,R, M
52H MOV Limitorque SMB-000 Q I,G M, A,T,P,G T,R,
M 60 MOV Limitorque SMS-0 Q I,G M, A,T,P,3 T, R g M
43A Temperature United Electric C-300 QI,QM,A,R switch 12 Resistance SOSTMAN UNK QI,A,S,CS,R temperature detectors 69 Electrical
.Weschler UNK QI,GM,A,T,P,GT,R, indicator M
75 Electrical D.G. O'Brien Type 1.1 GI,A,GM,CS,R penetration 76 Electrical D.G. O'Brien Type 5.2 QI,A,QM,CS,R penetration 44 Hydrogen GE SK182 QI,A,R recombiner OK742 blower B-3
APPENDIX B, Continued TER EQUIP MENT MODEL ITEM NO.
DESCRIPTION M ANU FACTURER TYPE DEFICIENCIES 5
Limit Swtich NAMCO E A180 A,GM,CS 11 Level Transmitter BARTON 386 QI,3M,A,QT,CS 8A Transmitter Fischer & Porter 1082496 QI,GM,A,QT,CS, P BBABBO-NS M,5 10A Transmitter Fischer & Porter 10B2491V QI,3M,A,GT,CS, CBB-NS M
108 Transmsitter Fischer & Porter 13D2495K QI,GM,A,GT,CS, BBABBB-NS M,5 10D Transmitter Fischer & Porter 50-EP1041 QI,QM,A,QT,CS, BCX A-NS M
31 Motor Westinghouse HSDP GI,A,T SBDP 55 Motor UNK fype B QI,A,QM,T,P,QT, R,M 6'
Motor Westinghouse TBFC GI,A 73 Pressure Switch Barksdale 9672-3 QI,GM,A,T,P,GT, R,M 33 Transmitter Fischer & Porter 1082495 QI,GM,A,QT,M 6-E MOV Limitoraue S MB-03-15 QI,GM,A,T,P,3T, R,M 65 SOV Operator ASCO HPX-8320 QI,A,T,P,QT A25, A26 67 07V Operator Ross 233693 QI,A,T,P,QT,R
.9 Level Switch Magnetrol A-153-FEP /
P,3T,S,CS VPX-Y-3X 3
SOV operator ASCO LBS31654 GI,A 18 2 SOV Operator ASCO THT-8316 QI,A,T,P,3T,CS,
-C34 R
62 P ressure Fischer & Porter 50EP104 RP S Transmitter LB CX A B-4
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APPENDIX C LIST 0F EQUIPMENT IN SECTION 4.3, EQUIPMENT CONSIDERED ACCEPTABLE OR CONDITION ALLY ACCEPT ABLE LEGEND:
A - Material Aging Evaluat' ion TER EQUIP MENT MODEL/
DEFICIENCIES ITEM NO.
DESCRIPTION M ANU FACTURER TYPE 24 Cable Boston Insulated CSPE/LSPE A
Wire & Cable Co.
78 Cable Boston Insulated CSPG /LSPE A
Wire & Cable Co.
25 Cable Kerite Corp.
V a rious A
28 Cable Kerite Corp.
V a rious A
26 Splices Raychem Corp.
UNK A
27 Splices Kerite Corp.
U NK A
77 Cable Anaconda V a rious A
77 Cable Okonite V a rious A
80 Cable Rockbestos V a rious A
S1 Cable Samuel Moore V a rious A
32A POV Limitorque SMB-2 A
52A POV Limitorque SMS-0 A
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MOV Limi t o r,que SMB-000 A
523 Mov Limitorque SMS-00-15 A
64A POV Limitorque.
SMB-2 A
l iD MOV Limitorque SMS-1 A
32C MOV Limitorque SMB-00 A
32)
'MOV-Limitorque SM8-000 A
l 32E MOV Limitorque SMS-000 A
399 POV Limitorque SMS-000 A
L 37 MOV Limitorque SMB-00-25 A
40-Motor Westinghouse TBLG A
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APPENDIX C, Continued TER EQUIPMENT MODEL/
DE FICIENCIES ITEM NO.
