ML19276E939
| ML19276E939 | |
| Person / Time | |
|---|---|
| Issue date: | 02/12/1979 |
| From: | Donna Anderson, Hale C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19276E933 | List: |
| References | |
| REF-QA-99900502 NUDOCS 7903260074 | |
| Download: ML19276E939 (10) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV Report No.
99900502/79-01 Program No.
51200 Company :
Brown and Root, Incorporated Power Engineering 4100 Clinton Drive Post Office Box 3 Houston, Texas 77001 Inspection Conducted: January 29-February 2, 1979
^
//
/
Inspector:
. Mad eb 2/9/79 D. G. Anderson, Principal Inspector, Vendor
' D6te Inspection Branch
\\
lI u
& 79 Approved by:
C. J.
al, Chief, Program Evaluation Section, Date '
Vendo nspection Branch Summary Inspection on January 29-February 2, 1979 (99900502/79-01)
Areas Inspected:
Implementation of Title 10 CFR 50, Appendix B, and Topical Report, B&R 002A, including design process management.
The inspection involved thirty-eight (38) inspector hours on site by one (1)
USNRC inspector.
Results:
In the one (1) area inspected, one (1) deviation from commitment and one (1) unresolved item was identified.
Deviation: Design Process Management - two (2) calculations involving a safety related st.ucture did not include the date of approval or references for two (2) sets of design input.
Unresolved Item:
Response spectra for the Reactor Containment Structure as identified in a Brown and Root report appears to differ from that reported in the FSAR for the South Texas Project.
This item will be followed-up in the next inspection of Brown and Root.
For details of this unresolved item see Section B.3. of the Details Section.
790326007 9 DETAILS SECTION A.
Persons Contacted
- K. M. Broom, Vice President, Engineering
- G. W. Bulcken, Auditing Section Manager
- T. H. Gamon, Quality Assurance Manager
- L. E. Hayden, Jr., Engineering Project Manager
- B. F. Mitchell, Project Quality Engineer
- H. Paperno, Assistant Quality Assurance Manager
- J. E. Paden, Project Quality Engineer
- R. W. Peverly, Assistant Engineering Project Manager, Quality A. J. Smith, Engineer III
- K. A. Swarts, Engineering Manager S. P. N. Singh, Supervisor, Nuclear Analysis
- Indicates those attending the exit meeting.
B.
Design Process Management 1.
Objectives The objectives of this area of inspection was to examine the establishment and implementation of quality related procedures for the design process to verify that:
a.
The design process system is defined, implemented, and enforced in accordance with approved procedures, instruc-tions, or other documentation for all groups perfoming safety related design activities.
b.
Design inputs are properly prescribed and used for transla-tion into specifications, drawings, instructions, or proce-dures.
c.
Appropriate qu:lity standards for items important to safety are identified, documented, and their selection reviewed and approved.
d.
Final design can be related to the design input with this traceability documented, including the steps perfomed from design input to final design.
e.
Design activities are documented in sufficient detail to pennit design verification and auditing.
f.
The methods are prescribed for preparing design analyses, drawings, specifications, and other design documents so that they are planned, controlled, and correctly performed.
g.
The methods are prescribed for identifying design deficiencies including the documentation, review, and reporting of those deficiencies to management for evaluation.
Procedures exist for the reporting of significant deficiencies to the USNRC.
2.
Method of Accomplishment The preceding objectives were accomplished by:
a.
A review of the Brown and Root Topical Report, B&R-002A, Section 17.3, Design Control, which summarizes the methods used by Brown and Root, Power Engineering Group, to describe their activities related to the design process.
The design process is defined, implemented, and enforced according to the following procedures:
(1) The Brown and Root Quality Assurance Manual.
(2)
Engineering Procedures STP-DC-002-I, Engineering Pr ocedure for Drawing Control, May 15, 1978.
STP-DC-005-H, Preparation and Control of Specifica-tions, February 7, 1978.
STP-PM-005-F, Interface Control, No> ember 4,1977.
STP-DC-007-G, Preparation and Control of System Design Descriptions (SDD), August 22, 1978.
STP-DC-008-G, Calculations, February 3,1978.
STP-DC-009-G, File and File Storage, February 14, 1978.
STP-DC-012-G, Final Safety Analysis Report (FSAR)
Change Control, June 14, 1978.
STP-DC-013-C, Document Change Notice Control, January 24, 1978.
STP-DC-014-E, Document Comment Process, January 10, 1978.
STP-DC-015-G, Design Verification, January 29, 1979.
STP-DC-017-C, Computer Program Documentation, July 27,1978.
STP-DC-021-8, Ergineering Design Deficiencies, July 13,1978.
STP-DC-022-D, Processing Non-confonnance Reports, September 25, 1978.
STP-DC-023-G, Field Requests for Engineering Action, October 17, 1978.
Design inputs were reviewed in 'Ihe following documents:
b.
(1)
South Texas Project Scope Document for Houston Lighting and Power Company, Section 6.1, Reactor Containment System, December, 1973.
