ML19246B650
| ML19246B650 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/27/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Koester G KANSAS GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7907180257 | |
| Download: ML19246B650 (1) | |
Text
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UNITED STATES gqd u,MN(//[ g NUCLEAR REGULATORY COMMISSION y h, ) _,
g REGION IV
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AR LING To.J, TE X AS 76012 June 27, 1979 In Reply Refer To:
RIV Docket No.
STN 50-482/IE Circular No. 79-11 Kansas Gas & Electric Co.
Attn:
Mr. Glenn L. Koester
cc President-Operations ce Box 208 Post 1.
..nsas 67201 W1..
Gentlemen:
The enclosed Circular 79-11, is forwarded to you for information.
No written response to this Circular is required.
If you require additional information regarding this subject, please contact this office.
Sincerely, 7's r
a.
. Seyfy Director
Enclosures:
1.
IE Circular No. 79-11 2.
List of IE Circulars Issued in the Last 12 Months cc: w/ enclosures Messrs. Nicholas A. Petrick, SNUPPS D. T. McPhee, Kansas City Power and Light Company Gerald Charnoff, Shaw, Pittman, Potts & Trowbridge E. W. Creel, Kansas Gas and Electric Company 7907180674 337 'O/
UNITED STATES NUCLEAR REGULATORY C0&lISSION OFFICE OF INSPECTION AND ENFORCEMEh"r WASHINGTON, D.C.
20555 IE Circular No. 79-11 Date: June 27, 1979 Page 1 of 2 DESIGN / CONSTRUCTION INTERFACE PROBLEM Description of Circumstences:
Apparent inadequate communication between nuclear steam supply system (NSSS),
architect / engineer (A/E) and canstructors have resulted in several cases where reactor vessels or the supports have been misoriented. The misorienta-tion problems appear to occur at sites where dual reactor units are being constructed and one primary system layout is a mirror image of the other.
In 1975 TVA reported a misorientation problem with the Sequoyah Unit 2 reactor vessel.
Westinghouse was the NSSS supplier and TVA provided their own A/E service.
In 1977 the Southern California Edison Company reported a reactor vessel mirorientation at San Onofre Unit 2.
Combustion Engineering was the NSSS
,upplier and Bechtel.provided the A/E service.
In 1979 the Texas Utilities Generating Company reported a reactor vessel support system misorientation at Comanche Peak Unit 2.
Westinghouse supplied the NSSS, Gibbs and Hill was the plant engineer and Brown and Root was the constructor.
Even though there appears to be minimal safety implications associated with the particular misorientation problems mentioned, repetition of the same type of errora suggests breakdowns in the design / construction interface relation-ships that could in turn lead to more significant safety problems.
Corrective preventive action is recommended for the following reasons:
If the interface control system between the NSSS/AE/ Construction is maio:nal or ineffective as evidenced by the misorientation of reactor vos vls and their supports, it is possible that other safety related equipment may also be misoriented and/or mislocated.
In some cases the errors may not be as obvious as a misoriented reactor vessel.
This type of error can and has resulted in hardware modifications and could cause functional and/or structural changes that affect design and operating parameters.
In translating NSSS design information into site construction documents, the A/E may make changes to facilitate construction of the balaace of plant.
These translations may also introduce errors which may not be 33l
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IE Circular No. 79-11 June 27, 1979 Page 2 of 2 recognized as errors by the A/E's review system. The organization responsible for function and/or structural design must be made aware of changes affecting design and operating parameters so that proper evalua-tion is performed.
It is recognized that there are effective field construction in.pection systems, deficiency reporting systems and as-built check systems to uncover and correct for deviations from design.
However, these are reactive type systems that address the problems after the errars occur and that rely on detection of errors and design deviations in the construction phase. The detection of certain other errors and design deviations may only be recogniz-able at the design level.
The NRC's concern is that in some instances sufficiant checks at the design level are not being performed to preclude design errors discovered at the con-struction site and that the designer may not be aware of other design related changes that affect design and operating parameters.
The 10 CFR 50, Appendix B requirement that addresses this concern is contained in Criteria III which states in part:
" Measures shall be established for the identification and control of design interfaces and for coordination among participating design organizations.,These measures shall include the establishment of procedures among participating design organizations for the review, approval, release, distribution, and revision of documents involving design interfaces."
