ML18138A088
| ML18138A088 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 02/29/1980 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| NUDOCS 8003180195 | |
| Download: ML18138A088 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II In Reply Refer To:
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~-50-281 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 FEB 2 9 198Q Virginia Electric and Power Company Attn:
J. H. Ferguson Executive Vice President-Power P. O. Box 26666 Richmond, Virginia 23261 Gentlemen:
Enclosed is Supplement Information to IE Bulletin No. 79-0lB.
This infor-mation is presented in the form of generic questions and answers which will assist you in responding to the actions required of IE Bulletin No. 79-0lB with regard to your power reactor facility(ies) with an operating license.
Should you have questions regarding this Supplement Information, please contact this office.
Enclosure:
IE Bulletin No. 79-0lB Supplement Information Sincerely,
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Jam;s P. O'Re1_1~
Director
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Virginia Electric and Power Company cc w/encl:
e W.R. Cartwright, Station Manager Post Office Box 402 Mineral, Virginia 23117 P. G. Perry Senior Resident Engineer Post Office Box 38 Mineral, Virginia 23117 W~ L. Stewart, Manager Post Office Box 315 Surry, Virginia 23883
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UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND_ENFORCEMENT WASHINGTON, D.C.
~0555 February 29, 1980 SSINS No. :
6820 Accession No. :
7912190696 IE Bulletin No. 79-0lB Supplement Information ENVIRONMENTAL QUALIFICATION OF CLASS IE EQUIPMENT Enclosed are the generic questions and answers which resulted from NRC 'Task Group/Licensee "workshop" meetings held recently in NRC Regional Offices regarding IE Bulletin No. 79-0lB.
This informat~on 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.
It should be recognized that the review of the licensee's responses may generate additional need for guidance of finalized resolution of the environmental qualification issue.
Enclosure:
Generic Questions and Answers to IE Bulletin No. 79-0lB
Question 1 Answer 1 Question 2 Answer 2 Question 3 Answer~):
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GENERIC QUESTIONS AND ANSWERS TO IE BULLETIN NO. 79-0lB
!EB 79-0lB indicates the scope of the task is only that equipment exposed to a harsh environment., 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 ev~luations?
No.
Although the guidelines encdmpass all safety-related electrical equipment and components, the scope of !EB 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 accom-plish long-term cooling following a LOCA.
All equipment and components identified in action item 1 shall be included in the subsequent actions required by !EB 79-0lB.
!EB 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 eq~*fpment 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 mitigation.
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 this non-qualified equipment will::,not be 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 environ-ment 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.
r Question 4 Answer 4 Question 5 Answer 5 Question 6 Answer 6 Question 7 Answer 7 Question 8 2 -
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 co~ditions in pressure suppression type containments, we do not require that 340 Degrees F for 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />s* 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 Sections 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, be included in the response to IEB.7,9-0lB?
No.
Will there be any other actions required when the NRC completes its evaluation of the responses to IEB 79-0lB and any related corrective actions :;:<ieemed nece'ssary are complete?
The NRC staff does not fore~e any additional actions for the electrical equipment and components which are included in the scope of IEB 79-0lB; however, if new problems or concerns are identified, appropriate action will be taken.
At.'-": 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 IEB 79-0lB.
The instruction sheet for Enclosure 3 "System Component Evaluation" 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 e
3 -
An outstanding item is defined as that item that does not meet the environmental qualification guidelines and requirements of IEB 79-0lB.
Are-the requirements and positions in NUREG 0588 the same as those in NUREG 0578 in relation io 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 IEB 79-0lB, that specific equipment be upgraded, are the guide-lines 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 79-0lB 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 IEB 79-0lB supercede or change the reporting requirements already defined?
No.
The requirement for reporting in IEB 70-0lB does not change the reporting requirements defined in the license conditions.
Are only those items known t~ be unqualified immediately
~eportable whereas*ttems 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 environ-ments, that is reportable per IEB 79-0lB.
The time and technical judgments required to make the determination should be based on the significance of the specific equipment, components and the discrepancies.
Question 14 Answer 14 Question 15 Answer 15 Question 16 Answer 16 Question 17 Answer 17 e
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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 79-0lB?
Yes, for those materials on the-list, however, Appendix C indicates this is a partial list: Your evaluation in response to IEB 79-0lB may identify other materials that are susceptible to _significant degradation.
What are the sources Appendix C-1 used to identify the materials in Table C-1 and establish the failure levels?
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.
Is additional effort or calculations required for radiation service conditions if previous efforts did not utilize the methodology or assumptions identified in NUREG 0588?
Yes, the extent of the effort required will be dependent on the significance of the difference in methodology and assumptions.
Will extension of time be granted for schedules if identified in IEB 79-0lB action item 7.
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 will make a
.determination on a !ca.se-by-case basis.
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I' e
IE Bulletin No. 79-0lB Supplement Information Bulletin No.
79-0IB (Supple.)
80-04 80-03 80-02 80-01 79-0lB 79-28 79-27 79-26 79-25 79-17 (Rev. 1)
RECENTLY ISSUED IE BULLETINS Subject Environmental Qualifica-tion of Class IE Equip-ment Analysis of a PWR Main Steam Line Break With Continued Feedwater Addition Date Issued 2/29/80 2/8/80 Loss of Charcoal From 2/6/80 Standard Type II, 2 Inch, Tray Adsorber Cells Inadequate Quality 1/21/80 Assurance for Nuclear Operability of ADS Valve 1/11/80 Pneumatic Supply Environmental Qualification 1/14)80 of Class IE Equipment Possible Malfunction of 12/7/79 Namco Model EA 180 Limit Switches at Elevated Temperatures Loss Of Non-Class~l-E 11/30/79 Instrumentation and Control Power System Bus During Operation Boron Loss From BWR 11/20/79 Control Blades Failures of Westinghouse 11/2/79 BFD Relays In Safety-Related Systems Pipe Cracks ln Stagnant 10/29/79 Borated Water System At PWR Plants e
Enclosure February 29, 1980 Issued To All power reactor facilities with an Operting License All PWR reactor facilities holding OLs and to those nearing licensing All holders of Power Reactor OLs and CPs All BWR licenses with a CP or OL All BWR power reactor facilities with and OL All power reactor facilities with an OL All power reactor facilities with an OL or a CP All power reactor facilities holding OLs and to those nearing licensing All BWR power reactor facilities with an OL All power reactor facilities with an OL or CP All PWR's with an OL and for information,
to other power reactors l