ML18081B192
| ML18081B192 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/29/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 8003140390 | |
| Download: ML18081B192 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 Docket-No. 50-272 Public Service Electric and Gas Company ATTN:
Mr. F. W. Schneider Vice President - Production 80 Park Place Newark, New Jersey 07101 Gentlemen:
February 29, 1980 Enclosed is supplemental information to IE Bulletin No.79-018.
This information is presented in the form of generic questions and answers which will assist you in responding to the actions required of IE Bulletin No.79-018 issued on January 14, 1980. Should you have any questions regarding this supplemental information, please contact this office.
Sincerely,
Enclosures:
- 1.
Supplemental Information to IE Bulletin No.79-018 w/Attachments
- 2.
List of Recently Issued IE Bulletins CONTACT:
S. 0. Ebneter (215-337-5296) cc w/encls:
F. P. Librizzi, General Manager - Electric Productfon E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station Q
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- ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 SSINS No: 6820 Accessions No:
7912190696 ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT IE Bulletin No. 79-0lB Supplemental Information Date:
February 29, 1980 Page 1 of 1 Enclosed are the generic questions and answers which resulted from NRC Task Group/Licensee 11workshop 11 meetings held recently in NRC Regional Offices.
regarding IE Bulletin No. 79-0lB.
This information is intended to further the understanding of the qualification review process and reporting requirements of the Bulletin.
The further intent of this information is to assist the licensees in providing a method of approach acceptable to the assigned NRC Task Review Group in determining adequacy of the environmental qualification of Class IE Electrical Equipment installed at their respective facilities.
I.t s.houl d be recognized that the review of. the 1icensee 1 s responses may generate additional need for guidance of finalized resolution of the environmental qualification issue.
Attachment:
Generic Questions and Answers to IE Bulletin No.79-018
Question 1 Answer 1 Question 2 Answer 2 Question 3 Answer 3 Attachment toSupplemental Information to IE Bulletin No. 79-0lB GENERIC QUESTIONS AND ANSWERS TO IE BULLETIN NO. 79-0lB IEB 79-0lB indicates the scope of the task is only that equipment exposed to a harsh env.i ronment. Enclosure 4, Section 4.3.3 identified areas outside of containment not exposed to harsh environmental conditions as the results of an accident. Should these areas be included in our evaluations?
No. Although the guidelines encompass all safety-related
- electrical equipment and components, the scope of IEB 79-0lB
. is limited to only that electrical equipment which is exposed to the harsh environments identified in action item 1, including where fluids are recirculated from inside containment to accomplish long-term cooling following a LOCA. All equipment and components identified in action item 1 shall be included in,
the subsequent actions required by IEB 79-0lB.
IEB 79-0lB action item 1 and Enclosure 4 indicate that emergency procedures be used to identify equipment to be included in the master list. Should all the equipment identified in the emergency procedures be included in the master list?
All the equipment the licensee relies upon in the emergency procedures to mitigate design basis events that may be exposed to a harsh environment must be identified in response to Question 1.
It is not the intent of this task to change the existing procedures by removing references to equipment or components that are considered nonessential and not environmentally qualified. This master list identifies all equipment and components that must be evaluated in response to action item 4. A determination should be made that sufficient equipment is environmentally qualified to permit accident mi~igation. A tabulation of other equipment or components which are referenced in the Emergency Procedures but are not relied upon should be available for NRC review. Justification
. should also be available so that thi~ non-qualified equipment.
will not b~ misleading to the operator.
Is note 2 of Appendix A to Enclosure 4 within the scope of this task?
Only those emergency shutdown systems that could be used for mitigation of a LOCA or HELB and are exposed to a harsh environment identified in response to Question 1. Licensee review should:
(1) identify equipment that could be used to achieve cold shutdown following LOCA or HELB; and (2) determine if environmental qualification exists. For equipment that is not environmentally qualified the licensee should either provide plans to qualify this equipment or provide justification that qualification is not needed to achieve safe shutdown to meet licensing requirements applicable to your facility.
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Question 4 Answer 4 Question 5 Answer 5 Question 6 Answer 6 Question 7 Answer 7 Question 8 Attachment to Supplemental Information to IE Bulletin No. 79-0lB What is the basis for the 340 Degrees F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> requirement identified in Enclosure 4 and NUREG 0588, Figure C 1?
For minimum high temperature conditions in pressure suppression type containments, we do not require that 340 Degrees F for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> be used for BWR drywells or that 340 Degrees F for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> be used for PWR ice condenser lower compartments. These
- values are from a bounding high temperature profile (see Section 1.1 and 1.2 of NUREG 0588) that can be used in lieu of a plant specific profile, provided that expected pressure and humidity conditions as a function of time are accounted for.
In general, the containment temperature and pressure conditions as a function of time should be based on analyses in the FSAR.
However, these conditions should bound that expected for coolant and steam line breaks inside the containment. The steam line break conditions should include superheated conditions: the peak temperature, and subsequent temperature/pressure profile as a function of time. If containment spray is to be used, the impact of the spray on required equipment should be accounted for.
