ML19259D592
| ML19259D592 | |
| Person / Time | |
|---|---|
| Issue date: | 07/26/1979 |
| From: | Brickley R, Brown R, Hale C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19259D580 | List: |
| References | |
| REF-QA-99900524 99900524-79-2, NUDOCS 7910250145 | |
| Download: ML19259D592 (17) | |
Text
.
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV
-Peport No. 99900524/79-02 Program No. 51200 Ccapany:
Gibbs and Hill Incorporated 393 Seventh Avenue New York, New York 10001 Inspection Conducted:
July 9-13,1979 Inspectors:
> < H Da Ll$L4 7/2*3/79 R. H. Brickley, Principal Inspector-Date Program Evaluation Section Vendor Inspection Branch w WK
~l 3/9
~
R. L. Brown, Principal Inspector Date Program Evaluation Section Vendor Inspection Branch b.h hd8/r, 7/z 3/79 J
P. Costello, Principal Inspector Date P
ram Evaluation Section Vendor Inspection Branch Approved by:
. t.d. b
'7 h C. J. Wale, Chief, Program Evaluation Section Date Vendor Inspection Branch Summary Inspection on July 9-13, 1979 (99900524/79-02)
Area Inspected:
Implementation of 10 CFR 50, Ar,ndix B, criteria involving design inspection, design change control, design process management, develop-ment of GIBBSAR, action on previous inspection findings, and actions on a potential 10 CFR 21 item. The inspection involved ninety (90) inspector hours on site by three (3) NRC inspectors.
Resul ts :
In the six (6) areas inspected there were no unresolved items identified in any of the areas, no deviations identified in five (5) of 1213 202 7910250 "I
. the areas, and a deviation was identified in the remaining area:
Deviation:
Design process management - failure to follow procedures in indicating the revised text on a revision to a procedure.
1213 203 DETAILS SECTION I (Prepared by R. H. Brickley)
A.
Persons Contacted B. J. Benderski, fluclear Engineer D. J. Castro, Supervisory Instrumentation Engineer
- N.
'.. Hyman, Manager, QA
' J.
cons, Senior Engineer D. Mirkovic, Associate Engineer H. D. Ricevuto, QA Engineer J
C. Triolo, Senior 0A Engineer
- Cenotes attendance at the exit interview B.
Action on Previous Inspection Findings 1.
(Closed)
Deviation (Report No. 78-02) Personnel not attending the Nuclear Engineering Course as required by procedure. The inspector examined the corrective action and preventive measures described in the letter of response dated February 8,1979, i.e.,
Revision 3 to procedure QAI-02 (Procedure for Indoctrination and Training) dated April 1979 which allows discipline Chief Engineers to exempt-their personnel from attending the in-house Nuclear Engineering Course based on the indi"L.Jal's experience and training.
2.
(Closed)
Deviation (Report No. 79-01) Design Descriptions (Technical Descriptions) do not specify the issue date of applicable codes and standards. The inspector examined the corrective action and preventive measures described in the letter of response dated May 2,1979, i.e., Revision 4 to procedure DC-2 (Design Description Procedure) dated May 1979 which requires that the Purchase Order specify the issue date of codes and standards and, records of a seminar -(attendance list, outline, etc.)
conducted on July 9,1979, for Job Engineers on this subject.
3.
(Closed)
Deviation (Report No. 79-01) A completed design review checklist from the review of Calcolation No. 2323-NC-AA-05 (LOCA Analysis) was not submittcc to the QA Engineer. The inspector examined the corrective action and preventive measures described in the letter of response dated May 2,1979, i.e., the Design Review-Calculations-Record Form dated May 4,1979, and its completed attachment Nuclear Checklist-Calculations, records of a seminar (attendance list, outline, etc.) conducted on June 27, 1979 121.5 20't
_4 for Design Reviewers on this subject, and Audit Report No. I dated May 10, 1979, which covered implementation of procedure DC-10 (Design Review Procedure-Calculations).
4.
(Closed) Unresolved Item (Report No. 79-01) It was not apparent that the title, preparation, contents and implementation of the External Design Interface Document met the requirements of Section 2.0 (External Design Interfaces) of procedure DC-13 (Procedure for Identification and Control of Design Interfaces, Both External and Internal), Revision 1.