Preventive action at the design level is necessary to minimize the possibility of the appropriate parties not being aware of A/E and construction related design changes and to prevent errors from occurring. An appropriate preventive action would be to have the NSSS review A/E drawings that show the location, orientation, clearance, etc., for equipment that the NSSS has functional and/or structural design responsibility.
All holders of coastruction permits should be aware of the potential problems caused by inadequate communication '_etween the design organization and the ccnstruction organization and should take appropriate action to assure them-selves that adequate interface controls are established and implemented.
No written response to this circular is required.
If you require additional information regarding this matter, contact the Director of the appropriate NRC Regional Office.
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IE Circular No. 79-11 June 27, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE MONTHS 78-12 HPCI Turbine Control 6/30/78 All Holders of Valve Lift Rod BWR Operating Bending Licenses (OL) or Construction Permits (CP) with Similar HPCI Design 78-13 Inoperability of 7/10/78 All Holders of Service Water Pumps Reactor Operating Licenses (OL) or Construction Permits (CP) except for plants located in:
AL, AK, CA, FL, GA, LA, MS, SC 78-14 HPCI Turbine Reversing 7/12/78 All Holders of Chamber Hold Down BWR Operating Bolting Licenses (OL) or Construction Permits (CP) for plants with a HPCI Terry Turbine excepting Duane Arnold and Monticello 78-15 Tilting Di.:c Check 7/20/78 All Holders of Valves Fail to Close Reactor Operating With Gravity in Licenses (OL) or Vertical Position Construction Permits (CP)
Enclosure Page 1 of 3
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IE Circular No. 79-11 June 27, 1979 78-16 Limitorque Valve 7/26/78 All Holders of Actuators Reactor Operating Licenses (OL) or Construction Permits (CP) 78-17 Inadequate Guard 10/13/78 All Holders of Training /Qualifica-and applicants tion and Falsified for Reactor Training Records Operating Licenses (OL) 78-18 Underwriters 11/6/78 All Holders of Laboratory Fire Reactor Operating Test Licenses (OL) or Construction Permits (CP) 78-19 Manual Override 12
/78 All Holders of (Bypass) of Safety Reactor Construction Actuation 9ignals Pc cmits (CP) 79-01 Administration of 1/12/79 All Medical Unauthorized Byproduct Licensees except Material to Humans Teletherapy Medical Licensees and each Radiopharmaceutical Suppliers 79-02 Failure of 120 Volt 1/16/79 All Holders of Vital AC Power Reacter Operating Supplies License (OL) and Construction Permits (CP) 79-03 Inadequate Guard 2/23/79 All Holders of Training - Qualifica-and applicants tion and Falsified for Special Nuclear Training Records Material Licenses in Safegui.rds Group I 79-04 Loose Locking Nut 3/16/79 All Holdars of On Limitorque Valve Reactor Operating Operators License (GL) or Construction Pe rmits (CP)
Enclosure Page 2 of 3
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IE Circular No. 79-11 June 27, 1979 79-05 Moisture Leakage in 3/20/79 All Holders of Stranded Wire Conductors Reactor Operating License (OL) or Construction Permits (CP) 79-06 Failure to Use Syringe 4/19/79 All Holders of and Battle Shields in Medical Licensees Nuclear Medicine except teletherapy licensees 79-07 Unexpected Speed Increase 5/2/79 All Holder s of BWR of Reactor Recirculatien Operating Licenses (OLs)
MG Set Resulted in Reactor or Const uction Power Increase Permits (cps) 79-08 Attempted Extortion - Low 5/18/79 All Fuel Facilities and Enriched Uranium Reactors Licensed by NRC 79-J9 Occurrences of Split or 6/22/79 All Materials Punctured Regulator Priority I, Fuel Diaphragms In Certain Cycle and Operating Self Contained Breathing Reactor Licenses (OL)
Apparatus 79-10 Pipefittings Manufactured 6/26/79 All Power Reactor from Unacceptable Material Licensees with a Construction Permit and/or Operating License (0L)
Enclosure Page 3 of 3 a c.
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