ML17298A621
| ML17298A621 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/11/1983 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17298A620 | List: |
| References | |
| NUDOCS 8311040112 | |
| Download: ML17298A621 (50) | |
Text
APPENDIX B SAFETY EVALUATION REPORT OFFICE OF NUCLEAR REACTOR REGULATION
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EQUIPMENT QUALIFICATION BRANCH PALO VERDE, UNITS 1, 2
8c 3 Environmental uglification of Electrical E ui ment Im ortant to Safet and Safet -Related Mechanical E ui ment
- 1. 0 INTRODUCTION Equipment which is used to perform a necessary safety function must be demonstrated to be capable of maintaining functional operability under all service conditions postulated to occur during its installed life for the time it is required to operate.
This requirement, which is embodied in General Design Criteria 1 and 4 of Appendix A and Sections III, XI, and XVII of Appen-dix B to 10 CFR 50, is applicable to equipment located inside as well as outside containment.
More detailed requirements and guidance relating to the methods and procedures for demonstrating this capability for electrical equip-ment have been set forth in 10 CFR 50.49, "Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants,"
and NUREG-0588, "Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment."
This NUREG supplements IEEE Standard
- 323, and various NRC Regulatory Guides and industry standards.
2.0 BACKGROUND
NUREG-0588 was issued in December, 1979 to promote a more orderly and systematic implementation of electrical equipment qualification'rograms by industry and to provide guidance to the NRC staff for. their use'in ongoing licensing reviews.
The positions contained in that report provide guidance on (1) how to establish 83ii040112 83iOii PDR ADOCK 05000528 j'~
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09/25/83 B-1 Palo Verde SSER 5
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environmental service conditions, (2) how to select methods which are considered appropriate for qualifying equipment in different areas of the plant, and (3) other, areas such as margin, aging, and documentation.
In February 1980 the NRC requested certain near term Operating License (OL) applicants to review and evaluate the environmental qualification documentation for each item of safety-related electric equipment and to identify the degree to which their qualification programs comply with the staff positions described in NUREG-0588.
IE Bulletin 79-01B "Environmental gualification of Class 1E Equipment;" dated January 14, 1980, and its supplements dated February 29, September 30, and October 24, 1980, established environmental qualification requirements for operating reactors.
This bulletin and its supplements were provided to OL applicants for consideration in their review.
A final rule on environmental qualification of electrical equipment important to safety for nuclee.r power plants became effective on February 22, 1983.
This rule, Section 50.49 of 10 CFR 50; specifies the requirements to be met for demonstrating the environmental qualification of electrical equipment important to safety located in a harsh environment.
In accordance with this rule, equipment for Palo Verde may be qualified to the criteria specified in Category I of NUREG-0588.
The qualification requirements for mechanical equipment are principally contained in Appendices A and B of 10 CFR 50.
The qualification methods defined in NUREG-0588 can also be applied to mechanical equipment.
In response to the above requirements, the applicant has provided equipment qualification information in letters dated February 7, 1983 and June 24, 1983 to supplement the information contained in Section
- 3. 11 of the FSAR.
2.1
~Pur oee The purpose of this report is to evaluate the adequacy of the Palo Verde environmental qualification program for electrical equipment important to
- safety, as defined in 10 CFR 50.49, and for safety-related mechanical equipment.
09/25/83 B-2 Palo Verde SSER 5
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The staff position relating to open items, as well as any unresolved
- issues, is provided in this report.
2.2
~Sco e
The scope of this report includes an evaluation of the completeness of the list of systems and equipment to be qualified, the criteria which must be met, the environments in which they must function, and an assessment of the qualifica-tion documentation for the equipment.
It is limited to electrical equipment important to safety within the scope of 10 CFR 50.49, and safety-related mechanical equipment.
- 3. 0 STAFF EVALUATION The staff evaluation of the applicant's environmental qualification program included an onsite examination of electrical equipment, audits of qualification documentation, and a review of the applicant's submittals for completeness and acceptability of systems and components, qualification methods, and accident environments.
The criteria described in NUREG-0800, Rev.
2, Section 3.11 and NUREG-0588, Category I, form the basis for the staff evaluation of the adequacy of the applicant's qualification program.
Revision 1 of NUREG-0588 was util-ized to clarify staff positions as required.
The staff performed an audit of the applicant's qualification documentation and installed electrical equipment on June 28-30, 1983.
The audit consisted of a review of ten files containing equipment qualification documentation.
The staff s findings during the audit are discussed in detail in Section 3.4 of this report.