DESCRIPTION MANU F A CTURER TYPE 2
Limit Switch NAMCO DX-2400 13 Humidity sensor Taylor 10HS 14 Resistance UNK 3 Wire temperature detectors 36A Distribution Fischbach-B/M-C458 panel Hatfield 35 Pressure switch United Electric J110-164
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44 Level indicating Endress-Hauser UNK switch 45 Radiation Nuclear G M-912, Detector Measurement S C-2-15, SC-28
'9 Pressure Switch United Electric J302-358 54A Control panel Westinghouse UNK TBDP 59 Thermostat Penn A A A37 38 Flow Fi s che r-P o rt e r 50EP1031 transmitter B CX A-NS 10C Transmitter Fi s che r-P o rt e r 1082496 BBABBB-NS 46 Pressure Fi sche r-Port e r 50EP10971 transmitter 63 Flow Fi s che r-P ort e r 108296 transmitter PBBABBB 323 MOV Limitorque H-3 B C 19 MOV Limitorque SMB-3-80 1C MOV Limitorque SMB-1 1F MOV Limitorque SMB-4 1G MOV Limitorque SMB-00 C-2 ys m---.
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APPENDIX C, Continued TER EQUIPMENT MODEL /
DE FICIENCIES ITEM NO.
DES CRIPTION M ANU F ACTURER TYPE THT-8316 4
SOV Operator AS CO 54-C34 47 Control Panel Powers Reg. Co.
U NK 52s Mov Limitorque SMB-000 IE MOV.
Limitorque SMS-2 9
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APPENDIX D Plant Safety-Related Systems and Display Instrumentation A.
Safe Shutdown Systems System Term Function RP - Reactor Protection / Trip (1)
S Trips reactor when predetermined set points are exceded MS - Main Steam (MSIVs, Safeties, I
Releases energy for plant cooldown Atmospheric Reliefs) (1 )
CV - Crib House Ventilation L
Cools service water pump motors FW - Steam Generator Feedwater/
I/L Provides makeup water to steam Auxiliary Feedwater (1) generator for cooldown V C.- Chemical and Volume Control L
Provides reactor makeup water and (charging portions)
(1 )
long-term chemical control RH - Residual Heat Removal L
P rovides long-term heat removal (required for cold shutdown)
RC Reactor Coolant L
Transfers heat from core to steam generator CC - Component Cooling L
Removes heat from core to steam generator SW - Service Water L
Takes heat from component coolant heat exchanger to heat sink DG - Diesel Generator (1)
S/I Provides emergency onsite power DC - 125 V DC Power Supply (1)
L Provides back-up power DO - Diesel Oil (1)
S/I Provides lubrication for emergency diesels AP - Auxiliary Power Distribution L
As indicated AR - Area Radiation Monit'oring (1 )
I/L Detects radiation diesels LEGEND:
(S) Short Term Less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> I
(I) Intermediate Term Up to 30 days (L) Long Term 30 days plus i
NOTE:
(1) Used for accident mitigation and safe shutdown (2) The NRC staff recognized that there are differences in nomenclature of j
systems because of plant vintage and engineering design, consequently l
some' systems performing identical or similar functions may have different names. In those instances it was necessary to verify the system (s) func-tion with FRC and/or the licensee.
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Appendix 0, continued B.
Accident Mitigating Systems (Lot A, MSLB, FWLB)
System Term Function CI - Containment Isolation Valve L
Isolates containment penetration RV - Reactor Containment Fan Coolers, I
Removes post LOCA containment heat Hydrogen Purge and Hydrogen and controls hydrogen Recombiners SI - Safety Injection and Accumulators S/I Provides post accident cooling water to core Pressurizer Pressure Relief I
Power operated relief valves relieve RCS pressure PR - Post-Accident Sampling and Monitor-L As indicated ing/ Containment Radiation Monitor CS - Containment Spray I
Provides post-accident containment crovides and iodine control IW - Isolation Valve Seal Water I
Seals penetration with high-pressure water PP - Penetration Pressurization I
Seals electrical penetration with high-pressure air or nitrogen IP - V ital Instrument Power Supply (1)
L As indicated AV - Puno Room Ventilation Coolers I/L As indicated (RHR/SI/S C/ CCP)
PV - Control Room Ventilation L
As indicated OV - Auxiliary Electrical Equipment L
As indicated Room Ventilation TV - Turbine Building Ventilation L
As indicated 0-2
Appendix D, continued C.
Saf e Shutdown / Accident Mitigating Instruments (LOCA, MSLB, FWLB)
Term Ins t ruments Pressurizer level I
L Pressurizer pressure RCI Temperature L
Containment pressure (2)
I L
Steam line pressure S
Steam line flow Containment spray flow (2)
I I
Safety injection flow (2)
Penetration pressurization (2)
I Isolation valve seal <ater pressure (2)
I S ur.: '.evel (2)
L L
Steam generator level L
Auxiliary feed system flow secondary storage tank level L
Chemical and volume control flow I
I RWST Level BIT (Boron Injection Tank) (2)
S L
Residual Heat Removal Flow L
Cor.conent Cooling Water, Flow L
Service Water System Legend:
S - Short term less than 24 hr.
