ML19209A466
| ML19209A466 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim, Sterling |
| Issue date: | 09/26/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Andognini G BOSTON EDISON CO. |
| References | |
| NUDOCS 7910040088 | |
| Download: ML19209A466 (4) | |
Text
Th p nea ug y $ c g);y@,,p, UNITED STATES y
NUCLEAR REGULATORY COMMISSION 5 ?',b' % '"df '. C REGION l o,
631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406
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61979 Docket No. 50-293 Boston Edison Company M/C Nuclear ATTN:
M,. G. Carl Andognini, Manager Nuclear Operations Denartment 800 Boylston Street Boston, Massachusetts 02199 Gentlemen:
The enclosed Information Notice provides information with regard to failures of lube oil coolers for emergency diesel generators.
Sincerely,
_ m h Ws Boyce H. Grier Director
Enclosures:
1.
IE Information Notice 79-23 2.
List of IE Information Notices Issued in the Last Six Months cc w/encls:
P. J. McGuire, Pilgrim Station Manager A. Z. Roisman, Natural Resources Defense Council 1n00 7 1 ')
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7910040
ENCLOSURE 1 Accession No:
7908220121 SSINS:
6870 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Information Notice No. 79-23 Date:
September 26, 1979 Page 1 of 1 EMERGENCY DIESEL GENERATOR LUBE OIL COOLERS Within a two week time span (August 27 to Septunber 11, 1979), the tube sheets failed in the Arkansas Nuclear 0. (AN0) Unit 1 lube oil coolers for hoth of the Unit 1 Emergency Diesel Generators.
The introduction of water into the diesel lube oil system resulted in trips of both diesels during surveillance testing.
The diesels were not considered capable of sustained operation.
Investigation by the licensee has indicated cracks around the outer periphery of the tube sheets.
The exact failure mode has not been assessed; however, the licensee has replaced the Emergency Diesel lube oil coolers for both diesels with a cooler of different design.
The original lube oil coolers had tube sheets which were one eighth (1/8) inch in thickness and the tubes were soldered in place.
Epoxy was also used as a sealer on the tube (water side) of the lube oil cooler.
The new coolers have one-half (1/2) inch tube sneets and the tubes are rolled.
The ANO, Unit 1 Emergency Diesel Generators were purchased in 1970 and were manufactured by the Electromotive Division of General Motors Corporation.
The lube oil coolers (Model Number D-191700) were manufactured by Young Radiator Corporation.
This information is provided as an early notification of a possible significant matter.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
1097
?43
ENCLOSURE 2 IE Information Notice No. 79-23 Date:
September 26, 1979 Page 1 of 2 LISTING 0F IE INFORMATION NOTICES ISSUED IN THE LAST SIX MONTHS Information Subject Date Issued to Notice No.
Issued 79-07 Rupture of Radwaste Tanks 3/26/79 All power reactor facilities with an OL or CP 79-08 Interconnection of 3/28/79 All power reactor Contaminated Systems with facilities with an Service Air Systems Used OL and Pu Processing As the Source of Breathing fuel facilities Air 79-09 Spill of Radioactivity 3/30/79 All power reactor Contaminated Resin facilities with an OL 79-10 Nonconforming Pipe 4/16/79 All power reactor Support Struts facilities with a CP 79-11 Lower Reactor Vessel Head 5/7/79 All power reactor Insulation Support Problem facilities with an OL or CP 79-12 Attempted Damage to New 5/11/79 All Fuel Facilities, Fuel Assemblies Research Reactors, and Power Reactors with an OL or CP 79-13 Indication of Low Water 5/29/79 All power reactor Level in the Oyster facilities with an Creek Reactor OL or CP 79-14 Safety Classification of 6/11/79 All applicants for, Electrical Cable Support and holders of a Systems power reactor CP 1089 '44
IE Information Notice No. 79-23 Date:
September 26, 1979 Page 2 of 2 LISTI.Nb 0F IE INFORMATION NOTICES ISSUED IN 1979 Information Subject Date Issued to Notice No.
Issued 79-15 Deficient Procedures 6/7/79 All power reactor facilities with an OL or CP 79-16 Nuclear Incident at 6/22/79 All research and Three Mile Island test reactors with an OL 79-17 Source Holder Assembly 6/20/79 All holders of reactor Damage from Misfit Between OLs and cps Assembly and Reactor Upper Grid Plate 79-18 Skylab Reentry 7/5/79 All helders of reactor OLs 79-19 Pipe Cracks in Stagnant 7/17/79 All power reactor Borated Water Systems at facilities with an PWR Plants OL or CP 79-20 NRC Enforcement Policy -
8/14/79 All Holders of Reactor NRC Licensed Individuals OLs and cps and Production Licensees with Licensed Operators 79-20 Same Title as 79-20 9/7/79 Same as 79-20 (Revision No. 1) 79-21 Transportation and Com-9/7/79 All power and research mercial Burial of Radio-reactors with OLs active Material 79-22 Qualification of Control 9/14/79 f.11 power reactor faci-Systems cilities with an OL or CP 1039 '45
GENER AL h ELECTRIC NUCLEAR ENERGY PRODUCTS DIVISION WILVINGTON MANUFACTURING C EP AR T*.t ENT CASTLE HAYNE ACAD. P. O. BOX 780. WILVINGTON, N. C. 28401. t919) 343 5000 k
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August 30, 1979 i
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01 SEP 719ZSh @
Secretary of the Commission U.S. Nuclear Regulatory Commission zg g Washington, D.