Mechanical equipment environmental qualification was also reviewed and staff's evaluation of the mechanical equipment is discussed in Section 4.2.
- 3. 1 Com leteness of E ui ment Im ortant to Safet The applicant was directed to (1) establish a list of systems and components that are required to prevent or mitigate a
LOCA or an HELB and (2) identify 09/25/83 B"3 Palo Verde SSER 5
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components needed to perform the function of safety-related display instrumentation, post-accident sampling and monitoring, and radiation monitoring.
The applicant's systems list for the environmental qualification program was compared to Table 3.2-1 of the FSAR.
Omissions from the harsh environment program were adequately justified by the applicant.
Attachment C lists the systems identified and their safety function.
Based upon information in the applicant s submittal, the staff has verified and determined that the systems included in the applicant's submittal are those required to achieve or support:
(1) emergency reactor
- shutdown, (2) con-tainment isolation, (3) reactor core cooling, (4) containment heat removal, (5) core residual heat removal, and (6) prevention of significant release of radioactive material to the environment.
The applicant has identified the equipment required by NUREG-0737, "Clarification of TMI Action Plan Requirements,"
but the qualification status has not been established for all items.
Prior to granting of an operating
- license, the applicant should identify the qualification status of all TMI Action Plan equipment.
For any TMI Action Plan equipment not yet installed and that will not be installed prior to operation, a description of the plans for qualification, including the schedule for completion of qualification, must be submitted.
(All TMI Action Plan equipment currently installed or that will be installed prior to operation must be qualified or justifications for interim operation provided prior to granting of an operating license, in accordance with 10 CFR 50.49.)
In order to comply with 10 CFR 50.49, the following information must be submitted by the applicant prior to granting of an operating license for Palo Verde Unit 1:
(1) g'list of all nonsafety-re1ated electrical equipment, located in a harsh environment, whose failure under postulated environmental conditions could prevent satisfactory accomplishment of safety functions by the safety-related equipment.
A description of the methods used to identify 09/09/83 B"4 Palo Verde SSER 5
this equipment must also be included.
The nonsafety-related equipment identified must be included in the environmental qualification program.
(2) statement that all safety-related electrical-equipment-in--a-harsh-
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environment, as defined in the scope of 10 CFR 50.49, is included in the list of equipment identified in the Eg submittal.
(3) jfi 'list of ail post-accident monitoring equipment currently instailed, or that will be installed prior to plant operation, that is specified as Category
- j. or 2 in Revision 2 of Regulatory Guide 1.97 and which is located in a harsh environment.
The equipment identified must be included in the environmental qualification program.
3.2 uglification Methods 3.2. 1 Electrical Equipment in a Harsh Environment Detailed procedures for qualifying safety-related electrical equipment in a harsh environment are defined in NUREG-0588.
The criteria in this NUREG are also applicable to other equipment important to safety defined in 10 CFR 50.49.
Type testing of equipment in a sequence consisting of pre-aging (thermal, radiation, and mechanical),
seismic and dynamic loading, and exposure to LOCA/HELB conditions (where applicable) is the preferred method of qualifica-tion.
However, in a number of cases the applicant has extrapolated partial test data to establish the equipment qualification.
The staff has reviewed this analysis and finds the approach to be adequate except as noted in this report.
3.2.2 Safety-Related Mechanical Equipment in a Harsh Environment Although there are no detailed requirements for mechanical equipment, General Design Criterion 1, "equality Standards and Records,"
and Criterion 4, "Environmental and Missile Design Bases,"
Appendix B to 10 CFR 50, "equality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,"
Section III, "Design Control" and Section XVII, "equality Assurance Records;"
09/25/83 B-5 Palo Verde SSER 5
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and SRP Section
- 3. 11, Revision 2 contain the following requirements and guidance related to equipment qualification.
(1)
Components shall be designed to be compatible with the postulated environmental conditions, including those associated with loss-of-coolant accidents.
(2)
Measures shall be established for the selection and review for suitability of application of materials,
- parts, and equipment that arq essential to safety-related functions.
(3)
Design control measures shall be established for verifying the adequacy of design.
(4)
Equipment qualification records shall be maintained and shall include the results of tests and materials analyses.
The staff review is concentrated on materials which are sensitive to environmental effects, for example,
- seals, gaskets, lubricants, fluids for hydraulic systems, and diaphragms.
gualification documentation was reviewed by the staff to verify conformance with the above criteria.
The results of the staff review are presented in Section 4.3 of this report.