(2)
System Design Descriptions List dated January 5, 1979, and including:
SDD-3C1695D006-D, Containment Internal Structure, March 21, 1978 SDD-3A3695D001.4, General Structural Design Criteria SDD-5V140D006-C, Reactor Containment Building HVAC, September 15, 1978.
SDD-3Z149ZD007-B, Radiation Monitoring, July 28, 1978.
SDD-5Z169ZD009-B, Containment Hydrogen Monitoring System, September 16, 1978.
SDD-2C0195D010-E, Containment Structure, March 21, 1978.
SDD-5R289ND006-D, Essential Cooling Water System, September 6, 1978.
SDD-5R209ND007-C, Component Cooling Water System, September 16, 1978.
c.
Review to assure that the design inputs identified above were translated appropriately into the following documents:
(1)
Engineering Specifications:
3R289NS012-D, Essential Cooling Water Pumps, February 10, 1977.
3R209NS011-D, Component Cooling Water Pumps, January 12, 1977.
3R209NS033-D, Component Cooling Water Heat Exchangers, January 27, 1977.
2V211VS001E, Reactor Containment Fan Coolers, January 27, 1977.
(2)
Drawings:
1-Z-0016B, Piping Diagram Containment Hydrogen Monitor-ing System, August 29, 1978.
HVAC Reactor Containment Building:
1-V-0016I, Fan Coolers Flow Diagram, January 9,1978.
1-V-0017J, System Composite Diagram, January 9, 1978.
1-V-0018J, Normal Purge Subsystem Diagram, January 9, 1978.
1-V-0019J, Supplementary Purge Subsystem Diagram, January 9,1978.
1-V-0020J, Penetration Exhaust Subsystem Diagram, January 9, 1978.
1-V-0021J, HVAC Chilled Water Subsystem Diagram, April 15,1978.
1-V-0022J, Miscellaneous Supply Subsystem Diagram, January 9, 1978.
1-V-0083F, (Plan Elevation 11'3")
1-V-0084F, (Plan Elevation 2'0")
1-V-0085F, (Plan Elevation 19'0")
1-V-0086F, (Plan Elevation 37'3")
1-V-0087F, (Plan Elevation 52'0")
1-V-0088F, (Plan Elevation 68'0"), April 5,1978.
1-V-0092A, Partial Plan Elevation 52'0", August 15, 1978.
1-V-0093A, Partial Plan Elevation 52'0", August 15, 1978.
1-V-0094A, Sections, August 15, 1978.
1-V-00960, Partial Plan and Sections, April 5,1978.
1-V-0097A, Miscellaneous Plan and Sections, February 25, 1977.
The following drawings for the component cooling water system:
Piping Diagrams 1-F-5017G 1-F-5018G 1-F-5019G 1-F-5020G 1-F-5021G, April 27, 1978.
The following piping diagrams for the essential cooling water system:
1-F-5038G, 1-F-5039D, December 5, 1978.
Reactor Containment Fan Coolers HVAC System:
1-V-0089R, Enlarged Plan and Sections, February 25, 1977.
1-V-0098B, Enlarged Plan Cooling Coil, March 31, 1975.
1-V-0099B, Enclosure and Detail, March 31, 1975.
d.
The following documents were reviewed for identification and review of quality standards:
The inspector reviewed the System Design Descriptions identified in B.2.b. above and particular the section,
" Design Codes, Standards, and Regulations" for this requirmient.
Each System Design Description includes the System Lasign Description Title page (Fonn STP 200.48) which references the revie< and approval dates. The Status page for System Design Descriptions (Form STP 200.50) references the dates of the last revision.
e.
The inspector reviewed the steps taken in the design process from initial design input to incorporation into the final design documents.
For this effort, the inspector selected the description of the Reactor Containment Building in the South Texas Project Scope Document.
The System Design Description for the containment structure includes references to drawings and specifications.
Reports are developed such as: South Texas Project Engineering Report No.
3N160SR043-B, Final Seismic Analysis of the Reactor Containment Building, which provides input to the final design document, the FSAR for the South Texas Project.
This input is in the form of seismic response spectra which is generated from the following comnuter programs:
ES432, Plan Section Properties and Shear Force Distribution on Assembly of Rectangular Sections.
ES433, Composite Modal Damping ES434, Generation of New Time History Loads ES431, Response Envelope f.
The following activities related to design change control were reviewed by the inspector to assure that documentation was provided in sufficient detail to permit design verification and auditing:
(1) The following Document Change Notices (Form STP 200.29) related to the System Design Descriptions identified in B.2.b. above:
3C1695D006-C/DCN, March 3, 1978.
5V140VD006-B/DCN, September 12, 1978.
3Z149ZD007-A/DCN, July 22, 1976.
. 2Z169ZD009-A/DCN, August 15, 1978.
2C019SD010-D/DCN, February 24, 1978.
5R289ND006-C/DCN, September 15, 1978.
R289ND007-B/DCN, September 16, 1978.
(2)
The following verification activities were reviewed:
Report No. 3N160SR043-B, Verification Checklist, November.28, 1975.
