ML19350E379
| ML19350E379 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Peach Bottom, Nine Mile Point, Oyster Creek, Hope Creek, Pilgrim, Susquehanna, Limerick, Vermont Yankee, FitzPatrick, Shoreham |
| Issue date: | 03/31/1981 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Counsil W, Curtis N, Daltroff S, Finfrock I, Kemper J, Lempges T, Martin T, Morisi A, Pasternak R, Pollock M, Rhode G, Rich Smith BOSTON EDISON CO., JERSEY CENTRAL POWER & LIGHT CO., LONG ISLAND LIGHTING CO., NIAGARA MOHAWK POWER CORP., NORTHEAST NUCLEAR ENERGY CO., PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC, PENNSYLVANIA POWER & LIGHT CO., POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK, Public Service Enterprise Group, VERMONT YANKEE NUCLEAR POWER CORP. |
| References | |
| NUDOCS 8106220033 | |
| Download: ML19350E379 (3) | |
Text
.
- o.
UNITED STATES
,.[} ) #( }
NUCLEAR REGULATORY COMMISSION
.4 REGION I O,
g[
" iI 631 PARK AVENUE h,
- V
,o KING OF PRUSSIA, PENNSYLVANIA 19406
.',iAR 31 iC81 p\\N 4
N' r-g
- Y Rg M
A v
h na
,\\
Gentlemen:
The enclosed IE Information Notice No. 31-12, " Guidance on Order Issued January oressure",
9,1981, Regarding Automatic Control Rod Insertion on Low Control Air is forwarded to you for information.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
- ncerely, Bo.e H. Grier Director
Enclosure:
1.
IE Information Notice No. 81-12 with 2 attachments CCNTACT:
- 0. L. Caphton (215-337-5266) ie l
300R ORGINAL 8106220033
u.C '
~,
e.
e s
LIST OF HOLDERS OF BWR POWER REACTOR OPERATING LICENSES AND CONSTRUCTION PERMITS RECEIVING g
IE INFORMATION NOTICE N0. 81-12 Boston Edison Company M/C Nuclear Docke; No. 50-293-1 ATTN: Mr. A. V.-Mo.isi-Nuclear Operations Support Manager
- 800 Boylston Street-Boston, Massachusetts 02199 Jersey Central Power and Light Company Occket No. 50-219'
. ATTN:. Mr. Ivan R. Finfrock, Jr.
Vice President Oyster Creek Nuclear' Generating Station P. 0. Box 388 Forked River, New Jersey L 31 Niagara Mohawk Power Corporation Occket No. 50-220 ATTN: Mr. T. E. Lempges
~Vice President Nuclear Generation 300 Erie Boulevard West Syracuse, New York 13202 Northeast Nuclear Energy Company Occket Nos. 50-245 ATTN: Mr. W. G. Counsil Senior Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Philadelphia Electric Company Docket Nos. 50-277 ATTN: Mr. S. L. Daltroff 50-278 Vice President Electric Production 2301 Market Street Philadelphia, Pennsylvania 19101 Power Authority of the State of New York Occket No. 50-333 James A. FitzPatrick Nuclear Power Plant ATTN: Mr. R. J. Pasternak Resident Manager P. O. Box 41 Lycoming, New York 13093
- Vermont Yankee Nuclear Power Corporation Docket No. 50-271 ATTN: Mr. Robert ~L. Smith Licensing Engineer 1671 Worcester Road Framingham, Massachusetts 01701 d.k
r_.
- p j' Ta g.
2 c
Long Island Lighting Company Docket No. 50-322 ATTN: Mr. M. S. Pollock.
-Vice President - Nuclear 175 East Old Country Road Hicksville, New York 11801
' Niagara Mchawk Power Corporation Occket No. 50-410
. ATTN: Mr. Gerald K. Rhede Vice President System. Project Management c/o Miss Catherine R.-Seibert 300 Erie Boulevard, West
. Syracuse, NY 13202 Pennsylvania Power & Light Company Docket Nos. 50-387 ATTN: Mr. Norman W. Curtis 50-388 Vice President Engineering and Construction - Nuclear 2 North Ninth Street A11antown, Pennsylvania 13101 Philadelphia Electric Company Docket Nos. 50-352 ATTN:
Mr.- John S. Kemper 50-353 Vice President Engineering and Research 2301 Market Street Philadelphia, Pennsylvania 19101 Public Service' Electric & Gas Company Docket Nos. 50-354 ATTN: Mr. T. J. Martin 50-355 Vice President Engineering and Construction 80-Park Plaza - 17C Newark, New Jersey 07101 f
I
+
SSINS N2.: 6835 Accession No.:
8011040284 IN 81-12 UNITED STATES NbCLEAR 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 R00 INSERTION ON LOW CONTR0L' 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 SWR licensees, but does not in itself establish new or additfora requirements.
No written response toLthis information is required.
If you nee'd 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
-7
w IN 81-12 March 31, 1981 GUIDANCE ON ORDER-The requirements of Section IV of the January 9,.1981 Order'are quoted below 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 determinc 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 eturn 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 consideration wculd 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 tc :ny failure mode which could also initiate the degraded-air conditions, unless it can be demonstr'ated that an automatic scram will occur promptly because of the failure mode of the power supply."
GUIDANCE - This statement is self-explanatory.
"(f) The system is not subject to the requirements lof Appendices A and B
' of 10 CFR 50."~
P" IN 81-12 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.
For systems directly interacting with the reactor protection systems, the require-ments of Appendices A and B 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 conc 1*Jsion 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 4.t the earliest outage for any purpose.
"(1) 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) Af ter April 9,1981, the Automatic Oump 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 hou: s unless system operability is restored."
GUIDANCE This statement is self-explanatory.
G 4
r a-IN 81-12 March 31, 1981 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notice No.
Issued 81-11 Alternate Rod Insertion 3/30/81 All holders of a for BWR Scram Represents BWR power reactor a Potential Path for OL or CP Loss of Primary Coolant 81-10 Inadvertant Containment 3/25/81 All holders of'a Spray.0ue to Personnel power reactor Error OL or CP 81-09 Degradation of Residual 3/26/81 All holders of a Heat Removal (RHR) power reactor System OL or CP 81-08 Repetitive Failure 3/20/81 All holders of a of Limitorque SM8-4 power reactor Motor-To-Shaft OL or CP 81-07 Potential Problems 3/16/81 All holders of a with Water-Soluble power reactor OL Purge Dam Materials or CP Used During Inert Gas Welding 81-06 Failure of ITE Model 3/11/81 All holders of a 600 Circuit Breaker power reactor 81-05 Degraded DC System 3/13/81 All holders of at Palisades a power reactor OL or CP 81-04 Cracking in Main 2/27/81 All holders of a Steam Lines power reactor OL or CP 81-03 Checklist for 2/2/81 All holders of a Licensees Making power reactor Notifi' cations of OL Significant Events in Accordance with
-10 CFR 50.72 81-02 Transportation of 1/23/81 All holders of a Radiography Devices radiography license j
_