I - Intermediate term up to 30 days more than 30 days L - Long term NOTE:
(2) Required for accident mitigation only D-3
Partial Review EQUIPMENT EV ALO ATION REPORT BY THE OFFICE OF NUCLEAR REACTOR REGULATION EQUIPMENT QUALIFICATION BR ANCH FOR COMMONWE ALTH EDISON CO.
ZION NUCLEAR POWER ST ATION, UNIT NO. 2 DOCKET NO. 50-304 ENVIRONMENT AL QU ALIFICATION OF S AFETY-REL ATED ELECTRIC AL EQUIPMENT 3.0 ST AFF EV ALUATION The staff's evaluation of the Licensee's responses was accompanied by performing an on-site inspection of selected Class IE equipment and by examining the licensee's report for completeness and accept-a:ility. The criteria described in the 00R Guicelines and NUREG-0588,
- a-, were used as a basis for the staff's evaluation of the adequacy e the Licensee qualification program.
d
- rir.g the week of June 7.,1980, NRC and FRC representatives visited the
- icn :Lant site, inspected safety-related systms and ecuipment, identified a-: taculated saf ety-related componcats through discussions with plant
- ersennel, and concucted a general review of CECO's submittal of May 2,1980.
the inspection verified proper installation of equipment, overaLL interf ace 3.ntegrity, and manufacturers nameplate data. The manufacturer and model number
' rem the nezeplate data was compared to information given in the Licensee's succittal.
W 4
The following safety evaluation incorporates the CECO submittal and the Franklin Research Center technical evaluation report (TER).
3.1 COMPLE1ENESS OF S AFETY-RELATED EQUIPMENT In accordance with the DOR guidelines, the licensee was directed to establish a list of systems and display instrumentation needed to nitigate the consequences of a LOCA or HELB, inside or outside con-tainment, and reach safe shutdown. The lists of safety related systems and display instrumentation were developed f rom a review of plant safety analyses and emergency procedures. The display instrumentation selected
' includes parameters to monitor overall plant performance as well as to monitor performance of the systems on the list. The systems list was established on the basis of the f:,nctions that must be performed for
'tigation of the consequences of a LOCA or HELB without regard to location of equipment relative to a potentially hostile environment.
Tre staff has determined and verified that the system considered by t e licensee are those required to achieve or support: (1 ) emergency reactor srutcown, (2) containment isolation, (3) reactor core cooling, (4) con-tainment heat removal, (5) core residual heat removal, and (6) prevention of significant release of radioactive material to the environment. The staff concludes that the systems identified by the licensee are accept-a:Le. The systems and. instrumentation list is contained in Appendix 3.
Tne licensee submitted an extensive list of safety-related electrical e:uipment. This list was evaluated and identical components within 2
- c e
=
O 4
a plant area exposed to the same environment were grouped; 101 item
}
Items types of equipment were identified and assessed by the staff.
with exceptions are discussed in section 5.0 of this report.
3.2 Service Conditions l
23, 1980 The Commission Memorandum and Order (CLI-80-21), dated May requires that the 00R Guidelines and the."For Comment" NUREG-0588 are to be used as the criteria for establishing the adecuacy of the safety These related electrical equipment environmental qualification program.
documents provide the option of establishing a bounding pressure and temqerature condition based on plant specific analysis identified in the licensees FSAR or based on generic profiles using the methods identified in these documents.
this basis the staff has assumed, unless otherwise noted, that 4
C a.
the analysis for developing the environmental envelopes for Zion 1 relative to the temperature, pressure, and the containment spray caustics, For have been performed in accordance with the aoove stated recuirments.
this review the staf f reviewed the qualification documentation to ensure F
that the qualification specifications envelope the conditions established During this review the staff assumed that for plants, designed by the licensee.
and equipped with an automatic containment spray system, which satisfies the single failure criterion, the main steam line break environmental conditions The staff are enveloped by the large break LOCA environmental conditions.
assumed and requires that the licensee verifies, that the containment spray subjected to a disabling single component failure and therefore system is not satisfies the 00R Guideline requirements of Section 4.2.1.
Equipment submergence has also been addressed where the possibility exists from high energy line breaks (HELB).
that flooding of equipment may result 3
A 3.3 TEMPERATURE, PRESSURE, AND HUMIDITY CONDITIONS INSIDE CONTAINMENT The License'e has provided the results of accident analyses as follows:
Max. Temp. *(
F)
Max. P ress. (psig)
Humidity LOCA 271 47 100%
MSLB (Not Provided)
The staff has concluded that the minimum temperature profile for equipment qualification purposes should include a margin to account for higher than can exist average temperatures in the upper regions of the containment that Use of the due to stratification especially following a postulated MSLB.
steam saturation temperature corresponding to the total building pressure (partial pressure of steam plus partial pressure of air) versus time until the sprays become effective wiLL provide an acceptable margin for either a costulated LOCA or MSLB, whichever is controlling as to potential adverse environmental effects on equipment.
