ML20004F568
| ML20004F568 | |
| Person / Time | |
|---|---|
| Site: | Hatch, Browns Ferry, Grand Gulf, Brunswick, Hartsville, Phipps Bend  |
| Issue date: | 03/31/1981 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Batum O, Jackie Jones, John Miller, Pack R, Parris H, Stampley N, Verdery E CAROLINA POWER & LIGHT CO., EDS NUCLEAR, INC., ENERGY, DEPT. OF, GEORGIA POWER CO., INSTITUTE OF NUCLEAR POWER OPERATIONS, MISSISSIPPI POWER & LIGHT CO., SOUTHERN COMPANY SERVICES, INC., TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 8106190097 | |
| Download: ML20004F568 (2) | |
Text
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Gentlemen:
The enclosed information notice provides guidance that has been issued to NRC inspectors to assist in their verification of the Order issued January 9,1981 regarding automatic control rod insertion on low control air pressure.
This guidance is for information purposes and does not establish new or added requirements.
No specific action or response is requested at this time; however, contingent on the results of further staff evaluation, a circular or bulletin may be issued to recommend or request specific licensee actions.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
W.!
""V James P. O'Reilly Director
Enclosures:
1.
IE Information Notice No. 81-12 2.
List of Recently Issued Information Notices 81o o l so09h 9
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5 Information Notice Nr 81-12 (INFORMATION)_
March 31, 1981 Mdresses In Reference To 1.
Carolina Power and Light Company 50-325 Brunswick Unit 1
~ Attn:
J. A. Jones 50-324 Brunswick Unit 2 Senior Executive Vice President and Chief Operating Officer 411 Fayetteville Street Raleigh, NC 27602 2.
Georgia P wer Company 50-321 Hatch Unit 1 Attn:
J'.
.i. Miller, Jr.
50-366 Hatch Unit 2 Executive Vice President 270 Peachtree Street
' Atlanta, GA 30303 3.
Mississippi Power and Light Company 416 Grand Gulf Unit 1 Attn:
N. L. Stampley 50-417 Grand Gulf Unit 2 Vice President of Production P. O. Box 1640 Jackson, MS 39205 4.
Tennessee Valley Authority 50-259 Browns Ferry Unit 1 Attn:
H. G. Parris 50-260 Browns Ferry Unit 2 Manager of Power 50-296 Browns Ferry Unit 3 500A Chestnut Street Tower II 50-518 Hartsville Unit 1 Chattanooga, TN 37401 50-519 Hartsville Unit 2 50-520 Hartsville Unit 3 50-521 Hartsville Unit 4 50-553 Phipps Bend Unit 1 50-554 Phipps Bend Unit 2 5.
Institute of Nuclear Power Operation Attn:
R. W. Pack Lakeside Complex 1820 Waterplace Atlanta, GA 30339 6.
Southern Company Services, Inc.
Attn:
- 0. Batum, Manager Nuclear Safety & Licensing Department P. O. Box 2625 Birmingham, AL 35202 1
7.
Department of Energy Clinch River Breeder Reactor Plant Project Office Attn:
Chief, Quality Improvement P. O. Box U Oak Ridge, TN 37830 8.
EDS, Nuclear, Inc.
Attn:
E. H. Verdery 330 Technology Park / Atlanta Norcross, GA 30092
l-SSINS No.:
6835 l
a e-Accessicn No.:
8011040284 IN 81-12 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 March 31,1981 IE Information Notice No. 81-12: GUIDANCE ON ORDER ISSUED JANUARY 9, 1981 REGARDING AUTOMATIC CONTROL R0D INSERTION ON LOW CONTROL AIR PRESSURE Descriotion of Circumstances:
The attached guidance has been provided to NRC inspectors to assist in the verification of BWR licensee action taken in implementation of the Order issued Janaury 9,1981 regarding automatic control rod insertion on low control air pressure.
This guidance may also be of interest to BWR licensees, but does not in itself establish new or additional requirements.
No written response to this information is required.
If you need additional information regarding this matter, please contact the Director of the appro-priate NRC Regional Office.
Attachments:
1.
Guidance on Order 2.
Recently issued Information Notices t
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IN 81-12 A-March 27, 1981 GUIDANCE ON ORDER The requirements of Section IV of the January 9, 1981. Order are quoted below p
with the appropriate guidance following each item.