The inspector examined the corrective action and preventive measures described in the letter of response dated May 2,1979, i.e., Revision 2 to DC-13 dated May 1979 which deleted the requirements for a separate External Design Interface Document and identifies the Project Guide as the document covering these activities, and the scheduling of a seminar on July 25, 1979 on this subject.
C.
Rosemont Pressure Switches Rosemont, Inc. recently identified to a licensee (Comanche Peak) a problem with the lift-off voltage requirement for the 1153 Series-A pressure transmitter. Under certain operating conditions; such as a suppressed zero, ranged down span, low input pressure and low ambient operating temperature; the transmitter may not start-up when 12VDC power is applied (it may require as much as 30VDC to start-up).
The problem only affects the start-up. Once started it will function properly under the specified conditions with a minimum power supply of 12VDC.
A G & H letter to the licensee dated July 3,1979 identified those 1153 Series-A pressure transmitters supplied under Purchase Order CP-0611A.
Their investigation of the application of these units concluded that the instruments are passive I&C equipment that perform no active safety functior, and that they have limited QA requirements related to their pressure boundary integrity.
They further concluded that the nature of the problem and their application of the instruments excluded this defect as repor+able under 10 CFR 21, however, they will be returned to Rosemont for correction of the defect.
Further, dis-cussions with G&ti engineering personnel revealed that in their ap lication there is no operational interface with safety systems.
It ap
.rs that questions raised by this problem have been satisfactorily res,1 ved.
D.
Gibbs & Hill Standard Safety Analysis Report (GIBBSSAR)
M
)1\\b 1.
Objectives Tre objectfve of this area of the inspection was to verify the cbsecut of audit findings from the G&H audit report dated Pay 2, 1978.
(Reportlio. 99900524/78-02 paragraph II.B.3.h) 2.
Fethod of Accomolishment Tr.e preceding objective was accomplished by an examin?. tion of:
a.
Client /NRC Audit Follow-Up Log issue flo. 2 dated June 1979.
b.
Status Reports of Commitments to flRC (issued monthly to VP, OA) for the months of March, April, May, and June 1979.
c.
The reports of audits of mechanical calculations conducted on January 17, 1979; nuclear calculations conducted on January 23, 1979; and structural engineering conducted on January 30, 1979.
d.
The Master Audit Schedule covering the period April 1978 through July 1980 and the Audit Schedule and Record Sheets for each audited organization.
3.
Findings a.
All findings from the G&H audit of May 1978 have been closed out.
b.
Previously identified deviations (Enclosure, Report No.
99900524/78-02) have been closed out (Report tio. 99900524/79-01).
c.
It appears that the implementation of the QA Program as described in the G&H topical report is consistent with the status of ongoing activities in the development of GIBBSSAR.
d.
There were no c'eviations or unresolved items identified in this area of the inspection.
E.
Design Inspection - Containment Spray System 1.
Objectives The objectives of this ares of the inspection wet; to verify the following items, not completed during the previous inspection (Report fio. 99900524/78-02) for the containment spray system:
121.3 206 a.
Design analyses establish tie capability of the system tc provide flow at rates and tamperature which result in heat removal rates consistent with those utilized in the LOCA and/or main steam line break analyses, b.
Provisions and plans have been made for pre-operational and operational testing consistent with SAR com'tments and state m ts.
c.
The analysis (design) of system spray coverage supports SAR commitments and statements.
d.
The system design for pH control including analyses of pH versus time after system actuation supports SAR commitments and statements.
e.
Provisions to prevent trapping of chemical additivies imple-ment SAR commitments.
f.
Calculations of iodine removal constants, use parameters, and system characteristics are consistent with those in items a-h of Report t'o. 78-02, paragraph I.C.1.
g.
Iodine removal constants used in the analyses of the radio-logical consequences of a LOCA are consistent with item f.
above.
2.
Method of Accomolishment The preceding objectives were accomplished by an examination of:
a.
Sections 6.2.3 (Containment Air Purification and Cleanup System), 6.2.2 (Containment Heat Removal System), 6.2.1.3 (Mass and Energy Release Analysis for Postulated Loss-of-Coolant Accidents), Table 6.2-11 (Containment Spray System Component Design Parameters), and Table 6.2.1-2 (Peak Containment Pressures and Temperatures for a Spectrum of Loss-of-Coolant Accidents and Steam Line Breaks) of the Comanche Peak Steam Electric Station (CPSES) FSAR; and Secticn 17.1.2 (Quality Assurance During Design and Con-struction (Gibbs & Hill)) of the CPSES PSAR to identify the technical and programatic comitments for the Containment Spray System (CSS).
b.