Computer Program Verification Report No. VRES431.01, October 1975.
Computer Program Verification Report No. 013, June 15, 1976.
Computer Program Verification Report No. 020, October 5, 1976.
Computer Program Verification Report No. 018, September, 1976.
Computer Program Verification Report No. A6500M056A, September 14, 1978.
(3)
Document Review Comment (Form 200.40) was reviewed for the following drawings:
1-V-0083-C, September 30, 1976.
1-V-0089-B, March 12, 1976.
1-V-0016-H, January 5, 1978.
1-V-0021-I, March 22, 1978.
g.
The inspector reviewed the following design analyses to assure that they are planned, controlled, reviewed, approved, and correctly performed:
(1)
Calculations:
C019NC091E, Hydrogen Generation in the STP Contain-ment Following a LOCA, January 24, 1978.
3R209NC078, Design Temperature of the Component Cooling Water System, September 29, 1975.
3R209NC076B, Component Cooling Water System Design Pressure, October 8, 1976.
3R289NC076B, Essential Cooling Water Design Temperature and Pressure, September 13, 1978.
A479NC118B, Radiation Exposure to Equipment, July 9, 1976.
M129NC111, Radiation Exposure to Auxiliary Equipment, MAB, May 3, 1976.
N079NC175A, Containment Volumes, Free and Sprayed, undated.
. Design Verification (Form 200.40A) for each of the above calculations.
Verifier Qualifications (Form 200.80) for each verifying individual.
(2) Stress Calculation Packages:
2R209RC034, Component Cooling Water System Piping Analysis, May 17, 1978, including the following Stress Isometric Drawings for the Component Cooling Water System:
1R-0400-J, 30" Supply and Return Mani-
" olds, June 1, 1978.
1R-0402-F, "A" Train Return Header, June 1, 1978.
1R-0404-F, "B" Train Return Header, June 1, 1978.
1R-0406-F, "C" Train Return Header, June 1, 1978.
1R-0406-H, CVCS Island Return Line, June 1, 1978.
2R209RC035, Component Cooling Water System Piping Analysis, April 28, 1978, including the following Stress Isometric Drawing for the Component Cooling Water System:
1R-0403-G, "B" Train Suppiy Header, April 24, 1978.
3R289RC043, Stress Analysis Essential Cooling Water Supply, July 20, 1978, including drawing
- 0R-0013-C, July 28,1978.
3R289RC044, Stress Analysis Essential Cooling Water Supply, July 20, 1978, including drawing #0R-014-B, July 28,1978.
3R289RC045, Essential Cooling Water System Piping Analysis, July 20, 1978, including drawing #0R-015-B, July 28,1978.
3R289RC147 Rev. A, Essential Cooling Water System Piping Analysis, July 12, 1978, including drawings #1-R-0103-B, July 19,1978; #1-R-0104-B, July 19,1978; and #1-R-0105-B, July 19,1978.
. 3R289RC148 Rev. A, Essential Cooling Water System Piping Analysis, July 17, 1978, including drawings #1-R-01008, July 28,1978; #1-R-0101-B, July 28,1W8; and #1-R-0102-B, July 28,1978.
(3)
Computer Programs:
SUPERPIPE, Structural Analysis and Code Compliance Verification of Piping Systems, Version July 1,1978.
h.
The inspector reviewed Engineering Procedure STP-DC-021-B, Engineering Design Deficiencies, to assure that the procedure includes requirements for identifying design deficiencies, for the documentation, review and reporting of those defiencies to management for evaluation, and for the reporting of significant deficiencies to the USNRC.
3.
Findings In this area of the inspection one (1) deviation from commitment was identified (See Notice of Deviation, Enclosure). The following unresolved item was also identified during this inspec-tion:
During a comparison of the response spectra for the Reactor Containment Building from Report No. 3N160SR043-B and the FSAR-South Texas Project, the inspector noted that Figure 16.2-22, in the Report did not compare with Figure 3.7.35 in the FSAR.
Further questioning revealed that possibly the response spectra in the FSAR was in error.
However, Brown and Root personnel notified the inspector on February 6,1979, that the FSAR was correct and Figure 16.2-22 appears to be incorrect.
The inspector then suggested that Brown and Root determine if Figure 16.2-22 had been used by Engineering for the design of the Reactor Containment Structure.
The inspector will follow-up on this item at the next inspection.
C.
~ Exi t ' Meeti ng An exit meeting was conducted with Brown and Root management personnel at the conclusion of the inspection on February 2,1979. Those individuals indicated by an asterisk in Section A of this Details Section were in attendance.
In addition, the following were present:
E. H. Bomke, Senior Vice President, Power Engineering W. N. Phillips, Projects Quality Assurance Manager, Houston Lighting and Power Company C. W. Vincent, Project Quality Assurance Manager The inspector discussed the scope of this inspection and the details of the findings identified during this inspection.
Management representatives of Brown and Root acknowledged the statements by the inspector with respect to the one (1) deviation presented.
,