The Licensee's specified temperature (service condition) of 271 F does not satisfy the above recuirement. A saturation temperature corresponding to should be used the pressure profile (295 F peak temperature at 47 psig) instead. The Licensee should update his equioment summary tables to reflect If there is any equipment that does not meet the staff position, this change.
the Licensee must provide either Justification that the equipment wiLL perform
~
its intended function under the specified conditions or propose corrective action.
TEMPER ATURE, PRESSURE AND HUMIDITY CONDITIONS OUTSIDE CONTAINMENT 3.4 The Licensee has provided the temperature pressure, humidity and applicable in the environme,tnal values associated with a HELB outside containment following plant areas:
4 u
v-"
g k?- - -
m r
p--
g-o ra-.
v-g
--w wwr'--e-wr F--
1.
Upper Safety Valve Room 2.
Lower Safety valve Room 3.
Main Steam & Feedwater Pipe Tunnel 4.
Tendon Tunnel S.
Aux. building (elev. 579 feet) 6.
Aux. building (elev. 592 feet) 7.
Seat water heat exchanger rooms.
8.
Pipe tunnels and penetration areas 9.
Centrifugal charging pump rooms 10.
RHR heat exchanger rooms 11.
Boric acid evaporator and R AD waste rooms The staf f has verified that the parameters identified by the licensee for the M5LB are acceptable.
3.5 SUBMERGENCE The maximum submergence levels have been established and assessed.by the licensee. The staff assumed for this review, unless, otherwise noted, that the methodology employed by the licensee is in accordance with the appropriate criteria as established by the Commission Memor-andum and Order (CLI-80-21), dated May 23, 1980. The Licensee's value for maximum submergence is 3.5. feet (elev. 581.5 f eet).
The-Licensee has identified 4 equipment items models below this level.
The staff concurs with the Licensee's position as presented in the TER, (1 ) operation is not required post LOCA and is therefore exempt from 5
6
a qualification, one item, and (2) failure due to submergence does not result in degradation of the capability to attain saf e shutdown, one item.
Based on the TER the staf t has determined that qualification is required for two items; interim justification for continued operation has been provided by the licensee.
The Licensee should provide an assessment of the failure modes associat-d with the submergence of equipment. Assurance should also be provided tnat the subsequent. failure of this equipment dill not adsersely affect Additionally, the any other safety functions or mislead an operator.
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 equipment may be exempt from the sa: mergence parameter of qualification.
3.6 Chemical Spray 2500-3000 Tne Licensee's FS AR value for the chemical concentration is ccM boric acid solution. The exact volume percene used by the vendors for
- ualification testing s ould be verified by the Licensee. Therefore, for h
the purpose of this review the ef fects of chemical spray wiLL be considered unresolved.
3.7 Aging The DCR Guidelines, section 7, does not require a cualified life to be established for all safety related electrical equipment, however the following actions are required:
6 4
e y
--y m
1.
Detailed comparison of existing ecuipment to the materials identif ed in Appendix C of the DOR guidelines. The first supplement to IEB-79-01B requires the Licensees to utilize the table and identify any additional materials as a result of their ef fort.
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 :haracteristics of the installed components.
For this review the staff requires that the Licensee submit supplemental information to verify and identify their degree of conformance to the acove requirements. The response snould be inclusive of atL the equipment identified as required to maintain their functional operability in harsn environments.
ne staf f wiLL review the licensees response, when submitted, and report
'ts evaluation in a supplemental report.
3.8 R ADI ATION (INSIDE AND OUTSIDE CONTAINMENT)
The Licensee has provided values for radiation Levels postulated to exist l
'f ollowing a LOCA event. The application and methodology employed to
~
cetermine these values have been presented to the Licensee as part of l
the NRC staf f. criteria contained in the DOR Guidelines, NUREG-0588 and the guidance provided in IEB-79-018, Supplement 2.
The value required by the 7
P
8 Licensee inside containment is an integrated dose of 1 x 10 R AD S.
Tnis value envelopes the DOR Guideline requirements and is therefore 7
acceptable. A required value outside containment of 2 x 10 RADS has been used by the Licensee to specify limiting radiation levels 3
This within the entrifugal charging pump rooms of the auxiliary building.
value appears to consider the radiation levels influenced by the source term cethodology associated with Post-LOCA recirculation fluid lines and is there-fore acceptable.