Procedure Nos. DC-7 (Technical Calculation Procedure), DC-9 (Design Review P ocedure - Specifications), and DC-10 (Design Review Procedure - Calculations) of the CPSES Project Pro-cedures Manual; and QAII-D (Engineering and Design Verification 1213 207
?00RORGNIL Procedure) of the G&H QA Manual to determine that they were consistent with SAR commitments.
c.
Calculations No. NC-AA-05 (L0ra.!alysis), NC-CT-2 (LOCA Analysis) and associated rect 5-e.g., the Design Review -
Calculations - Record Form and the Nuclear Checklist -
Calculations to verify that they satisfied E.1.g. and E.1.a. above, and were done in accordance with applicable procedures.
d.
Drawing No. 2323-MI-0232 (Flow Diagram - Containment Spray System) Revision 5 dated June 7,1978 to verify that it pro-vided for pre-operational and operational testing (E.1.b.
above) and was done in accordance with applicable procedures.
a.
Calculation No. 232-10 (Containment Sprayed Volume) dated April 29,1977 and its associated records, e.g., Design Verification Record Form and Mechanical Checklist - Calcula-tions to verify that it satisfied E.1.c. above and was done in accordance with applicable procedures.
f.
Calculation No. 232-7 (Injection and Sutp Solution pH) Revision 1 dated March 21, 1979 and its associated records, e.g., Design Review - Calculations - Record Form and Mechanical Checklist-Calculations to verify that it satisfied E.1.d. above and was done in accordance with applicable procedures.
3.
Findings There were no deviations or unresolved items identified in this area of the inspection; however, the following items were identified:
a.
Calculation No. NC-CT-2 (LOCA Analysis)
The table of data on page 10 was not revised to reflect the changes made during Revision 1.
b.
Calculation No. 232-10 (Containment Sprayed Volume)
~
(1) On Page 19: The volume of a rotating olatform should be 3
3 125 ft, not 1023 ft, and of a polar c. cane should be 15,585 ft, ris 11,255 ft3 as listed.
3 (2) On Page 39: The results of a cgiculation of a volume 3
30' x 40' x l' should be 120 ft", not 130 ft as listed.
s 121.3 203
. (3)
Or. Page 40:
Theresultsofagalculationo{avolume 70' x 4' x l' should be 280 ft3, not 140 ft as listed.
(4)
On Page 39: The results of a calculation alume 3
56'x20"@(56'x4(20/12)7/shouldbe12i
,ot 88 ft,
(5)
On Page 40:
The results of a calculati a volume 84' x - h shouldbe16.5ft,not20ftgrsi 3
(6) On Page 78: The formula for the calculation of Area
= 1/2[r2(S +C )+C h ] should be AXVII = 1/2[r2(S -C )+
2 2 22 2 2 (7)
On Page 78:
XVUI = 1/2[The formula for the calculation of A r (3 +C )+C h ] should be A A
3 3 3 33 3 3 Ch31-c.
G&H management was asked to consider the cause of the type errors identified in a. and b. above and provide actions to prevent recurrence.
F.
Exit Interview An exit interview was bald with management representatives on July 13, 1979.
In addition to chose individuals indicated t'y an asterisk in paragraph A of each Details Section, those in attendance were:
J. R. Ainsworth, QA Engineer, Texas Utilities Generation Corrpany P. P. DeRienzo, Vice President, QA F. W. Gettler, Jr., Vice President, Power Engineering fl. fl. Y,eddis, Project QA Supervisor A. f!atiuk, President and Chief Executive Officer R. Prieto, Project Engineer W. B. Staab, QA Consulting Engineer E. J. Zadina, QA Engineer The inspector summarized the scope and findings of the inspection.
He also stated,that, as a result of observations and findings of this inspection, it appeared that a decided improvement has aeen made of QA activities on the Comanche Peak project such that, at present, QA performance is acceptable.
Management comments were generally for clarification only, or acknowledge-ment of the statements by the inspector.
