ML19332A671
| ML19332A671 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 08/29/1980 |
| From: | Sarsten G UNITED ENGINEERS & CONSTRUCTORS, INC. |
| To: | |
| References | |
| REF-PT21-80-221-002 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8009160645 | |
| Download: ML19332A671 (8) | |
Text
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CGPAW NVE.4 Ga uahd t PART 21 IDENTIFICATION NO. So-tu-oo2.
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IRTE OF ETIER.
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l PRELIMINARY EVALUATION OF THE' ATTACHED REPORT INDICATES LEAD RESPONSIB FOLLOWJP AS SH7dN BELOW:
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30 South 17th Street MLADELMA Post Office Box 8223 Philadelphia. PA 19101 Y'H4h August 29, 1980 Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D. C.
20555 Subj ect:
10CFR21 Report of Situation related to Public Service Company of New Hampshire - Seabrook Project.
Reference:
June 2,1980 letter regarding revised report date.
s Gentlemen:
Attached is our final report on the subject matter in fulfillment of the commitment in the referenced letter. A similar report is being made by the Public Service Company of New Hampshire in accordance with 10CFR50.55(e) commitments.
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Very,,truly your,
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- Vic, esident-Power RHL/GES/be Enclosure copy: Regional Director USNRC - Region I 2
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NAME' AND: ADDRESS '0F THE INDIVIDUAL OR INDIVII}UALS INFORMING THE COMMISSION.
G.-E.
Sarsten, Vice President-Power-
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United. Engineers & Construckors Inc.
30 South 17th Street.
j Philadelphia,;Pa. 19101 IDENTIFICATION OF THE FACILITY, THE ACTIVITY, OR THE BASIC COMPONENT SUPPLIED FOR SUCH FACILITY OR SUCH ACTIVITY WITHIN THE UNITED STATES WHICH FAILS.*IO COMPLY OR CONTAINS A DEFECT.
Seabrook Station of Public Service Company of New Hampshire The design deficiency involved the use of. invalid seismic amplified response spectra (ARS) in' the design of components supported by the containment building annular steel framing.
IDENTIFICATION OF THE FIRM ~ CONSTRUCTING THE FACILITY OR SUPPLYING THE BASIC COMPONENT WHICH~ FAILS 70 COMPLY OR CONTAINS A DEFECT.
United Engineers & Constructors Inc., architect, engineer and construction manager.
NATURE OF THE DEFECT OR FAILURE TO COMPLY AND THE SAFETY HAZARD WHICH IS
' CREATED OR COULD BE CREATED BY SUCH DEFECT 'OR FAILURE TO COMPLY. -
The defect. identified is. the use of incorrect Amplified Response
- Spectra -(ARS) for the design of the subject containment building annular' steel framing. This deviation, if uncorrected, could result in the-failure of components supported by the annular steel framing to perform the intended safety. function during and after an Operating Basis Earthquake (OBE) or Safe ~ Shutdown Earthquak'e (SSE) event.
THE DATE ON WHICH THE INFORMATION F SUCH DEFECT OR FAILURE TO COMPLY WAS
'OBTAINED.
November 5,-1979.
IN THE CASE OF A BASIC COMPONENT.WHICH CONTAINS A DEFECT OR FAILS TO COMPLY, THE. NUMBER AND LOCATION OF ALL SUCH COMPONENTS IN USE AT, SUPPLIED FOR, OR BEING. SUPPLIED FOR ONE OR MORE FACILITIES OR ACTIVITIES SUBJECT TO THE REGULATIONS IN THIS PART.-
.Part 1:
The specific defect identified relative to the subject
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components pertains to the input parameter for the ARS for a unique location in the Plant. As such, the defect is not generic in nature to 'such components (namely,
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piping and other components) which are used in the Plant in both the safety-related and non-aafety related functions in various loca' ions within the subject Seabrod Station, t
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. 3 Part 2:- The ARS input which is the identified defect in this case, however, is furnished as a design input parameter to various
-safety-related systems. structures and components in the Plant with specific relevance to the individual locations.