4.0 QUALIFICATION OF EQUIPMENT The following subsections are the staf f's assessment, based on the Licensee's submittal, and the Franklin TER of the qualification status of safety-related electrical equipment.
into three categories the staff has separated the safety-related eouipment requiring immediate corrective action, (2) ecuipnent requiring (1 ) ecuipment equip-i soditional qualification information and/or corrective action, and (3) considered acceptable conditioned only on the satisf actory resolution of ent tre staf f's concern idertified in Section 3.7.
The NRC staf f in its assessment of the licensees submittal and the TER i
review the methodology employed to cetermine the values estab-
'did not However, in reviewing the TER a determination l
s.ished by the Licensee.
by the
.as made by the staff as to the stated conditions presented Additionally, the detailed review of supporting documentation j
'icensee.
has been completed by
-ref erenced by the Licensee (e.g., test reports) l FRC.
8 L
r
6 The environmental qualification data bank to be established by the staf f wilL provide the means to cross ref erence each supporting docu-ment to the referencing Licensee.
Where supporting documents were found to be unacceptable, the Licensee wiLL be required to take additional corrective actions to either estab'Lish qualification or replace the item (s) of concern. An 4
appendix for each subsection is attached which provides a list of equip-ment which requires additional information anc/or corrective action.
Where appropriate, a reference is provided in the appendices to identify deficiencies. It should be noted, as in the Commission Memorandum and
~ 0rder, that the deficiencies identi'ied do not necessarily mean that ecuipment is unqualified. Howeve", they are cause for concern and may recuire further case-by-case evaluations.
4.1 EQUIPMENT REQUIRING IMMEDI ATE CORRECTIVE ACTION o'
9 4
9 c
--n,
)
4.2 EQUIPMENT REQUIRING ADDITIONAL INFORMATION AND/OR CORRECTIVE ACTION Appendix B identifies equipment in this category, including the tabulation of their deficiencies. The deficiencies are noted by a letter relating to the legend, identified below, including that insufficient information has been provided for the qualification parameter or condition.
R - Radiation T - Temperature QT - Qualification Time RT - Required Time P - Pressure H - Humid'ty CS - Chemical Spray
't Material Aging Evaluation, Replacement Schedule, Ongoing Ecuipment t
Surveillance 5 - Submergence M - Margin I - HELB Evaluation outside Containment Not Completed 3M - 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.
10 h
n,
r c-,
6 6
At noted in Section 4.0, these deficiencies do not necessarily mean that the equipment is unqualified. However, they are cause or concern d
and require further case-by-case evaluations. The staff *** determined
- at an acceptable basis to exempt equipment f rom qualifi on, in whole or part, can be established provided the following can be estab-lished and verified by the licensees:
(1 )
Equipment does not provide essential safety functions in the harsh environment and failure of it in the harsh environment will not impact safety related functions or mislead an operator.
(2 a)
Equipment performs its function prior to its exposure to the harsh environment and the adequacy for the time margin provided o
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.
11 8
)
i (3)
The safety-related function can be accomplished by some other designated equipment that has been adequately qualified and satisfies the single failure criteria.
(4)
Equipment not subjected to a harsh environment as a result of the postulated accident.
The Licensee is therefore required to supplement the information presented by providing their resolutions to the deficiencies identified which should include a description of the corrective action and schedules for its completion (as applicable), etc. The staff wiLL review the Licensees response, when submitted, and report on the resolution in a supplemental report.
It should be noted that where testing is presently being conducted, a
- endition 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 sitL be required to provide their crocosed corrective action, on a timely basis, to assure that qualifi-
- ation can be established by J une 30, 1982.
4.3 EQUIPPENT CONSIDERED ACCEPTABLE OR CONDITIONALLY ACCEPT ABLE Based on the staffs review of the Licensees submittal and the TER the f
staff identified the equipment in Appendix C (1) as acceptable on the basis o that the qualification program adequately enveloped the specific environ-mental plant parameters, or (2') conditionally acceptable subject to the satis-
- f actory resolution of the staf f concern identified in Section 3.7.
12 S
e 3
- ~ _ _ _
y,
,)
For the equipment identified as conditionally acceptable the staff deter-mined that the Licensee did not clearly:
(1 )
state that a material evaluation on their equipment was conducted to assure that no known materials susceptible to degradation due to aging have been used in their equipment.
(2 )
establish an ongoing program to review the surveillance and maintenance records of their plant 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 Licensees response, when suomitted, and report on the resolution in a supplemental report.