3 M7 121.7
_9 DETAILS SECTION II (Prepared by J. R. Costello)
A.
Persons Contacted E. Horovitz, Supervising Mechanical Engineer
- C. A. Jacobsen, Quality Assurance Engineer G. M. Reiner, Project Engineer H. D. Ricevuta, Associate Quality Assurance Engineer P. K. Sweeney, Senior Project Engineer
- Denotes those present at the exit meeting B.
Design Process Managerrent 1.
Objectives The objectives of this area of inspection were to examine the establishrrent and implementation of quality related procedures for the design process to assure that:
a.
The design process system is defined, implemented, and enforced in accordance with approved procedures, instructions, or other documentation for all groups performing safety related design activities.
b.
Design inputs are properly prescribed and used for translation into specifications, drawings, instructions, or procedures.
c.
Appropriate quality standards for items inportant 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 performed from design input to final design.
e.
Design activities are documented in sufficient detail to permit design verification and auditing.
f.
Methods are prescribed for preparing design analyses, drawings, specifications, and other design documents and they are planned, controlled, and correctly performed.
1213 210
. 2.
Method of Accomplishment The preceding objectives were accomplished by an examination of:
a.
Section 17.1.2.3 (Design Control) of the Preliminary Safety Analysis Report, Amendment 5, dated April 5,1974, for Comanche Peak Steam Electric Station.
b.
Section 17.1.3 (Design Control) of the Final Safety Analysis Report, Amendment 6, dated May 31, 1979, for Comanche Peak Steam Electric Station.
c.
Gibbs & Hill Project Guide for Comanche Peak Steam Electric Station, Latest Revision dated June 22, 1979.
d.
Implerrenting instructions and procedures to satisfy PSAR/FSAR Quality Assurance Program Commitments, Gibbs & Hill Project Guide for Comanche Peak Steam Electric Station and to satisfy the intent of the objectives section above.
These are as follows:
(1)
Project Procedures for the Comanche Peak Steam Electric Station.
(a) Project Administration PA-4, Revision 2, February 1979 Project Guide (b)
Project Control PC-2, Revision 1, March 1972 Drawing Control PC-3, Revision 2, August 1974 Specification Production PC-4, Revision 4, April 1978 Vendor Drawings, Documents and Request for Deviation Handling PC-5, Revision 2, May 1973 Vendor Drawing Review Procedure PC-G, Revision 1, March 1972 Vendor Drawing, Follow-up
/
(c)
Design Control DC-1, Revision 1, March 1972 Codes & Standards Appli-cation DC-2, Revision 3, December 1973 Design Description DC-3, Revision 3, April 1978 Drawing Production 1213 211
\\
. DC-4, Revision 4, May 1975 Design Drawing, Checking and Approval DC-5, Revision 4, April 1978 Specification Production-and Solicitation of Bids DC-7, Revision 5, April 1978 Technical Calculations DC-8, Revision 4, May 1979 Design Review Procedure-Drawings DC-9, Revision 4, May 1979 Design Review Procedure-Specifications DC-10, Revision 4, May 1979 Design Review Procedure-Calculations DC-13, Revision 2, May 1979 Identification and Control of Design Interfaces both External and Internal (d) Quality Assurance QA-7, Revision 2, April 1979 Issuance, Modification and Control of Project Procedures Manual e.
Documents to verify implementation of PSAR/FSAR Quality Assurance Program commitments, procedural and project guide requirements and to satisfy the intent of the objectives section. These documents are as follows:
(1)
Drawing Status Report - Project No. 11-2323-001, dated 6/15/79.
(2) Specification Status Report - Project No. 11-2323-001, Issue 32, dated December 1978.
(3) Specification Status Report - Project No. 11-2323-001, Issue 34, dated May 1979.
(4) Specification 2323-MS-15A, dated 12/12/77 - Reactor Makeup Water Pumps Nuclear - design review completed 4/18/78 - vendor Bingham Willamette.
(5) Specification 2323-MS-208.3, dated 6/15/78 - Rubber Lined Steel Check Valves - design review completed 7/21/78 -
vendor TRW Mission Manufacturing Company.
(6) Specification 2323-MS-100, dated 8/15/77 - Piping Erection Specification - design review completed 11/28/77 - design review for revision 5 completed 3/23/79 - construction specification.