In this respect, the identified defect pertains to the
" generation and.use of ARS", which is ~a " basic component" in use at other areas of the plant systems, structures and components in the Seabrook Station.
THE CORRECTIVE ACTION WHICH HAS BEEN, IS BEING, OR WILL BE TAKEN: THE NAME OF THE' INDIVIDUAL OR ORGANIZATION RESPONSIBLE FOR THE ACTION: AND THE LENGTH,OF TIME HAS BEEN OR WILL BT TAKEN TO COMPLETE THE ACTION.
An " Interim Report" on this subject was submitted on May 13, 1980.
This was followed by additional written information on June 2, 1980.
The latter also revised the submittal date of the final report-from June 1 to September 1, 1980.
This report gives the final status of the actions committed to'in the Interim Report and also details further corrective action UE&C.is undertaking as a result of_the design deficiency.
The following Corrective Action commitments are quoted from the Interim Report:
Corrective Action 1.
UE&C is conducting a short-term audit of selected seismic Category I systems and co=ponents to assure use of correct Amplified Response Spectra in their seismic, design.
2.
Containment building annular steel frame is being redesigned to increase'its rigidity.- The intent is to reduce the values of the ARS imposed on the piping systems and other components supported by the annular steel frame.
- 3. ~A " HOLD" has been placed on the design and analysis of piping systems located in the containment annulus.
- 4. - UE&C will conduct a longer term audit of all seismic Category I systems and components to assure use of correct ARS in their seismic design.
o 5.
When the redesign of the annular steel framing is complete, a seismic analysis of it_ will be performed, generating new ARS at significant individual points.
-6.
Existing analyses of Safety Class 2 and 3 piping running in the containment annulus will be reviewed dgainst ARS generated in #5 above. Where necessary, piping will be reanalyzed to assure con-formance with applicable Code and regulatory requirements.
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UE&C is currently reviewing the seismic design requirements of all other components supported by the containment annular steel frame.
They are the following:
a.
Containment Recirculating Air Units:
These would be used for' post-LOCA hydrogen mixing and are Safety Class 3.
b.
Containment Cooling Units:
These are non-safety-related, non-seismic Category I.
- However, they will be seismically designed since they are located in a seismic Category I building.
Hydrogen Recombiners:
c.
There'are two thermal-type recombiners mounted on the annular steel frame. They are safety Class 3, seismic Category I.
d.
Cable Trays and their Support Systems:
Tray supports are seismic Category I.
Heating, Ventilating and Air Conditioning Ductwork Systems:
e.
These are a mixture of Category I and non-Category I systems.
f.
Air Compressors:
Two small'non-Category I units for instrumentation and control supply.
8.
Existing UE&C procedures involving seismic design, especially those treating Amplified Response Spectra, are under review to determine
~the need for revisions or additions which will upgrade,them in areas
~f selection, use a'nd review of ARS.
o 9.
Quality Assurance training ses'sions, in addition to those on the regular schedule, are planned on.the subject of ARS treatment for all UE&C personnel who interf ace with ARS.
C[rrectiveAction The following is the status of the corrective action commitments as listed above:
1.
The short term audit (UESC internal audit number NH-314) of selected seismic Category I systems and co=ponents has been completed.
Project -engineering has responded to all findings and the responses have-been accepted by the auditors. Several corrective actions 4
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_ 5 remain to be verified; however, no find 1ngs require corrective action in the form'of structura,1 modifications or major modifications to piping and pipe supports.
2.
Redesign of containment annular steel has been completed. All-original design drawings in this area have been voided and design calculations redone.
3.
The " HOLD"'s placed on design and analysis of affected piping systems have been removed since updated amplified response spectra for the containment building annular structural steel are now available. The seismic analyses of these piping systems are beinh reviewed to determine the effect of the revised ARS.
It is anti-cipated that no changes will be required in piping configurations; however, certain lines will require additional-supports.