5.0 DEFERRED REQUIREMENTS IE Rulletin 79-013, supplement 3 nas relaxed the time constraints for the submission of the information associated with cold shutdown equipment and TMI Lessons Learned modifications. To permit a uniform program schedule o the SEP plant reviews have been amended. The staff wilL require that this information be provided by February 1,1981. The staf f will provide a supplemental safety evaluation adoressing these concerns.
13
.4
'ut APPENDIX B List of Equipment in Section 4.2, Equipnent Requiring Additional Information And/Or Corrective Action LEG END:
Designation for Deficiency R - Radiation M - Margin T -. Temperature I - HELB Evaluation Outside OT - Qualification Time Containment Not Completed RT - Required Time QM - Qualification Method P - Pressure RPN - Equipment Relocation or Replacement, H - Humidity Adequate Schedule Not Provided CS - Chemical Spray EXN - Exempted Ecuipment J ustification A - Material Aging Evaluation, Inadequate Replacement Schedule, Ongoing SEN - Separate Ef fects Qualification Equipment Surveillance Justification Inadequate 5 - Submergence QI - Qualification Information Being Developed RPS - Equipment Relocation or Replacement Schedule provided TER EQUIP MENT MODEL /
ITEv NO.
DESCRIPTION M ANU F ACTURER TYPE DEFICIENCIES 20 J unction box UM; EB-215 QM,GI,S,CS 2'
Junction box UNK EB-214 Q M,G I,S, C S 22 Junction box UNK EM-47150 QM,GI,S,CS 23 Junction box U4; UNK Q M,G I,S, CS 5:
Junction box UNK EM-47150 QI,S,CS,A l
l
- Terminal block Marathon 6000 QI,S,CS, A 1
5" Junction box UNK EB-214 QI,S,CS,A I
Terminal block Marathon 6000 QI,S,CS,A 55 Junction box UNK EM-47L50 QI,S,CS, A l
438 J unction box UNK EB-214 QI,S,CS,A i
l 548 Junction box UM; EB-214 GI,S,CS,A l
64-Junction box UNK EB-215 QI,S,CS,A l
65 Junction box UM; EB-215 GI,S,CS,A i
9 B-1
s
't e3 i
APPENDIX B (CONTINUED)
TER EQUIPMENT MODEL/
ITEM NO.
DESCRIPTION MANUFACTURER TYPE DEFICIENCIES 71 Junction box UNK EB-215 QI,5,CS,A Terminal block Marathon 6000 72 Junction box UNK EM-47150 QI,5,CS,A Terminal block Marathon 6000 73 Junction box UNK EB-215 QI,5,CS,A Terminal block Marathon 6000 74 Junction box UNK EB-214 GI,5,CS,A Terminal block Marathon 6000 48 Junction box UNK EM-47150 QI,S,CS,A Terminal blocs Marathon 6000 7
SOV operato-aIC:
53 0 QI,A,T,F,CS, R,M,3M,;T 53 SOV ocerato-13 :
HPx-5320A25 QI,A,T,:
LB-5314e LB-831654 HPx-5320A26
- o SOV operato-AS~;
5316E34 QI,A,T,7 is Level switer.
Mao etrol 52-1212-002 QI 37 Remote shutoown UNK UNK QI,A panel
,34 Elect ri ca l Westinghouse VX-252 QI,A,T,?,R,M,GM indicators QT 6,
Motor Westinghouse 585.5 CSP QI,A,GM 42 Motor UNK 36MP/184 A,R 56 Motor Westinghouse HSDP QI,A 39A MOV Limitorque.
SMB-000 GI,QM,A,T,P,QT R,M B-2
M Appendix B, Continued TER EQUIP MENT MODEL/
ITEM NO.
DESCRIPTION MANU F ACTURER TYPE DE FICIENCIES 16 Electrical D.G. O'Brien Type 4.1 A,CS,R penetrations 17 Electrical D.G. O'Brien Type 3.1 A,CS,R penetrations 18 Electrical D.G. O'Brien Types 2.1,
A,CS,R penetrations 2.2, 2.3 19 Electrical D.G. O'Brien Type 5.1 A,CS,R penetrations IA MOV Limitorque SMS-3 QI,A,T 52C POV Limitorque SMS-1 GI,G M, A,T,P,R,M, QT 520 MOV Limitorque SMS-0 Q I,G M, A,T,P,G T,R,
M
$25 MOV Limitoroue SMS-00 QI,2M,A,T,P,GT,R, M
$2H MOV Limitorque SMS-000 QI,3M,A,T,P,GT,R, M
60 MOV Limitorque SMS-0 GI,0M,A,T,P,GT,R, M
'2 Resistance SO STM AN UNK QI,A,S,CS,R temperature detectors 69 Electrical Weschler-UNK QI,3M,A,T,P,QT,R, indicator M
75,
Elect ri cal 3.G. O'Brien Type 1.1 Q I, A,G M,Cs,R penetration 76 Electrical D.G. O'Brien Type 5.2 QI,A,GM,CS,R penetration 41 Hydrogen GE 5<182 QI,A,R Recombiner CK742 Blower B-3
- e 9
k
F APPENDIX B, Continued TER EQUIPMENT MODEL/
ITEM NO.