3.3 Service Conditions NUREG-0588 defines the methods to be utilized for determining the environmental conditions associated with loss-of-coolant accidents or high energy line
- breaks, inside or outside of containment.
The review and evaluation of the adequacy of these environmental conditions are described below.
The staff has reviewed the 'qualification documentation to ensure that the qualification conditions envelop the conditions established by the applicant.
3.3. 1 Temperature,
- Pressure, and Humidity Conditions Inside the Primary Containment 09/09/83 B"6 Palo Verde SSER 5
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The applicant provided the LOCA/MSLB profiles used for equipment qualification.
The peak values resulting from these profiles are as follows:
'F 300 370 Maximum
- Pressure,
~51 49 41
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X 100 100 The staff has reviewed these profiles and finds them acceptable for use in equipment qualification; i.e., there is reasonable assurance that the actual pressures and temperatures will not exceed these profiles anywhere within the specified environmental zone (except in the break zone).
3.3.2 Temperature,
- Pressure, and Humidity Conditions Outside the Primary Containment The applicant has provided the temperature,
- pressure, and humidity conditions associated with high energy line breaks outside containment.
The staff has used a screening criterion of saturation temperature at the calculated pressure to verify that the parameters identified by the applicant are acceptable.
The staff has previously accepted the HELB analysis in Section 3.6 of the SER.
3.3.3 Submergence The maximum submergence level established by the applicant is 10< ft. above the containment floor.
All s'afety-related equipment subjected to submergence is or will be qualified for the time duration necessary for it to complete it's safety function.
The applicant should provide a list of all equipment important to safety which could be subjected to submergence and provide justi-fication that failure of this equipment will not affect the safety function of any other equipment and will not mislead the operator.
The effects of flooding on equipment located outside containment have been evaluated to assure that safe shutdown can be achieved.
The staff's evaluation of the applicant's analysis is provided in Section 9.3.3 of the SER.
09/25/83 B-7 Palo Verde SSER 5
3.3.4 Chemical Spray Chemical spray is used for containment heat removal following a design basis accident.
The specified composition of the spray is 4400 ppm boron buffered with 50 ppm hydrazine with a pH of 7.0 to 8.5 using trisodium phosphate.
Equipment inside containment was reviewed for qualification under the above condition.
3.3.5 Aging The aging program requirements for Palo Verde electrical equipment are defined in Section 4, Category I of NUREG-0588.
The degrading influences of tempera-ture, radiation, vibration and mechanical stresses should be considered and included in the aging program.
This requires the establishment of a qualified life with maintenance and replacement schedules based on the findings.
In addition to the above, a maintenanc'e surveillance program should be implemented to identify and prevent significant age-related degradation in electrical and mechanical equipment.
The applicant has committed to follow the recommendations in Regulatory Guide 1.33, Revision 2, "guality Assurance Program Requirements (Operation)," which endorses American National Standard ANSI N18.7-1972, "Administrative Controls for Nuclear Power Plants."
This standard defines the scope and content of a maintenance/surveillance program for safety-related equipment.
Provisions for preventing or detecting age-related degradation in safety-grade equipment are specified and include:
(1)
Development of a maintenance program to maintain safety-related equipment at the quality required for it to perform its intended function.
(2)
Evaluation of causes of equipment failures and review of experience with failed equipment and similar components to determine whether a replacement component of the same type can be expected to'erform its function rel iably.
(3)
Inspection and performance testing to assure an appropriate quality level.
09/25/83 B-8 Palo Verde SSER 5
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(4)
Development of preventive maintenance schedules which describe the frequency and type of maintenance to be performed.
A preliminary schedule should be developed early in plant life. and it should. be refined and changed as experience is gained with the equipment.
(5)
Surveillance testing related to the results of reliability analyses, frequency and type of service, or age of the item or system, as appropriate.
The above guidelines apply to equipment located in both harsh and mild environments.
The applicant has described a program which incorporates the above guidelines with the exception of surveillance techniques to be utilized to identify significant age-related degradation in equipment.
Therefore, the applicant should furnish for staff review a description of the surveillance program to be developed and the specific techniques for the following three items:
(1)
Conax Electrical Penetration (2)
Reliance Electric Motor (3)
ASCO Solenoid Valve The staff will verify that the maintenance/surveillance program is implemented prior to fuel loading.
3.3.6 Radiation (Inside and Outside Containment)
The applicant has provided values for the radiation levels postulated to exist following a LOCA.
