ML20052H293

QA Program Insp Rept 99900524/82-01 on 820222 & 24-26.No Noncompliance Noted.Major Areas Inspected:Analysis of Tornado Venting Sys,Status of Previous Insp Findings & Design Insp of Safe Shutdown Capability

ML20052H293
Person / Time
Issue date:	04/14/1982
From:	Fox D, Hale C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
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ML20052H288	List: ML20052H287 ML20052H293
References
REF-QA-99900524 NUDOCS 8205200156
Download: ML20052H293 (11)

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{{#Wiki_filter:. ORGANIZATION: GIBBS & HILL, INC. NEW YORK, NEW YORK REPORT INSPECTION INSPECTION NO.: 99900524/82-01 DATE(S) 2/22-26/82 ON-SITE HOURS: 26 CORRESPONDENCE ADDRESS: Gibbs and Hill, Inc. ATTN: Mr. P. P. DeRienzo, Vice President Quality Assurance ~ 393 Seventh Avenue New York, New York 10011 ORGANIZATIONAL CONTACT: Mr. N. N. Keddis, QA Manager TELEPHONE NUMBER: (212) 760-5450 PRINCIPAL PRODUCT: Architect Engineering and Consulting Services NUCLEAR INDUSTRY ACTIVITY: The total effort committed to domestic nuclear design activities is approximately 23% of the 2,000 employees of Gibbs & Hill, Inc., at their New York facilities. Major projects include the design of Comanche Peak, Units 1 and 2; Three Mile Island, Unit 1, FSAR update; Beaver Valley, Unit 1, equipment update, and Bellefonte, Unit 1, design studies. ASSIGNED INSPECTOR: \\/ h-/QO

0. F.Yox', Reactor /SystemsSection(RSS)

Date OTHER INSPECTOR (5): APPROVED BY: Rj h k-71 C. J 4 ale, Chief. RSS Date INSPECTION BASES AND SCOPE: A. BASES: 10 CFR Part 50, Appendix B and the PSAR and FSAR for the Comanche Peak Steam Electric Station (CPSES), Units 1 and 2. B. SCOPE: This inspection was made as a result of the issuance of a 10 CFR Part 21 report by Gibbs & Hill pertaining to an analysis of the Tornado Venting System for the Comanche Peak Steam Electric Station. Additional areas included in the inspection were status of previous inspection findings and design inspection of safe shutdown capability following high and moderate energy line breaks outside containment. PLANT SITE APPLICABILITY: Comanche Peak Steam Electric Station, Units 1 and 2, Dockets 50-445 and 50-446; Fort Calhoun, Unit 1, Docket 50-285. l ,wcanTED ORIGINAL $$00$$ E c m.ttN d Dy R 99900524 1

ORGANIZATION: GIBBS & HILL, INC. NEW YORK, NEW YORK REP 0Hi INdFtL110N NO.. 99900524/82-01 RESULTS: PAGE 2 of 4 A. VIOLATIONS: None. B. NONCONFORMANCES: None. C. UNRESOLVED ITEMS None. D. STATUS OF PREVIOUS INSPECTION FINDINGS: (Closed) Nonconformance (81-04): Contrary to CPSES project procedure DC-5, certain of the changes made in Revision 3 of specification 2323-MS-46A were not identified nor design reviewed. as required. Specification 2323-MS-46A was revised on February 2, 1982, (via DE/CD S-2564) to identify, with line bars and revision numbers, the pitviously unidentified changes that were made to Revision 3 of the specification. The revised specification was design reviewed on February 23, 1982. Procedure DC-5 was being revised to delete the requirement that design reviews be performed on the edited and finished typed document and permit the design review to be performed on a draft version of the document. The design review would be performed in parallel with the interdis-ciplinary reviews of the document. The originating discipline would be responsible for assuring that all significant changes made to the draft were design reviewed prior to issue of the document. Gibbs'and Hill management stated that the revised procedure will be issued during the first quarter of 1982. 1 m

l ORGANIZATION: GIBBS & HILL, INC NEW YORK, NEW YORK REPORT INSPECTION NO.: 99900524/82-01 RESULTS: PAGE 3 of 4 E. OTHER FINDINGS OR COMMENTS 1. 10 CFR Part 21 Report Inspection - Review of available docu-mentation, and interviews with cognizant personnel, indicate that the original (February 11, 1977) CPSES tornado venting system pressure and air flow analyses was not sufficiently detailed so as to determine if the pressure differential across interior walls, doors, glass panels, electrical equipment cabinets, etc., would exceed the design allow-able in the event of a design basis tornado (DBT). The original calculation assumed that the interior of the turbine, auxiliary, safeguards, fuel handing and electrical and controls buildings of the CPSES was divided into approximately 25 " fire zones" and determined the venting area necessary to assure that the maximum differential pressure (DP) between any two contiguous volumes (zones), or to the atmosphere, did not exceed the design allowable (DA) of 1.5 PSI. The analysis is currently being redone using the COMPARE computer code. The affected buildings are assumed to be divided into 95 interior volumes with 163 interconnecting air flow paths. The status (open and closed) of over 400 interior doors is being considered in the analysis. The preliminary results indicate that approximately 15% of the DPs exceed the DA by over 10% and that approximately 5% of the DPs exceed the DA by over 40%. The results of the calculation are being transmitted to the affected disciplines for the evalua-tion of the effect of the increased DPs and air mass flow rates on their designs and air handling systems. G&H stated that the calculation should be completed by March 26, 1982, and that all required design corrective actions will be completed during 1982. The inspector noted that the validity of the analyses is dependent upon the status of approximately 246 doors within the identified buildings. Some of the doors are assumed to be held open (or closed) during a DBT by a locking mechanism. The status of certain other doors during a DBT must be assured by administrative control. Further, many of the doors and their associated hardware are being procured as architectural doors and as such are only capable of with-standing a DR of from 0.3 to 0.8 PSI depending upon the direc-tion of the applied loading. G&H stated that this concern will be addressed during the design corrective action phase of the program.

ORGANIZATION: GIBBS & HILL, INC. NEW YORK, NEW YORK REPORT IN5P L110N NO.: 99900524/82-01 RESULTS: PAGE 4 of 4 Unit 1 of the Fort Calhoun nuclear power station was also designed by G&H. Detailed design records were not available at G&H for examination by the inspector. G&H management stated that they informed the Omaha Public Power District (0 PPD) of the situation prior to October 8, 1981. Action taken on this item by OPPD could not be determined from the documentation avail-able at G&H. This item will be followed during future inspections. 2. Design Inspection - Branch Technical Position Papers and sections of the CPSES Units 1 and 2 FSAR pertaining to postulated piping failures in fluid systems and accident analyses, were reviewed to determine the commitments, design bases, and design measures employed by G&H to assure that the nuclear power station can be safely shut down in the event of the postulated rupture of any high or moderate energy line outside of the reactor containment. One technical report, 2 analytical models, 22 drawings and figires, 7 calculations, 2 design verification records, and other related documentation were examined by the NRC inspector to verify imple-mentation of commitments. The NRC inspector determined that some of the subcompartment tempera-ture and pressure analyses performed to date do not appear to support the conclusion that no essential system or component required for safe plant shutdown is rendered incapable of performing its necessary functions as a result of any postulated pipe rupture. This area will be inspected further during subsequent inspections.

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