DESCRIPTION M ANU F A CTUR ER TYPE DEFIC 1ENCIES 5
Limit Swtich NAMCO E A180 A,GM,CS 11 Level Transmitter BARTON 386 Q I,G M, A,Q T, CS 8A Transmitter Fischer & Porter 1082496 Q I,Q M, A,Q T, CS,
ABBABBB-NS M,S 10A Transmitter Fischer & Porter 10B2491V Q I,G M, A,G T, CS,
CBB-NS M
109 Transmsitter Fischer & Porter 1302495K QI,GM,A,QT,CS, BBABBB-NS M,5 100 Transmitter Fischer & Porter 50-EP1041 Q I,Q M, A,Q T, C S,
BCX A-NS M
31 Motor Westinghouse HSDP QI,A,T SBDP 58 Motor U NK Type B QI,A,QM,T,P,QT, R,M 61 Motor Westinghouse TBFC QI,A 70 Pressure Switch Barksdale 9672-3 QI,GM,A,T,P,QT, R,M 33 Transmitter Fischer & Porter 1082495 Q I,G M, A,G T,M 67 SOV Operator Ross 233693 QI,A,T,P,GT,R 9
Level Switch Magnetrol A-153-FEP /
P,QT,S,CS I
V PX-Y -3X 3
SOV Operator ASCO LB831654 QI,A 82 SOV Operator ASCO THT-8316 QI,A,T,P,GT,CS,
-C34 R
368 MCC GG McC23838 QI,A,GM,T 838-MOV Limitorque SMB-00-15 QI,QM,A,T,P,GT, R,M 8'
SOV Operator ASCO HPX-8320-Q I, A,T,P,QT A25, A26 62 Pressure Fischer & Porter 50EP104 RPS Transmitter LBCX A B-4
o.
t APPENDIX C LIST OF EQUIPMENT IN SECTION 4.3, EQUIPMENT CONSIDERED ACCEPTABLE OR CONDITIONALLY ACCEPTABLE LEGEND:
A - Material Aging Evaluatio'n TER EQUIPMENT
- MODEL, DEFICIENCIES ITEM NO.
DESCRIPTION MANUFACTURER TYPE 2A Cable Boston Insulated CSPE/LSPE A
Wire & Cable Co.
75 Canle Boston Insulate:
CSPG/LSPE A
Wire & Cable Co.
25 Cable Kerite Corp.
Va ri ous A
25 Cable Kerite Cor:.
Va rious A
26 S;Lices Raychem Corp.
UN<
A 27 Solices Kerite Corp.
UNK A
~~
Cable Ana conoa Various A
?
Ca:Le Okemite various A
i:
CacLe Re:<=es :s va ri ous A
l' Cacie Sar.;e'. M00 e Various A
32; MOV
.iritarcue SMS-2 A
51; MOV
.iritorcue SMS-C A
51" MOV
.iriterese SMS-000 A
523 MOV Limi:orcue SMS-00-15 A
"O' MOV Limitorque SMS-1 A
53j MOV Liritorcue SMS-2 A
22*
MOV Licitorcue S MS-00 A
32
.MOV Limitorcue SMS-000 A
32E MOV-Licitorcue SMS-000 A
57 MOV-Limitorcue S MS-00-25 A
Motor Westinghouse TELG A
.375 MOV Lici:e :ve S ".S - 3 A
9 1
A?PENDIX C, Continued TER EQUIPMENT MODEL/
DE FICIENCIES ITEM NO.
DESCRIPTION M ANU F ACTURER TYPE 2
Limit Switch NAMCO DX-2400 13 Humidity sensor Taylor 10HS 14 Resistance UNK 3 Wire temperature detectors 35 Pressure switch United Electric J 110-164 44 Level indicating Endress-Hauser UNK switch 45 Radiation Nuclear G M-912,
Detector Measurement S C-2-15, SC-2B 49 Pressure Switch United Electric J 302-358 SB Flow Fi s ch er-P orte r 50EP1031 transmitter B CX A-N S 13C Transmitter Fi s ch e r-P ort e r 1082496 BBABBB-NS
'6 Pressure Fi s cher-P ort e r 50EP10971 transmitter 63 Flow Fi s cher-P orte r 108296 transmitter P3BABBB 328 MOV Limitorque H-3BC 18 MOV Limitorque SMB-3-80 ic,
POV Limitorque SMB-1 1F MOV Limitorque SMB-4 13 MOV Limitorque SMB-00 C-2
O APPENDIX 0, Continued T E :.