The application and methodology employed to determine these values were presented to the applicant in NUREG-0588 and NUREG-0737, "Clarifi-cation of TMI Action Plan Requirements."
The staff review has determined that the values to which equipment was qualified enveloped the requirements identi-fied by the applicant.
The value specified for use in equipment qualification in the containment is 3.3 x 10 rads gamma and 1 x 10 to 2 x 10 rads beta.
In the auxiliary
- building, a value of 6.4 x 10'ads gamma has been utilized in areas with 09/25/83 B"9 Palo Verde SSER 5
recirculatory fluid lines.
These values are acceptable for use in the qualification of equipment.
3.4 Environmental uglification Audit The staff conducted an audit of the applicant's qualification documentation and installed equipment on June 28-30, 1983.
Ten items of equipment were reviewed to determine if the test data and analysis in the files supported the qualification status determined by the applicant.
The following general
- comments, excluding the open items previously covered in this report, were made during the audit:
(1)
The arrangement and information contained in the files were very difficult to follow in some instances.
Much of the pertinent information was neither contained in the files nor was reference made to it.
(2)
During the plant walkdown the applicant was unable to locate two items (Rockbestos cable inside containment and pre-amplifier for excore detec.-
tor).
One item (ASCO Solenoid valve) didn't have <any name plate attached to it.
(3)
The applicant is using 30 days post accident operability for most equipment.
Only one item of equipment (HPCS pump motor) has been identi-fied to have an operability of 4 months.
The staff is reviewing the applicant's justification for using the 30 days post-accident operability time.
(4)
The staff reviewed ten files during the audit.
Several comments were made on these files.
The staff also informed the applicant during the exit interview that these comments should also be applied to other files, if applicable.
09/09/83 B-10 Palo Verde SSER 5
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The specific comments on the files are as follows:
(1)
Rockbestos Cable (13EM-058)
(a)
According to Test Report E058-13-4, radiation aging was completed by July 1976 while the DBA test was not done till February 1978.
An explanation of what occurred in between should be provided.
(b)
Temperature and pressure profiles do not envelop the required profiles.
No explanation is provided in the files regarding the acceptability of these profiles.
(c)
No margin is included for the temperature and pressure parameters, nor is justification provided in the file.
(d)
Operability time required is for 30 days while the test duration was only 16 days.
'An explanation should be provided on how 30 days operability, with margin, was achieved.
(e)
The status of the cable in the applicant's submittal and in the file is defined as qualified; however, APS has not approved the file.
(f)
The checksheet should identify the applicability and restriction of different test reports, e.g.,
Test Report E058-40-3 is not applicable A
to Palo Verde but is kept in the files only for reference, and Test Report E058-39-3 is applicable only for cable outside containment.
(g)
Although an outstanding deviation report had been issued by the APS for the subject cable, the status of the report was defined as qualified prior to resolution of the deviation.
(h)
The file was not arranged in a logical manner and much of the correspondence related to qualification was not included.
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(2)
ACSO Solenoid Valve (a)
The aging analysis did not take into account the temperature rise far. the.solenoid. valve caused by the energized condition.
During plant walkdown a thermometer placed on the surface of an energized solenoid indicated a temperature of 141.4 F while the ambient tem-perature was only 98 F. It should be noted that 141.4 F was only the surface temperature.
Temperatures inside the valve (coil and seat) will be higher than this value.
Aging analysis should take into account the temperature rise caused by the energized condition.
(b)
There are three test reports included for the solenoid valve; however, the informational relationship from one test report to another could not be easily followed.
The checksheet should refer to the specific report and paragraph from which information is utilized.
Also if Report AgS 2768 is used for valves outside containment only, then it should be so stated.
(3)
Solenoid Valve for Feedwater Isolation Valve The qualification testing does not'nvelop the required pressure profile.
The steam test was done at atmospheric pressure while the required pressure was 21 psig.
The file didn't contain any justifi-cation to explain this deficiency in the test report.
(4)
Rotork A C Motor 0 erators (a)
The applicant used the specified test environment as the qualification data rather than the actual test data.
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(b)
The wrong number W test cy es~ performed on the valve.
(c)
The 10'C rule was used for aging analysis without any justification given.
09/25/83 B-12 Palo Verde SSER 5
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(5)
RTDs and Thermocou les (Meed Instrumentation)
The qualification data sheet (gDS 841) states that the review of the file is complete and the only outstanding item is related to submer-gence.
However, the checklist in the file identified many open items which are not resolved.
Further review of the report was not conducted because of the many open items.