1213 212
. (7) Specification 2323-SS-10, dated 3/2/79 - Reinforcing Steel - design review ccepleted 4/11/79 - construction specification.
(8) Specification 2323-SS-20, dated 7/22/79 - Sei uic Criteria for Equipment Design - design review completed 8/24/76 - general specification.
(9) Specification 2323-ES-9, dated 10/28/77 - Static Un-interruptible Power Supply Systems - design review completed 4/5/78.
(10)
Specification 2323-ES-16, dated 4/7/78 - Digital Radiation Monitoring System - design review completed 6/7/78.
(11) Specification 2323-AS-27, dated 3/20/78 - Watertight Doors - design review completed 4/17/78.
(12) Calculation fio.16, Set 1 - Manual Calculations Equipment Loads (Auxiliary Building) - Book SAB 120G-1.
(13) Calculation fio. 5, Set 1 - Reactor Building Containment Penetrations - Book SRB-108C.
(14) Calculation lio. 2-260 - Residual Heat Removal System Heat Loss - Book 9.2.
(15) Technical Description 2323-TD-0228, dated 6/7/76 - Primary Plant Sampling System.
(16) Technical Description 2323-TD-0235, dated 6/10/76 - Spent Fuel Pool Cooling and Cleanup Systet..
(17) Technical Description 2323-MI-0241, dated 6/14/76 - De-mineralized & Reactor Make-Up-Water.
(18) Technical Description 2323-TD-0302, dated 6/22/76 - Diesel Generator Room Heating and Ventilating System.
(19)
Drawing El-0036-32, Revision 1, 3/3/77 - Solenoid Operated Damper X-HV-6179, Primary Plant Ventilation Exhaust Damper.
(20)
Drawing El-0171-03, Revision 1, 3/15/79 - Main Control Board CPI-ECPRCB-03, Interconnection Jiagram.
(21)
Drawing El-0031-45, Revision 1 1/11/77 - 6.9KV Switch-gear Bus 1EA1 Safety Injection Pump #11 Breaker 1APS11 Schematic Diagram.
1213 213 (22)
Drawing El-0022, Revision 1, 10/12/76 - Reactor-Turbine-Generator Trip Protection Diagram, Unit 1.
(23)
Drawing Mi-2702-1, Revision 3, 4/26/79 - Instrumentation &
Control Diagram - Main Steam Reheat and Steam Dump System.
(24)
Drawing M2-3513-13, Issue A, 12/11/78 - Diesel Generatcr Exhaust, Diesel Generator Room.
(25)
Drawing S-0836, Revision 2, 10/21/77 - Fuel Building Crane Supports & Details.
(26)
Drawing S1-0584, Revision 2, 4/3/79 - Reactor Building Internal Structure Pipe Whip Restraints.
3.
Findings In this area of inspection, one deviation from commitment was identified.
There were no unresolved items.
a.
Deviation (See Enclosure, "flotice of Deviation")
b.
Present Project Control Procedure PC-3, Revision 2, dated August 1974 (Specification Production Procedure) calls for a specification schedule to be prepared rronthly by the project group which is to be used in conjunction with the schedule issued by the Procurement Department.
The project group in conjunction with the purchasing group has developed a new series of reports called the Specification Assignment Report and the Specification and Purcher,e Order Report to replace the present Specification Sta%s Reports.
The new reports contain more information and will be issued periodically as needed rather than monthly. Work is in progress to update the Project Procedures to reflect this change.
This area will be further inspected during the next regular inspection.
1213 214
P003OMIML DETAILS SECTION III (Prepared by Ross L. Brown)
A.
Persons Contacted M. L. Bergman, Senior S'.ructural Engineer E. J. Bond, Supervising Structural Engineering
- 3. Czarnogorski, Quality Assurance Engineer H. D. Ricevuto, Quality Assurance Engineer T. R. Vardaro, Supervising Electrical Engineer
- Denotes those present at exit meeting B.
Design Change Control 1.
Objectives The objectives of this area of the inspection were to verify that:
Procedures have been established and implemented for a.
controlling changes to approved design documents.
b.
Design changes are:
(1) reviewed for the impact of the change (2) documented at to the action taken, and (3) transmitted to all affected persons and organizations.
The design changes are justified and subjected to review and c.
approval by the same groups or organizations as for the original design (see d. below for exceptions).
d.