"(1) An automatic system shall be operable to initiate control rod insertion on low' pressure in the control air header, which meets the following criteria:"
"(a) The system shall automatically initiate control rod insertion at 10 psi or greater above scram outlet valve opening pressure."
GUIDANCE Ir. addition to the 10 psi requirement the base setpoint should be at least 50 p:1.
If the setpoint is not at least 50 psi, NRR should be informed to determine whether any further action might be necessary.
"(b) The system shall not degrade existing safety systems (e.g., reactor protection system)."
GUIDANCE If the system is interconnected with the reactor protection system, its components shall be qualified and its design shall be safety grade (i.e., conform with applicable IEEE standards).
If the system is fully isolated or does not interconnect with the reactor protection system, its components shall be of a quality consistent with the requirements of item (d) below.
"(c) The system shall allow for scram reset."
GUIDANCE Scram reset is intended to accomplish only the return of control air and the subsequent closing of scram valves and opening of scram discharge instrumented volume (SDIV) vent and drain valves.
, "(d) The design shall consider the potential for inadvertent or unnecessary scrams."
GUIDANCE This cons'ideration would suggest the use of safety grade equipment for operational reliability reasons, but, as a minimum, control grade equipment may be used.
"(e) Any required power supply should not be subject to any failure mode which could also initiate the degraded-air conditions, unless it can be demonstrated that an automatic scram will occur promptly because of th'e failure mode of the power supply."
GUIDANCE This statement is self-explanatory.
"(f) The system is not subject to the requirements of Appendices A and B of 10 CFR 50."
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1 March 31, 1981 Page 2 of 2 GUIDANCE This criterion is applicable only for. those automatic dump systems that do not interconnect with, or are fully isolated from the reactor protection system.
Fo.r, systems directly irteracting with the reactor protection' systems, the require-ments of Appendices A and 8 of 10 CFR 50 are fully applicable.
"(g) There shall be a documented independent design review of the system."
GUIDANCE This statement is self-explanatory with the added proviso that the conciusion reached will not include any unreviewed safety questicn.
"(h) Before the system is declared operable, a documented preoperational test of the system will be successfully completed."
GUIDANCE An integrated system test should be performed in every case.
For those plants that remain operating and cannot p rform a fully integrated test, demonstration of the portions of the system is a satisfactory test until an integrated test can be perforned at the earliest outage for any purpose.
"(i) The system shall be functionally tested at each unit shutdown, but not be tested more-than once each 90 days."
GUIDANCE This statement is self-explanatory.
"(2) After April 9, 1981, the Automatic Dump System as described above shall be operable in all modes cther than shutdown and refueling or the unit shall be placed in a cold shutdown condition within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unless system operability is restored."
GUIDANCE This statement is self-explanatory.
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IN 81-12 March 31, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of.
Notice No.
Subject Issue Issued to 81-11 Alternate Rod Insertion 3/20/81 All BWR facilities for BWR Scram Represents with an OL or CP a Potential Path for Loss of Primary Coolant 81-10 Inadvertant Containment 3/25/81 All power reactor Spray Due to Personnel facilities with an
. Error OL or CP 81-09 Degradation of Residual 3/26/81 All power reactor Heat Removal (RHR) System facilities with an OL or CP 81-08 Repetitive Failures of 3/20/81 All power reactor Limitorque Operator SNB-4 facilities with an Motor-to-Shaft Key OL or CP 81-07 Potential Problem with 3/16/81 All power reactor Water-Soluble Purge Dam facilities with an Materials Used During OL or CP Inert Gas Welding 81-06 Failure of ITE Model 3/11/81 All power reactor K-600 Circuit Breaker facilities with an OL or CP 81-05 Degraded DC System at 3/13/81 All power reactor Palisades facilities with an OL or CP 81-b4 Cracking in Main Steam 2/27/81 All power reactor Lines facilities with an OL 81-03 Checklist for Licensees 2/12/81 All power reactor Making Notifications of facilities with an Significant Events in OL Accordance with 10 CFR 50.72 81-02 Transportation of 1/23/81 All Radiography Radiography Devices licensees OL = Operating Licenses CP = Construction Permits l