EQUIPMENT MODEL/
DEFICIENCIES ITEM No.
DESCRIPTION MANUFACTURER TYPE 4
SOV Operator ASCO TNT-8316 54-C34
- t. 7 Control Panet Powers Reg. Cc.
UNK 5 2E MOV Limitorcue S P3-000
'5 E MOV Limitoroue S P3-2 0
- -3 C
e APPENDIX D Plant Saf ety-Related Systems and Display Instrumentation A.
Safe Shutdown Systems System Term Function RP - Reactor Protection / Trip (1)
S Trips reactor when predetermined set points are exceded MS - Main Steam (MSIV s, Safeties, I
Releases energy for plant cooldown Atmospheric Reliefs) (1 )
C/ - Crib House Ventilation L
Cools service water pump motors FW - Steam Generator Feedwater/
I/L Provides makeup water to steam Auxiliary Feedwater (1) generator for cooldown V C - Chemical and Volume Control L
Provides reactor makeup water and (charging portions)
(1 )
long-term chemical control R4 - Residual Heat Removal L
Provides long-tern heat removal (recuired for cold shutdown)
RC - Reactor Coolant L
Transfers heat from core to steam generator CC - Co conent Cooling L
Removes heat from core to steam generator 34 - Service Water Takes heat from component coolant heat exchanger to heat sink 03 - Siesel Generator (1)
S/I Provides emergency onsite power
- - 125 V DC Power Supply (1)
L P rovides back-up power 00 - Diesel Oil (1 )
S/I Provides Lubrication for emergency diesels to - Auxiliary Power Distri'oution L
As indicated 19 - Area Radiation Monitoring (1 )
I/L Detects radiation diesets
. LEGEND:
(0) Short Term Less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (I) Intermediate Term Up to 30 days (L) Long Term 30 days plus NOTE:
(1) Used for accident mitigation and safe shutdown (2) The NRC staff recognized tnat there are differences in nomenclature of systems because of plant vintage and engineering design, consecuen:Ly some systems cerforming identical or similar functions may have different In those instances it was necessary_to verify the system (s) func-nanes.
tion with FRC and/or the Licensee.
D-1
Appendix D, continued B.
Accident Mitigating Systems (LOCA, MSLB, FWLB)
System Term Function CI - Containment Isolation Valve L
Isolates containment penetration RV - Reactor Containment Fan Coolers, I
Removes post LOCA containment heat Hydrogen Purge and Hydrogen and controls hydrogen Recombiners SI - Safety Injection and Accumulators S/I Provides post accident cooling water to core Pressurizer Pressure Relief I
Power operated relief valves relieve RCS pressure PR - Post-Accident Sampling and Monitor-L As indicated ing/ Containment Radiation Monitor CS - Containment Spray I
Provides post-accident containment provides and iodine control IW - Isolation Valve Seal Water I
Seals penetration with high-pressure water PP - Penetration Pressurization I
Seals electrical penetration with high-pressure air or nitrogen IP - Vital Instrument Power Supply (L)
L As indicated AV - Dump Room Ventilation Coolers I/L As indicated (RHR/SI/S C/ C CP)
PV ' Control Room Ventilation L
As indicated OV - Auxiliary Electrical Equipment L
As indicated Room Ventilation TV - Turbine Building Ventilation L
As indicated D-2 e
h w
= - _ _ _
Appendix 0, continued i
C.
Safe Shutdown / accident mitigating instruments (LOCA, MSLB, FWLB)
Instruments Term I
i Pressurizer level I
Pressurizer pressure L
RCS Temperature L
Containment pressure (2)
I Steam Line pressure L
Steam Line flow S
Containment spray flow (2)
I Saf ety injection flow (2)
I Penetration pressurization (2)
I i
Isolation valve seat water pressure (2)
I Sune level (2)
L Steam generator level L
Auxiliary feed system flow L
Secondary storage tank level L
Chemical and volune control flow I
RLST Level I
BIT (Boron Injection Tank) (2)
S Residual Heat Removal Flow L
Cor,:enent Cooling Water. Flow L
L Service Water System Legend:
3 - Short term iess than 24 hr.
I - Intermediate term up to 30 days L - Long term more than 30 days NOTE:
(2) Required for accident mitigation only
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