The applicant should review the status of this file.
'I (6)
Pneumatic Low Leaka e
Dam er The testing sequence for this item was radiation first before thermal aging.
Since radiation is the only harsh environment (excluding seismic) that it could be subjected to, this testing sequence should be explained.
(7)
Barton Transmitter The file for this item identified possible problems with lead corrosion and a recommended fix.
- However, correspondence
.to and from the manufacturer regarding the problem and documentation regarding whether the applicant will perform the recommended fix w'ere not included in the file.
The resolution of the concerns identified above must be provided 60 days prior to issuance of an operating license.
3.5 Outstandin E ui ment For safety-related items not having complete qualification documentation, the applicant has provided commitments for corrective action and schedules 'for completion.
For items not expected to.have full qualification, analyses will be performed in accordance with paragraph (i) of 10 CFR 50.49 to ensure that the plant can be operated safely pending completion of environmental qualifi-cation.
These analyses must be submitted to staff prior to granting of an operating license.
Section
- 3. 1 of this report discusses additional equipment 09/25/83 B"13 Palo Verde SSER 5
which may'require qualification based on 10 CFR 50.49.
These items must be identified to the staff and included in the qualification program.
- 4. 0 QUALIFICATION OF EQUIPMENT The following subsections present the staff's assessment of safety-related electrical equipment based on the applicant's submittal, audits of documenta-tion at the plant site, information in the NRC Equipment gualification Oata Bank,'nd previous staff evaluations of equipment in other plants.
- 4. 1 Safet -Related Electrical E ui ment The staff electrical equipment in a harsh environment into three categories:
(1) equipment requiring replacement prior to plant startup, (2) equipment requiring additional qualification information or corrective
- action, and (3) equipment considered acceptable pending implementation of the maintenance and surveillance program.
Attachments listing equipment in these categories are included with this report.
- 4. 1.1 Equipment Requiring Replacement Prior to Plant Startup There is no equipment in this category for the Palo Verde Nuclear Generating
- Station, Units 1, 2 and 3.
- 4. 1.2 Equipment Requiring Additional Information and/or Corrective Action Attachment A identifies equipment in this category.
Corrective action or deficiencies are noted by a letter relating to the legend identified below.
09/25/83 B-14 Pal o Verde SSER 5
~Le end A
- material-aging evaluation; replacement schedule; ongoing equipment surveillance CS
- chemical spray EXN - exempted equipment justification inadequate H
- humidity I
- HELB evaluation outside containment not completed M
- margin P
- pressure gI
- qualification information being developed gM
- qualification method gT
- qualification time R
- radiation RPS
- equipment relocation or replacement schedule provided RTS
- retest, schedule provided S
- submergence SEN
- separate effects qualification justification inadequate T
- temperature AC
- accuracy These deficiencies do not necessarily mean that the equipment is unqualified.
However, the deficiencies are cause for concern and require further case-by-case evaluation.
The applicant should resolve these deficiencies and document the resolutions in an auditable form.
- 4. 1.3 Equipment Considered Acceptable or Conditionally Acceptable Based on the staff review, the items identified in Attachment B have been determined to be acceptable, pending implementation of the maintenance/surveil-lance program.
4.2 Safet -Related Mechanical E ui ment The applicant shall submit information to demonstrate the adequacy of thel mechanic'al equipment qualification program.
A brief description of the program, 09/09/83 8-15 Palo Verde SSER 5
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including the qualification by test, analysis, and/or vendor certification, shall be submitted to the staff for review.
Vendor certifications alone are not evidence of qualification and are not acceptable to the staff.
The.staff requires the following information to complete this review:
(1)
A complete list of safety-related mechanical equipment and harsh environment locations.
(2)
The results of the review performed for mechanical equipment, i.e., identification of qualified equipment and corrective actions for unqualified equipment.
The staff has selected three equipment items from the preliminary list and requires the applicant to submit complete infor-mation including (a) detailed drawings with the complete bill of material for the equipment, (b) required environmental service conditions (tempera-ture, radiation), (c) qualification information for non-metallic materials, and (d) copies of the reference documents used to demonstrate the qualifi-cation.
The items selected are listed below.
(a)
Pressure relief valve (Spec.
¹J691)
(b)
Air Handling Units (Spec.
¹M721B)
(c)
High Pressure Safety Injection Pump (Spec.
¹PE-410)
(3)
For any safety-related mechanical equipment for which qualification can not be established prior to fuel load, justification should be provided for interim operation using the guidelines of 10 CFR 50.49.
