ML19246B667
| ML19246B667 | |
| Person / Time | |
|---|---|
| Site: | Catawba, Perkins, Cherokee  |
| Issue date: | 06/27/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dail L DUKE POWER CO. |
| References | |
| NUDOCS 7907180288 | |
| Download: ML19246B667 (2) | |
Text
J g *" "' G oq'o, UNITED STATES d
NUCLEAR REGULATORY COMMISSION k
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AT L ANT A. GE ORGI A 30303 In Reply _ Refer To:
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$0-413.__5.0-4 b 50-488, 50-489 50-490, 50-491 50-492, 50-493 Duke Power Company Attn:
L. C. Dail, Vice President Design Engineering P. O. Box 33189 Charlotte, So th Carolina 28242 Gentleten:
The enclosed Circular 79-11, is forwarded to you for information.
50 vritten response to this Circular is required.
If you require additional inforcatier regarding this subject, please contact this office.
Sincerely,
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Jares P. O'Reilly Director
Enclosures:
1.
IE Circular No. 79-11 2.
List of IE Circulars Issued in the Last 12 Months
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&lN271470 Duke Power Company ec w/ encl:
D. G. Beam, Project Manager Post Office Box 223 Clover, South Carolina 29710 J. T. Moore, Project Manager Post Office Bcx 422 Caffney, South Carolina 29340
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9 UNITED STATES NUCLEAR REGULATORY COMMISSIJN OFFICE OF INSPECTION AND E"' t' CEMENT WASHINGTON, D.C.
20335 June 27, 1979 IE Circular No. 79-11 DESIGN / CONSTRUCTION INTERFACE PROBLEM Description of Circumstances:
Apparent inadequate communication between nuclear steam supply 8ystem (SSSS),
architect / engineer (A/E) and constructors have resulted in several cases where reactor vessels or the suppo-ts have been misoriented.
The misorienta-tion problems appear to occur at sites uhere 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 s e rvic e.
In 1977 the Southern California Edison Company reported a reactor vessel misorientation at San Onofre 'Jnit 2.
Combustion Engineering was the NSSS supplier and Bechtel provided the A/E service.
In 1979 the Texas Utilities Generating Company reported a reactor vessel support system misorientation at Cor :he Peak Unit 2.
Westinghouse supplied the NSSS, Gibbs and Hill was the pl at engineer and Brown and Root was the constructor.
Even ' hough there appears to be minimal safety implications associated with the particular misorientation problems mentioned, repetition of the same t ype of errors suggest s 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 _ollowing reasons:
If the interface control system between the NSSS/AE/ Construction is marginal or ineffective as evidenced by the misorientation of reactor vessels 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 obx*ious as a misoriented reactor vessel This t ype of error car. and has resulted in hardware modifications and could cause functional and/or structural changes that affect design and operating paramecers.
In t ranslating, NSSS design informat ion into site con st ruction document s,
the A/E may rake changes to f at ilitate construction of the balance of plant.
There translutions may also introduce errors which may not be
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June 27, 1979 IE Circular No. 79-11 Page 2 of 2 The organization recognized as errors by the A/E's review system.
be made aware of responsible for function and/or structural design must changes af f ecting design and operating parameters so that proper evalua-tion is performed.
It is recognized that there are effective field construction inspection systems, deficiency reporting systems and es-built check systems to uncover and correct for deviations frc= design.
However, these are reactive t ype systems that address the prob 1 cms after the errors 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 sufficient ch2cks 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 The 10 CFR 50, Appendix 5 changes that affect design and operating parameters.
requirement that addresses this concern is contained in Criteria III which states in part:
" Measures shall be established for the identification ano control of design interf aces and for coordination among participating decign organizations. These measures shall include the establishment of procedures among participating design organizations for the review, approval, release, listribution, and revision of documents involving design interfaces."
Preventive action at the design level is necessary to minimize the pessibility of the appropriate parties not beir g aware of A/F and construction relatec design changes and to prevent errors from occurring.
An appropriate preventive action would be to have the NSSS review A/E drawings tha; show the locatien, orientation, clearance, etc., for equipment that the NSSS has function:1 and/or structural design responsibility All holders of const ruction permits should be aware of the potential problems caused by inadequate communication betwcen the design organization and the construction organizat ion and should take appropriate action to assure them-selves that adequate interface controls are established and implemented.
No.ritten response to this circular is required.
If you require additional in f o rma t ion regarding t his rat t e r, contact the Director of the appropriate NRC Regional Office.
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F Enclosure IE Circular No. 79-11 Page 1 of 2 June 27, 1979 1.ISTING OF IE CIRCULARS ISS"ED IN
!>.ST TVELVE MONTHS Date Issued To Circular Subject of Issue No.
78-12 HPCI Turbine Control 6/30/78 All Holders of BWR OLs or cps Valve Lift Rod Bending for plants with HPC: Terry Turbine 78-13 Inoperability of Multiple 7/10/78 All Holders of Eeactor OLs and cps Service Water Pumps except for plants located in: AL, AK, CA, FL, GA, LA, MS, SC 78-14 HPCI Turbine Reversing 7/12/78 All Holders of BWR OLs or cps for Chamber Hold Down Bolting p1'ints with a HPCI Terry Turbine excepting Duane Arnold and Monticello 78-13 Checkvalves Fail to 7/20/78 All Holders of Reactor OLs or cps C l o.:.c In Vertical Positi n 78-16 lim; t orque Valve 7/26/78 All Holder s of Reactor OLs or etictors cts 78-17 Inadequate Guard Training /
10/13/78 All Holders of Oualification and Falsified and applicants for Reactor OLs Training Records 78-18 UL Fire Tert 11/6/78 All Holders of Reactor OLs or cps 78-19 Manual Override (Bypass) 12/28/78 All Holders of cps of Safety Actuaticn Signals
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e IE Circular No. 79-11 Enclosure June 27, 1979 Page 2 of 3 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE MONTHS Circular Subj ec t Date of Issued to No.
Issue 79-01 Administration of 1/12/79 All Holders of Unauthorized Byproduct Licensees except Material to Humans Teletherapy Medical Licensees and each Rad i opha rma c eu t i c al Suppliers 79-02 Failure of 120 Volt Vital 2/16/79 All Holders of AC Power Supplies Reactor OLs and cps 79-03 Inadequate Guard Training-2/23/79 All Holders of Qualification and Falsified and applicants i.aining Records for Special Nuclear Material Licenses in Safeguards Group I 79-04 Loose Locking Nut On 3/16/79 All Holders of Limitorque Valve Reactor OLs or cps Operators 79-05 Moist ure Leakage In 3/20/79 All Holders of Stranded Wire Condu-tors Reactor OLs or cts 70-06 Failure te Use Syringe 4/19/79 All lblders of and Battle Shields in Medical Licensees Nuclear Medicine except teletheraps licensees 79-07 Unexpected Speed Increase 5/2/79 All Holders of of Reactor Recirculation BWR OL's or CP's MC Set Resulted in Reactor Power Increase 79-08 Attempted Extortion - Low 5/18/79 All Fuel Facilities Enric hed Uranium Licensed by NRC 79-09 Occurrences of Split or 6/22/79 All Materials Punctured Regulator Diaphragus Priority I, Fuel In Certain Self Contained Cycle and Operat ing Breathing Apparatus Reactor Licensees D ?) I
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d Enclosure IE Circular No. 79-11 Page 3 of 3 June 27, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE MONDIS Date of Issued to Circular Subject Issued No.
79-10 Pipefittings Maaufactured 6/26/79 All Power Reactor Licensees with a from Unacceptable Material CP and/or OL 7 i: O
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