4.
The longer term audit (UE&C internal audits numbers NH-350 and NH-351) has been completed. Preliminary responses have been prepared for all findings on components.
It is anticipated that corrective action will not require physical change to any component.
Findings on piping systems have been reviewed.
Based on this review and on the results of the "short, tens" audit describeo above, it is anticipated that corrective action will not require modifications to piping configurations..
Detailed corrective action and its verification will be determined during the Seismic Verification Prog. ram discussed below.
S, The seismic analysis of the redesigned annular steel framing has -
p been completed.
Generation of the new amplified response spectra for the steel frame has been completed.
- 6. & 7.
ReviewofanalhsisandseismicdesignrequirementsofSafety
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Class 2 and 3 piping and other components supported by the annular steel frame is underway.
Th'is review is in conjunction with the Seismic Verification Program discussed below.
8.
A new Se:' 'cok Administrative Procedure No. 36 (AP-36), " Control of Seismic Design", has been prepared and issued to all UE&C personnel' involved in this aspect of the Seabrook plant design.
9.
An initial training session on the use of AP-36 for all UE&C personnel who interface with. ARS*used on the Seabrook project
.was held on June 4, 1980.
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- y Seismic Verification Program-The UE&C internal audits- (NH-314, NH-350 and NH-351) cited above showed that there are no other areas in the plant where the seismic analysis of a-group of local systems and components was based on seismic amplified response spectra of a different structure, as was the case of the piping and components supported by the containment annular steel. However, UE&C-
'has undertaken a verification program (" Seismic Verification. Program") to insure that the seisade design and analyses for all seismic Category I systems and components is based on input derived from the final design of those systems and components.
In addition, the seismic analyses for all Category I systems are being reviewed for correctness. Major design and analytical input being reviewed includes but is not limited to the following:
a.
Location of pipe and component supports.
b.
Type and-function of pipe and component supports.
d.
Seismic amplified response spectra at all pipe and component support points.
The program will not address the analysis of Safety Class I components and piping for which the NSSS supplier is responsible. However, it has been confirmed that the UE&C generated amplified response spectra for the containment structure used by Westinghouse in their analysis are correct and up-to-date.
Due to the nature of the verification program, the program cannot be
. concluded without the final,.as-built plant data.
The verification program which is currently in progress would systematically identify the input ARS design parameters that have been used in the design for all safety related systens and components such that, should a defect be uncovered as a result of the pregram, corrective actions can be sicultaneously initiated. The corre;tive actions, in general would consist of stiffening of a floor, a colu=n, or of a beam, or reanalysis to exacine design margins, or relocation of components as necessary.
The completion of this verification program and corrective actions resulting vill constitute final cidsecut of corrective action items 4,
.6, and 7 noted above.
Name of the Organization R'esponsible for the Corrective Action:
Project Engineering - Seabrook Project JP United Engineers & Constructors Inc.
30 South 17th Street Philadelphia, Pa.
19101 The Length of Time that will'be Taken to Complete the Action:
Corrective action is scheduled to be complete prior to fuel loading.
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_, 1 ANY ADVICE RELATED Td THE DEFECT OR FAILURE TO COMPLY ABOUI THE FACILITY, ACTIVITY, OR BASIC COMPONENT THAT HAS BEEN, IS BEING, OR WILL BE GIVEN TO PURCHASERS OR LICENSEES.
Report of the subject defect was i ade to the Licensee (Public Service Company of New Hampshire) in the following sequences:
'On November 6, 1979, PSNH sa's orally notified.
On November 6,1979, PSNH was notified in writing by letter
~SBU-31426.
On December.5,1979, PSNH was given a follow-up interim report in writing by letter SBU-32245.
PSNH w's given further follow-up information
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On May 27, 1980, a
in writing by letter SBU-36792.
On August 29, 1980, PSNH was given a final report in writing by by letter SBU-38895.
This defect has been notified to the NRC under the rules and requirements of 10CFR Part 50.55(e).
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