- 5. 0 CONCLUSIONS The staff has reviewed and eva1uated the Palo Verde program for the environmental qualification of electrical and mechanical equipment.
This review has included the systems selected for qualification, the environmental conditions resulting from design basis accidents, the methods used for qualification and the 09/09/83 B-16 Palo Verde SSER 5
documentation for specific items of equipment.
The following items are outstanding and must be resolved prior to issuance of an operating license.
(1)
Information demonstrating qualification of all electrical equipment located in a harsh environment, including certain nonsafety-related equipment, equipment required by the TMI Action Plan, and installed Regulatory Guide 1.97 equipment should be provided, as discussed in Section
- 3. 1 of this report, or justifications for interim operation in accordance with 10 CFR 50.49 must be supplied.
The qualification infor-mation or justifications should be submitted with sufficient time for staff review and approval prior to issuance of an operating license.
(2)
Additional information concerning surveillance techniques to be utilized for detecting age-related degradation of equipment, as discussed in Section 3.3.5, should be provided.
(3)
Equipment in the containment potentially exposed to submergence must be identified and qualified, as discussed in Section 3.3.3.
(4)
The outstanding items identified during the site audit by the staff, as described in Section 3.4, must be resolved.
(5)
The information requested by the staff in Section 4.2, to demonstrate an adequate mechanical equipment qualification program, must be provided.
Based on these considerations, the staff concludes that satisfactory completion of the corrective actions identified herein wi'll ensure conformance with the requirements of 10 CFR 50.49 and relevant parts of General Design Criteria 1 and 4 of Appendix A; Sections III, XI, and XVII of Appendix B, 10 CFR 50; and the criteria specified in NUREG-0588.
In addition to the above, for Units 2 and 3, the applicant must identify all equipment that is not identical to Unit 1 equipment and/or is located in areas in which environmental conditions are more severe than the demonstrated valu es for Unit 1.
For any such equipment, the applicant shall submit complete qualification information, or justifications for interim operation, prior to issuance of an operating license for those units.
09/25/83 B-17 Palo Verde SSER 5
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Attachment A
EQUIPMENT REQUIRING ADDITIONAL INFORMATION OR CORRECTIVE ACTION (CATEGORY 4. 1.2)
Equipment Item Manufacturer Model No.
Deficiency/
Corrective Action 480 V Motor Control Centers Aux. Relay Cabinets Low Voltage Elec.
Penetration Medium Voltage Elec. Penetration Instrumentation Elec.
Penetration 600 V Power Cable 600 V Control Cable Inside Contmt.
Prefab Cable Inside Contmt.
Prefab Cable Ring Tongue Terminals High Voltage Terminations, 5
KV & 15 KV Heat Shrinkable Kit Heat Shrinkable Kit
- 4. 16 KV Transfer SW.
'Hydrogen Recombiner Panel Hand SW Fuel Pool Panel Hand SW.
Ccntmt.
Hz Monitor Acoustic Monitor Acoustic Monitor GE Harl o Conax Conax Conax Rockbestos Brand-Rex BIW BIW AMP Raychem
'Raychem Raychem ITE Comsip Delphi Comsip Delphi TEC TEC 1C7700 XLPE XLPE Silicone FR-EP NHVT NHCK, NHBK,
- NESK, WCSF-N NMCK8 HPL-C Micro SW.
PTSB-C2-12-C GE 10CG211 K III BBN424ISO 424-C2 QI QI R,
M, CS, A
R, A
QI T, P, QT, A" QI QI M, R, A
M, R, A
QI R,
A QI M,
A QI QI QI QI QI In addition to the deficiences identified, the staff has recently received addi-tional information concerning the acceptability of Rockbestos cable test reports.
The qualification of this cable is currently under investigation by the staff and additional information and/or test data may be required prior to OL issuance.
09/25/83 B"18 Palo Verde SSER 5
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Attachment A (Continued)
EQUIPMENT REQUIRING ADDITIONAL INFORMATION OR CORRECTIVE ACTION (CATEGORY 4. 1. 2)
Equipment Item Manufacturer Model No.
Deficiency/
Corrective
.-Action Acoustic Monitor Preamplifier Transient Shield Rad.
Resistant Cable Level T. ansmitter RTD's and Thermocouples Position Transmitter s Solenoid Valve Solenoid Valve Solenoid Valve Solenoid Valve AC MOV Operator Aux.
