ML20003G045
| ML20003G045 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1981 |
| From: | Carroll D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Wright G ILLINOIS, STATE OF |
| References | |
| NUDOCS 8104280127 | |
| Download: ML20003G045 (2) | |
Text
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'o UNITED STATES NUCLEAR REGULATORY COMMISSION g
.t REGION 111 L
799 ROOSEVELT ROAD GLEN ELLYN, ILLINOIS 60137 o
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Illinois Department of
%2s Nuclear Safety ATTN:
Mr. Gary N. Wright
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Deputy Director 1035 Outer Park Drive os to Springfield, IL 62704 Gentlemen:
The attached IE Information Notice No. 81-12 titled " Guidance on Order Issued Janaury 9, 1981 Regarding Automatic Control Rod Insertion on Low Control Air Pressure" was mailed on March 31, 1981, for information to the following licensees.
Cincinnati Gas & Electric Company Zimmer (50-358)
Cleveland Electric Illuminating Company Perry 1, 2 (50-440, 50-441)
Commonwealth Edison :ompany Dresden 1, 2, 3 (50-10, 50-237, 50-249)
Quad-Cities 1, 2 (50-254, 50-265)
LaSalle 1, 2 (50-373, 50-374)
Consumers Power Company Big Rock Point (50-155)
Dairyland Power Cooperative LACBWR (50-409)
Detroit Edison Company Fermi 2 (50-341)
Illinois Power Company Clinton 1, 2 (50-461, 50-462) l I
Iowa Electric Light & Power Company Duane Arnold (50-331) l 18104280 M
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Illinois Department of Nuclear Safety Northern Indiana Public Service Company Bailly (50-367)_
Northern States Power Company Monticello (50-263)-
Sincerely, t.
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WordProce,/Carro.
orothy E.
ll, Chief ssing and Document Control Section
Enclosure:
IE Information
. Notice No. 81-12 cc w/ encl:
Mr. D. W. Kane, Sargent & Lundy Central Files Reproduction Unit NRC 20b AE0D Resident Inspector, RIII J. G.~-Keppler, RIII C. E. Norelius, RIII R. E. Heishman, RIII J. A. Hind,-RIII P. R. Wohld, RIII PDR Local PDR-NSIC TIC I
A e
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SSINS No.:
6835 Accession No.:
8011040284 i
IN 81-12' UNITED STATES NUC! EAR REGULATORY COMMISSION 0FFICE 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 Description 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
IN 81-12 March 31, 1981 GUIDANCE ON ORDER TherequirementsofSectionIVoftheJanuary9,1981Orderarehuotedbelow 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 In addition to the 10 psi requirement the base setpoint should be at least 50 psi.
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 iso'ated 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 sL5 sequent 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 consideration 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 the tailure 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."
o IN 81-12 I
March 31, 1981 Page 2 of 2 4
GUIDANCE This criterion is applicable only for those automatic dump systems that do not interconnect with, or are fulry isolated from the reactor protection system.
For systems (tirectly interacting *,ith the reactor protection systems, the require-ments of Appendices A and B of 10 CFR 50 are fully applicable.
"(g) There shall !
a documented independent design review of the system."
GUIDANCE This statement is self-explanatory with the added proviso that the conclusion reached will not include any unreviewed safety question.
"(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 perform a fully integrated test, demonstration of the portions of the system is a satisfactory test until an integrated test can be performed 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 other 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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e Attachment.2 IN 81-12 g
March 31, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Date of Notice No.
Subject Issue Issued to 81-11 Alternate Rod Insertion 3/30/81 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 81-04 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
.