ML19225A091
| ML19225A091 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/27/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 7907180281 | |
| Download: ML19225A091 (2) | |
Text
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/g s, nE r.,g'o UNITED STATES E
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NUCLE AR REGUL ATORY COMMISSION f
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5 RE GION 11
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101 M An tE T T A ST, N W, SulT E '100 c;, **
AT L ANT A. GE ORGI A 30303
_f E g In Reply Refer To:
g g 7 jg7g RII:JPO 50-400, 50-401 50-402, 50-403 Carolina Power and Light Cocpany ATTN:
J. A. Jones Executive Vice President and Chief Operating Officer 411 Fayetteville Street Raleigh, North Carolina 27602 Centieren:
The enclosed Circular 79-11, is forwarded to you for infor.ation.
No writter response to this Circular is tequired.
If you require additiona'. information regarding this subject, please contact this office.
5incerely, JamesP.O'ReilI)
Director
Enclosures:
1.
IE Circ lar No. 79-11 2.
List of IE Circularr.
Issued in the Last 12 Mont!<
2 7907180261 7qq 1
J
Jutt 2 7 P
Carolina Power and 2
light Co:::pany ce v/enti:
R. Farsons, Site Manager Post Office Box 101 27562 New Bill, North Carolina 4
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I UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 June 17, 1979 IE Circular No. 79-11 DESIGN / CONSTRUCTION INTERFACE PROBLEM Description of Circumstances:
Apparent inadequate communication between nuclear steam supply system (SSSS).
architect / engineer (A/E) and constructors have resulted in several cases where reactor vessels or the supports have been misoriented.
The misorienta-tien problems appear to occur at sites where dual reactor units are being constructed and one primary system leyout is a mirror image of the other.
2 reactor In 1975 TVA reported a miserientation problem with the Sequoyah Unit Westinghouse was the NSSS supplier and TVA provided their own A/E vessel.
se rvic e.
1977 the Southern California Edison Company reported a reactor vessel In miserientation at San Onof re Unit 2.
Combustion Engineering was the NSSS supplier and Bechtel provided the A/E service.
1979 the Texas Utilities Generating Co=pany 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 appeat s to be minimal Jafety implications associated with Even the particular misorientation problems mentioned, repetition of the same type of errors suggest s breakdowns in the design / construction interf ace relation-ship s t ha t could in turn lead to more signif. cant safety problems.
Corrective preventive action is recommended for the following reasors:
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 also be misoriented and/or mislocated.
In some cases the equipment cm,
errors may not be as obvious as a miscriented reac;or 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 in f o rma t ion i..to site construction documents, the A/E may make changes to f acilitate construction of the balance of plant.
These translations may also introduce errors which may not taO ] E I' 7906',100176
9 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 as-built check systems to uncove-and correct for deviations from design. However, these are reactive type systems that address t'.e problems after the errors occur and that rely on The detection of errors and design deviations in the construction phase. 5 be recogniz-detection of certain other errors and design deviations may on1 able at the design level. The NRC's concern is that in some instances sufficient checks at the design level are not being performed to preclude design errors discovered at the con-be aware of other design related struction site and that the designer may not The 10 CFR 50, Append iz B 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 and control of design interfaces and for coordination among participating design organiz a t ion s. These measures shall include the establishment of
- review, procedures among participating design organizations for the approval, release, d ist r ibut ion, and revision of documents invc1ving 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 fron occarring. An appropriate preventive action would be to have the NSSS review A/E drawings that show the locatien, orientation, clearance, etc., for equipment that the NSSS has functional and/or structural design responsibility. All holders of construction permits should be aware of the petential problems caused by inadequate communication between the design organization and the them-construction organization and should take appropriate action to assure selves that adequate interface controls are established and leplemented. No written response to this circular is required. If you require additiena: in f o rma t ion regarding this matter, contact the Director ef the appropriate NRC Regional Office. ~ , 9 O~ )Li
v Enclosure IE Circular No. 79-11 Page 1 of 2 June 27, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST TVELVE MONTHS Date Issued To Circular Subject of Issue No. 78-12 HPCI Turbine Control 6/30/78 All Holders of BWR GLs or cps Valve Lift Rod Bending for plants with HPCI Terry Turbine 78-13 Inor-ability of Multiple 7/10/78 All Holders of Reactor OLs and cps
- Ser, e Water Pumps except for plants located in: AL, AE, 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 plants with a HPCI Terry Turbine e2cepting Duane Arnold and Montic el' c 78-15 Checkvalves Fail to 7/20/78 All Holders of Reactor OLs or cps Close In Vertical Position 78-15 Limitorque Valve 7/26/78 All Holders of Reacter OLs or Actuators cps 78-17 Inadequate Guard Training /
10/13/78 All 'M ders of and applicants Qualification and Falsified for Rea-tor OLs Training Records 11/6'78 All H.ldeis c 78-16 UL Fire Test Reactor OLS er 78-19 Manual override (Bypass) 12/28'78 All Holders er cps of Safety Actuation Signals ~{ C) )b
IE Circular No. 79-11 Enclosure June 27, 1979 Page 2 of 3 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE MONTHS Circular Subject Date of Issued to No. Issue 79-01 Administ ration of 1/12/79 All Holders of Unauthorized Byproduct Licensees except Material to Hunans Teletherapy Medical Licensees and each Radiopharmaceutical 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 Tra?ning-2/23/79 All Holders of Qualification and Falsified and applicants T 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 Moisture Leakage 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 Shields in Medical Licensees Nuclear Medicine except teletherarv ^ 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 - 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 Diaphragms Priority I, Fuel In Certain Self Contained Cycle and Operating Breathing Apparatus Reactor Licensees } } #) D
Enclosure IE Circular No. 79-li Page 3 of 3 June 27, 1979 LISTING OF IE CIRCULARS ISSUED IN LAST TWELVE MONTHS Date of Issued to Circular Subject Issued No. 79-10 Pipefittings Manufactured c/26/79 All Power Reactor Licensees with a from Unacceptable Material CP and/or OL -}}