FWP Turbine Control MSIV Pressure Transmitter FWIV Pressure Transmitter FWIV Solenoid Valve MSIV Solenoid Valve Electric Low Leakage Damper Pneumatic Low Leakage Damper Solenoid Valves Limit Switches Essential AH Unit Heater Hq Recombiner Blower Motor TEC TEC TEC TEC Delaval Gems Weed Inst.
Schaevitz Target Rock Target Rock Target Rock Target Rock Henry Pratt Custom Built Anchor Darling Anchor Darling Anchor Darling Anchor Darling Waldinger Waldinger Waldinger Waldinger Nutherm Rockwell 2273AMI TEC-504A TEC-160-2 2273-C2
ÃM-54854 RTD-611 C4" C" 2-A2-0~
-K28250G~
HPA-10000 76HH-002 76HH-009-010 76HH-007, 008 76HH-009,
- 011, 013
-001, 005 Limitorque SMB-00-40 Rosemount 1152GP Rosemount 1152GP Skinner V5H65590 Skinner V5H65590 ITT NH95 Fisher 656 ASCO NP8320 Namco EA170 QI QI QI QI QI QI QI QI QI QI QX QI QI QI QI QI QI QI QI QI QI QI QI 09/25/83 B-19 Palo Verde SSER 5
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Attachment A (Continued)
EQUIPMENT REQUIRING ADDITIONAL INFORMATION OR CORRECTIVE ACTION (CATEGORY 4. 1. 2)
Equipment Item Manufacture Model No.
Deficiency/
Corrective Action Hz Recombiner package except Blower Motor A.C. Motor Operators AC Motor Operators for Contmt. Isol. Valves AC 8 DC Motor operators for MS and FW Isol. Valves MOV Actuator, (Aux Bldg SIS)
MOV Actuator (Contmt Bldg SIS)
Limit SW (Contmt Bldg)
Solenoid Valve (Contmt Bldg)
Solenoid Valve Process System Solenoid Valve (Contmt Bldg)
Solenoid Valve (Contmt Bldg)
Level Transmitter Diff. Press.
Transmitter Pressure Transmitter Pressure Transmitter Pressure Transmitter Level Transmitter Level Transmitter Level Transmitter Transmitter Rack RTD Rockwell Dresser Anchor Darling Anchor Darling Limitorque Limitorque Limitorque Limitorque Limitorque Namco Valcor Target Rock ASCO ASCO ITT Barton ITT Barton ITT Barton Rosemount ITT Barton ITT Barton ITT Barton ITT Barton CE RDF Rotork 7NAB1-43 Limitorque SB 7 ~ 5 Limitorque SB-0-40 Various SB-1-60 SMB-00"15 SMB-0-25(DC)
SMC-04-5, 7 1/2 Various EA 180 V-526-5683-45 77L"001 NP8320A187E.
NP8320A1B7E 764 764 763 1153AD8 763 763 763 763 21245 QI QI QI QI QI QI QI QI S,
A S,
A QI S,
A S,
A QI QI QI QI QI QI QI QI QI QI 09/09/83 B-20 Palo Verde SSER 5
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Attachment B
EQUIPMENT CONSIDERED ACCEPTABLE PENDING IMPLEMENTATION OF AGING PROGRAM (CATEGORY 4. l. 3)
Equipment Item 5
KV Power Cables 600 V Control Cables Coaxial Cables Manufacturer Anaconda Brand-Rex Brand-Rex Shielded Thermocouple Extension Anaconda Cable Model No.
FR-EP Ins
~
XLPE Ins.
Neoprene Jkt XLPE Ins.
Hypalon Jkt FR-EP Ins.
Hypalon Jkt Shielded Instrumentation Cable Outside Contmt Prefab Cable Pressure Transmitter Level Transmitter Flow Transmitter Pressure Transmitter I/P Convertor Level Switch DC MOV Actuator AC MOV Actuator Limit Switch Solenoid Valve AC MOV Actuator Aux FW Pump Motor Aux FWP Valve Essential CW Pump Motor MSIV Limit Switch FWIV Limit'.Switch Essential Air Handling Motor Essential Air Handling Motor Hz Recombiner Fan Motor Anaconda Bendix/Anaconda Erickson Rosemount Rosemount Rosemount Rosemount Masoneilan Magnetrol CCI CCI Namco CCI Henry Pratt W
Anchor Darling Anchor Darling Reliance Reliance FR-EP Ins.