When responsibility has been changed, the designated organi-zation shall have access to the pertinent information, competence in the specific area of design, and an under-standing of the require:nents and intent of the original design.
2.
Method of Accomplishmeg The preceding objectives were accomplished by an examination of:
a.
The following instructions and procedures:
1213 215
.. (1) Gibbs & Hill (G&H) Project Guide for Comanche Peak Steam Electric Station (CPSES) (Contract flo. 2323),
Section V, to identify any additional and/or unique project requirements relative to design change control.
(2)
Project Procedures Manual, procedure embers:
(a)
FL-3, Rev. 2; Specification Production (b)
PC-4, Rev. 4; Vendor Drawing, Documents and Request for Deviations Handling Procedure that describes the method (s) for handling vendor deviation requests and modification of the applicable specification and/or drawing.
(c)
PC-8, Rev. 3; Change Order Procedure - Engineering and Design, establishes the procedure to be followed and assigns responsibilities in handling engineering and design changes, regardless of the cause.
(d)
PC-9, Rev. 3; Design Change Procedure - Field, describes the procedures followed in handling field changes or deviations and to ensure proper control by qualified personnel of these changes or deviations and to establish the impact on the project and its technical acceptability.
(e)
DC-2, Rev. 4; Dcsign Description Procedure Requires, a design description document to be prepared stating all pertinent and relevant information required by the design personnel, and any design and/or technical revisions made af ter the first approvea issue :he requirement are the same as for the first issue.
(f DC-4, Rev. 4; Design Drawing Checking and Approval Procedure, establishes the guidelines to be followed in the Engineering and Design Departments for checking and approving drawings, including changes thereto.
(g)
DC-7, Rev. 5; Technical Calculation Procedure, requires that all calculations (including changes) performed as part of the engineering and design 121.73 216
300R ORBM effort are formally recorded, checked, approved and properly stored.
(h)
DC-8, Rev. 3; Design Review Procedure -
Drawings, requires that a design review be performed on all drawings and subsequent revisio, s for safety related structures, systems and components. The design review is performed against a checklist prepared for each discipline establishing those items to be addressed by the reviewer.
(i)
DC-9, Rev. 3; Design Review Procedure -
Specifications, requires that a design review be performed on specifications (and revisions) for all safety related structures, systems and components. The design review is to be performed by a qualified Design Review Engineer against a prepared checklist for each discipline.
(j) DC-10, Rev. 3; Design Review Procedure -
Calculations, requires that a design review be performed on cainulations (and revisions) by the appropriate departent for all safety related structures, systems, or.d components.
(k) QA-1, Rev. 4; Design and Engineering Surveillance Procedure, establishes the guidelines for QA surveillance of design and engineering activities to provide confidence that the applicable project requirements are being implemented.
b.
The following documents related to Contract 2323:
(1) Specification and Applicable Design Review Checklist:
(a) MS-12, issue 2, Containment Spray Pump.
(b) MS-208.1, issue 2, Steel Valves 2 1/2-inch and Larger.
(c) ES-8A, issue 2, Batteries and Accessories.
(d) ES-12, issue 1, Electrical Penetrations Assemblies.
121'> 217
.. (e) SS-15, issue 3, Personnel Air Lock.
(f) SS-18, issue 2, Stainless Steel Liver.
(2)
Drawings and Applicable Design Review Checklist:
(a) f11-0510, Rev. 6, Containment Spray Piping Arrgt. Sections.
(b) El-0018-1, Rev. 3, 208,120, and 118 VAC One Line Diagram.
(c) El-0033-11, Rev. 3, Bus IEB2 & 1EB4, Bus Tie Bkr. BT-1EB24.
(d) 51-0581, Rev. 2, R.B Internal Structural Pipe-whip Restraints, SR.1.
(e) SI-03116, Rev. 3, Condensate Storage Tank.
(3)
Design / Engineering Change / Deviation Requests (DE/CD);
S-00738, S-00903, Rev. 1, S-00673, S-01189, S-00943, S-00690, Rev. 1, S-00327 and S-00827.
(4)
Calculations for SS-15, Personnel Air Lock.
(5)
Specification Status Report.
(6)
Drawing Status Report.
3.
Findings ho deviations from commitment or unresolved items were identified in this area of the inspection.
1213 213