ML19246B674
| ML19246B674 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/27/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Parker W DUKE POWER CO. |
| References | |
| NUDOCS 7907180303 | |
| Download: ML19246B674 (2) | |
Text
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' 'o UNITED STATES h
E' NUCLEAR REGULATORY COMMISSION o,k ' 5 PEGION ll 5 ' Mbf f 101 M ARIE T T A ST, N W, SUIT E 3100 ATL ANT A GEORGI A 30303 5,
_f JUN 2 7 lo7a In Reply Refer To:
RII:JP0 50-369, 50-370 Duke Power Company Attn:
W. O. Parker, Jr.
Vice President, Steam Production P. O. Box 33189 422 South Church Street Charlotte, North Carolina ?8242 Gentlenen:
The enclosed Circular 79-11, is forwarded to you for information. No written response to this Circular is required.
If you require additional inforcation regarding this subject, please contact this office.
Sincerely, JamesP.O'Reilhy Director
Enclosures:
1.
IE Circular No. 79-11 2.
List of IE Circulars Issued in the Last 12 Months 790718 93
JUN 2 71979 v'
2-Duke Power Corgany cc w/ encl:
M. D. McIntosh, Plant Manager Post Office Box 488 Cornelius, North Carolina 28032 J. C. Rogers, Project Manager Post Office Box 33189 Charlotte, North Carolina 28242 339 235
UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 27, 1979 IE Circular No. 79-11 SESIGN/ CONSTRUCTION INTERFACE PROBLEM Description of Circumstances:
Apparent inadequate co=munication between nuclear steam supply system C SSS),
architect / engineer (A/E) and constructors have resulted in several cases where reactor vessels or the supports have been misoriented.
The misorienta-sites where dual reactor units are being tion problems appear to occur at constructed and one primary system layout is a mirror image of the other.
2 reactor In 1975 TVA reported a misorientation problem with the Sequoyah Unit Westinghouse was the NSSS supplier and TVA provided their own A/E vessel.
s e rv ic e.
In 1977 the Southern California Edison Company reported a reactor vessel misorientation at San Onofre Unit 2.
Combustion Engineering was the NSSS supplier and Bechtel provided the A/E service.
1979 the Texas Utilities Generating Company reported a reactor vessel In 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.
though there appears to be minimal safety implications associated with Even the particular misorientation problems mentioned, repetition of the same t ype interface relatien-of errors suggest s breakdowns in the design / construction ships that could in turn lead to more significant sa fety problems.
Corrective preventive action is recommended for the f 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. heir supports, it is possible that other safety related equipment may also be misoriented and/or mislocated.
In same cases the errors may not be as obvious as a misoriented reactor vesse:
This type of error can and has resulted in hardware modifications and could cause f unct ional and/or st ructural changes that affect design and operating parameters.
In translating NSSS design in f o rma t t or. into sit e const ruction document s,
the A/E may make changes to facilitate construction of the balance of plant.
These translations may also introduce errors which may not be 339 236 n..
t.
I June 27, 1979 IE Circular No. 79-11 Page 2 of 2 recognized as errors by the A/E's review system.
The organization be made aware of responsible for function and/or structural design mutt changes affecting design and operating parameters so that proper evalua-tion is perf ormed.
It is recognized that there are effective field construction inspection systems, deficiency reporting systems and as-built check systems to uncover and correct for deviations f rom design.
However, these are reactive type systems that address the problems 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 checks at the design the con-level are not being performed to preclude design errors discovered at 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, Appendiz E 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 f or 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 locatter.,
orientation, clearance, etc., for equipment that the NSSS has functional and/or structural design respoisibility.
All holders of construction permits should be aware of the potential problems caused by inadequate com=unication between the design organization and the construction organization and should take appropriate action to assure them-selves that adecuate interface controls are established and implemented.
No wr it t en response to this circular is required.
If you require additiona:
in f o rma t ion regarding this matter, contact the Director of the appropriate NRC Regional Office.
339 237
I Enclosure IE Circular No. 79-11 Page 1 of 2 June 27, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE 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 f or plant s witi.
HPCI Terry Turbine 78-13 Inoperability of Multiple 7/10/78 All Holders of Reactor OLs and cps Service Water Pumps except for plant-located in: AL, AE, CA, FL, GA, LA, MS, SC 78-14 HPCI Turbine Reversing 7/12/78 All Holders of BWR
.l.s or cps for Chamber Hold Down Bolting plants with a HPCI Tert y Turbine excepting Duane Arnold and Monticello 78-15 Checkvalves Fail te 7/20/78 All Holders of Reactor OLs or cps Close In Vertical Position 7/26/78 All Holders of 78-16 Limitorque Valve Reacter OLs er A-tuators cps 78-17 Inadequate Guard Training /
10/13/78 All Holders cf and applicants Qualification and Falsified fer Reacter OLs Training Records 11/6'78 All Holders of 78-16 UL Fire Test Reacter OLs er CFs 78-19 Manual Override (Bypass) 12/28'78 All Holders cf cps of Safety Actuation Signals 339 238
I IE Circular No. 79-11 Enclosure June 27, 1979 Page 2 of 3 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE MONTHS Circular Subj e c t Date of Issued to No.
Issue 79-01 Administ ration of
'/12/79 All Holders of Unauthorized Byprodt et Licensees except Material to Humans Teletherapy Medical Licensees and each Rad iopha rma c eut i c al Suppliers 79-02 Failure of 120 Volt \\ ital 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 Training Lecords for Special Nuclear Material Licenses in Safeguards Group I 79-04 Loose Locking Nut On 3/16/75 All Holders of Limitorque Valve Reactor OLs or cps Operators 79-05 Moisture Lea kag e In 3/20/79 All Holders of Stranded Wire Conductors Reactor OLs or cps 79-06 Failure to Use Syringe 4/19/79 All Holders of and Battle Shielu3 a Medical Licensees Nuclear Medicine except taletherap-licensees 79-07 Unexpected Speed Increase 5/2/79 All Holders of of Reactor Recirculation BWR OL's or CP's MG Set Resulted in Reactor Power Increase 79-08 Attempted Extortion - Lew 5/18/79 All Fuel Facilities Enriched Uranium Licer. sed by NRC 79-09 Occurrences of Split or 6/22/79 All Materials Punctured Regulator Diaphrages Priority I, Fuel In Certain Self Contained Cycle and Operating Breathing Apparatus Reactor Licensees
4 Enclosure IE Circulat No. 79-11 Page 3 of 3 June 27, 19/9 LISTING OF IE CIRCULARS ISSUED IN LAST TEIXE MONTHS Date of Issued to Circular Subject Issued No.
79-10 Pipefittings Manufactured 6/26/79 All Power Reactor Licensees with a from Unacceptable Material CP and/or OL 339 240