C.
20555 5
saem i
O' Attention:
Docketing and Service Branch
Reference:
Federal Register Volume 44, Number 138, July 17, 1979, Nuclear Regulatory Commission, " Safeguards on Nuclear Material; Implementation of U.S./IAEA Agreement" Gentlemen:
General Electric's Wilmington Manufacturing Department has reviewed the referenced proposed rule and offers the following comments:
1)
Paragraph 7 5. 3.Exe: tptions,
... consistent with the Agreement."
This paragraph should be modified to read:
e
"... consistent with the objectives of the Agreement."
This is necessary to ensure clear understanding that licensees are at liberty to utilize the best available methods and new technology to meet international cojectives.
The Agreement and regulations are written based on current and past knowledge and, in certain instances, do not specifically provide for advanced techniques.
2)
Paragraph 75. ll(a) (4),
"A Description of the Existing and Proposed Procedures at the Installation for Nuclear Material Accounting and Control... "
This paragraph should be modified to read:
e "A Description of the Systems at the Installation..."
A " description of procedures" is really the specification for the system which the procedures implement.
Therefore, it is more appropriate to require that a description of the systems be submitted than to require the more nebulous
" description of procedures".
7910040 0794 -
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1039 '46
GENER AL h ELECTRIC Page 2 2)
Continued The mechanism is already in place, both in proposed 10 CFR 75. ll(b) and in existing 10 CFR 70. 32 (c), for the IAEA and the NRC to be kept informed concerning changes in the safeguards system; therefore, advance notice of " proposed" procedures is unnecessary.
Also, " proposed procedures" (or proposed systems) will be difficult to describe ahead of their implementation, without risking that the submittal will be useless since between proposal and implementation many changes are sometimes made.
In preparation of the guidance for licensees associated with preparation of compliance plans for this new 10 CFR 75, the NRC should assure that the description referred to above need only be concise and definitely need not include a requirement for the procedures themselves to be submitted.
3)
Paragraph 75. ll(b) (1),
"...with respect to a modification or a change which will necessitate'a change in a license condition or technical specification or which will decrease the effectiveness of the material accounting and control procedures at least 70 days before the modification or change is scheduled to be ccmpleted."
e This paragraph should be modified to read:
... control procedures prior to the completion of the modification or change sufficiently in advance for the safeguards procedures to be adjusted when necessary."
This change is in accord with the Agreement.
Much of the information required herein is already required in 10 CFR 70; however, there is no timing requirement for submittal of the changes which require prior NRC approval.
We attempt to provide such requests as early as pcssible, but there are times when we mi.st operate on a short cycle.
4)
Paragraph 75. ll(b) (2),
...with respect to any other change or modification, at the time the first inventory change report is submitted after the modification or change is completed."
1089 '47
G EN ER AL (h ELECTRIC Page 3 4)
Continued This paragraph should be modified to read:
e
... first inventory change report is submitted or within six months if inventory change reporting is not affected."
10 CFR 70 contains a comparable requirement specifying "within six months".
The requirement to submit such other modifications or changes, at the next time a Form 741 i_
completed, puts an unwarranted burden on the licensee.
This. reporting requirement should be made compatible with that presently in 10 CFR 70.
All changes may not effect inventory change reporting.
Therefore, consideration must be included for a reduced urgency in reporting changes which do not effect inventory change reports.
10 CFR 70 appears to be a good guide.
5)
Paragraph 75.12 (b) (1),
"A licensee may request that information of particular sensitivity, which it customarily holds in confidence, not be transferred physically do the agency... "
e This paragraph should be modified to read:
"In addition to Section 75. ll(f), the licensee may request..."
Note:
Add paragraph (f) to Section 75.11 as follows:
"The licensee may specify in the Facility Attachment those types or categories of information which shall be considered proprietary and, therefore, not provided to the agency, provided that justification for such specifications fulfill the conditions of Section 75.12. "
These and other statements under paragraph 75.12 related to licensee-identified sensitive information, possibly could be covered under the Facility Attachment.
Otherwise, the interest of the licensee may not be properly safeguarded as indicated; for example, under paragraph 75.12 (d), which states that a request made to the NRC under paragraph 2.790 (d) of 10 CFR will not be treated as a request under 10 CFR 75 unless the application makes specific reference to this action (etc.).
This sitation could lead to inadvertent disclosure of information sensitive to a licensee.
Therefore, it might be appropriate to additionally cover such matters under the Facility Attachment.
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