Hypalon Jkt FR-EP, CPE Jkt 1153G87 1153DB4 1153DB5 1153GB9 8005A FLS-X-MPX-SIMD4DC Limitorque SB-00-10 Limitorque SB-00-10 EA 180 ASCO 206-381"44 Limitorque SMB-00-2 4x6x10 1/2 B, MSD-8 STG SMB-000 HSWF Frame 6808L Namco EA 180 Namco EA 180 09/25/83 B-21 Palo Verde SSER 5
Attachment B (Continued)
EQUIPMENT CONSIDERED ACCEPTABLE PENDING IMPLEMENTATION OF AGING PROGRAM (CATEGORY 4. 1. 3)
Equipment Item Manufacturer.
,Model No.
Limit SW for MS Blowdown Isol. Valve Limit SW for MS and FW Isol. Valves Solenoid Valves for MS 8 FW Isol. Valves AC MOV Operators Limit SW for Radwaste Sump Pump Discharge Valve Solenoid Valves for Radwaste Sump Pump Discharge Valve Solenoide Valve for MS Blowdown Isol. Valve Limit SW (Aux Bldg)
Solenoid Valve (Aux Bldg)
Solenoid Valve (Aux Bldg)
Solenoid Valve (Aux Bldg)
HPCI Pump Motor LPCI Pump Motor CS Pump Motor Charging Pump Motor Motor to Spray Chemical Addition Pump Excore Detector Assy Encore Preamplifier/filter Assy Pressure and Flow Transmitter (Aux Bldg)
Flow and Level Transmitter (Aux Bldg)
Anchor Darling Anchor Darling Anchor Darling Limitorque Anchor Darling Anchor Darling Anchor Darling Namco Valcor ASCO ASCO W
W W
W Reliance W
W Rosemount Rosemount Namco EA 180 Namco EA 180 ASCO NP831654E SB-00-7.5 Namco EA 180 ASCO NP831654E ASCO NP831664E EA 180 V-526"5683-6 NP8320A187E NP8321A1E 5810HWP2 5010P39WP2 5808P39WP2 404TS DP 18FTC TEFC-XT WL"24036 WL-24037 1153B 1153B 09/25/83 B"22 Palo Verde SSER 5
l I
Attachment C
SAFETY-RELATED SYSTEMS IN THE. ENVIRONMENTAL QUALIFICATION PROGRAM
- Function, System 1.
Emergency Reactor Shutdown Reactor Coolant Safety Injection and Shutdown Cooling Chemical and Volume Control Reactor Protection Excore Neutron Monitoring 2.
Containment Isol'ation Main Steam Aux Feedwater Safety Injection and Shutdown 'Cooling Chemical and Volume Control Nuclear Sampling Containment Hydrogen Control Radiation Monitoring Gaseous Radwaste Radioactive Waste Drains 3.
Reactor Core Cooling Reactor Coolant Safety Injection and Shutdown Cooling Fuel Pool Cooling 4.
Containment Heat Removal Safety Injection and Shutdown Cooling Containment -
HVAC 09/25/83 B-23 Palo Verde SSER 5
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I
Attachment C (Continued)
SAFETY-RELATED SYSTEMS IN THE ENVIRONMENTAL QUALIFICATION PROGRAM Function System 5.
Core Residual Heat Removal Main Steam Aux Feedwater Condensator Transfer and Storage Safety Injection and Shutdown Cooling Essential Spray Pond Essential Cooling Water 6.
Prevention of Significant Release of Radioactive Material to Environment Reactor Coolant Safety Injection and Shutdown Cooling HVAC - Fuel Building HVAC - Control Building Containment Hydrogen Control Containment Purification 09/25/83 B"24 Palo Verde SSER 5
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Attachment C (Continued)
SAFETY"RELATED SYSTEMS IN THE ENVIRONMENTAL QUALIFICATION PROGRAM Function System 7.
Support Systems Essential Spray Pond Essential Cooling Water Essential Chilled Water HVAC - Fuel Building HVAC -
DG Building DG Fuel Oil and Transfer Diesel Generator Class lE 4. 16 KV Power Class 1E Standby Generation Class 1E 480 V Power MCC Class 1E 125VDC Power Class lE Instrument AC Power Engineered Safety Features Actuation Reactor Protection Excore Neutron Monitoring Radiation Monitoring Demineralized Water Fuel Pool Cooling Nuclear Cooling HVAC - Aux Bldg HVAC - Containment Gaseous Radwaste Radioactive Waste Drains Instrument and Service Air Fire Protection Service Gas 09/25/83 B-25 Palo Verde SSER 5
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