Should equipment or systems which are presently planned to be modified as a result of actions, such as lessons learned, to be included in the response to !EB 79-0lB?
No.
Will there be any other actions required when the NRC completes its evaluation of the responses to !EB 79-0lB and any related corrective actions deemed necessary are complete?
The NRC staff does not foresee any additional actions for the electrical equipment and components which are included in the scope of !EB 79-018; however, if new problems or concerns are identified, appropriate action will be taken.
Are Spare Parts required to meet 79-0lB?
Yes. The Spare Parts are required to meet the same criteria as the installed electrical equipment or component resulting from the evaluation of !EB 79-018.
The instruction sheet for Enclosure 3 11System Component Evaluation 11 indicates that outstanding items be identified.
What is the definition of outstanding items?
Answer 8
. Question 9 Answer 9 Question 10 Answer 10 Question 11 Answer 11 Question 12 Answer 12 Question 13 Answer 13 Attachment to Supplemental Information to IE Bulletin No.79-018 An outstanding item is defined as that item that does not meet the environmental qualification guidelines and requirements of IE8 79-01.
Are the requirements and positions in NUREG 0588 the same as those in NUREG 0578 in relation to environmental qualification of electrical equipment and components?
Yes. -
NUREG 0588 is out for comment. Does the staff expect any
- significant changes which may impact this effort?
No.
When it is determined, as a result of the efforts required by IE8 79-018, that specific equipment be upgraded, are the guidelines in Enclosure 4 to be used?
As a minimum the same requirements that were used to determine the acceptability of the electrical equipment and components within the scope of.IEB 79-018 may be used; however, if equipment is available which meets the requirements of IEEE 323-1974 it should be used.
Does the Licensee Event Report (LER) requirements of lEB 79-018 supercede or change the reporting requirements
- al ready defined?
No. The requirement for reporting in IEB 70-018 doe*s not change the reporting requirements defined in.the license conditions.
Are only those items known to be unqualified immediately reportable whereas items for which there is no data or insufficient data are open items.to be resolved, but are not immediately reportable?
- When a determination has. been made that the existing data is inadequate or no data exists to have reasonable assurance that the Class IE electrical equipment components can perform their safety-related function required in the specified*
FSAR environments, that is reportable per IEB 79-018. The time and technical judgments required to make the determination should be based on the significance of the specific equipment, components and the discrepancies.
Attachment to Supplemental Information to IE Bulletin No.79-018 Question 14 Are the results of an evaluation using the materials identified in Enclosure 4, Appendix C, of an acceptable method of addressing the effects of aging within the scope of Bulletin 7~01~
Answer 14 Yes, for those materials on the list, however, Appendix C indicates this is a partial list. Your evaluation in response to
- IE8 79-018 may identify other materials that are susceptible to significant degradation.
Question 15 What are the sources Appendix C':'"l used to identify the materials in Table C-1 and establish the failure levels?
Answer 15 Typical sources for the information are given in Appendix C.
Your information of materials not on this table should identify the source for your evaluation.
Question 16 Is additional effort or calculations required for radiation
,service conditions if previous efforts did not utilize the methodology or assumptions identified in NUREG 0588?
Answer 16 Yes, the extent of the effort required will be dependent on the significance of the difference in methodology and assumptions.
Question 17 Will extension of time be granted for schedules if identified in IE8 79-018 action item 7.
Answer 17 The schedule was based on the significance of the safety concerns relating to the adequacy of environmental qualification of electrical equipment or components. Any projected deviations from these schedules should be identified to the Regional Office by a written request. The NRC staff wi 1.1 make a determination on a case-by-case basis.
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Bulletin
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79-02 (Rev. 2) 79-26 79-27 79-28 79-018 80-01 80-02 80-03 79-018 ENCLOSURE 2 RECENTLY ISSUED IE BULLETINS Subject Date Issued Pipe Base Plate Designs 11/8/79 Using Concrete Expansion Bolts Boron Loss From BWR 11/20/79 Control Blades Loss of Non-Class-1-E 11/30/79 Instrumentation and Con-trol Power System Bus During Operation Possible Malfunction 12/7/79 of NAMCO Model EA180 Limit Switches at Elevated Temperatures Environmental Quali-
.fication of Class IE Equipment 1/14/80 Operability of ADS Valve 1/14/80 Pneumatic Supply Inadequate Quality Assurance for Nuclear Supplied Equipment 1/21/80 Loss of Charcoal From 2/6/80 Standard Type II, 2 Inch, Tray Adsorber Cells Environmental Quali*
fication of Class IE Equipment 2/29/80 IE Bulletin No. 79-0lB Supplemental Information Date: February 29, 1980 Page 1 of 1 Issued To All Power Reactor Facilities with an Operating License (OL) or Construction Permit (CP)
All BWR Power Reactor Facilities with an OL All Power Reactor Facilities with an OL and those nearing Licensing (for Action)
All Power Reactor Facilities with a CP (for Information).
All Power Reactor Fatilities with an OL or CP All Power Reactors with an OL except SEP Plants All BWRs with an