ML20205Q591
Text
_ _ _ _ _ _ _ - - _ _ -
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION INSPECTION NO.-
99900403/83-03 DATE(S) 8/29-9/2/83 ON-SITE HOURS: 135 CORRESPONDENCE ADDRESS: General Electric Company Nuclear Energy Business Operations ATTN:
W. H. Bruggeman, Vice President and General Manager 175 Curtner Avenue San Jose, California 95125 ORGANIZATIONAL CONTACT: Mr. J. J. Fox, Senior Program Manager TELEPHONE NUMBER:
(408) 925-6538 PRINCIPAL PRODUCT: Nuclear steam system supplier.
NUCLEAR INDUSTRY ACTIVITY: General Electric Ccmpany (GE), Nuclear Energy Business Operations (NEBO), has a work force of approximately 7000 people with approximately 98 percent of that work force devoted to domestic nuclear j
activity.
NEB 0 currently has 26 reactor units under construction and 2 reactor units under contract.
NEB 0 also has approximately 125 service contracts with various clients.
1h d.
bb[4'tbwE
/d-/M -63 ASSIGNED INSPECTOR:
D. D. Chamberlain, Reactor Systems Section (RSS)
Date OTHER INSPECTOR (S):
D. G. Breaux, RSS R. H. Brickley, RSS R. Nguyen, RSS P. Sears, RSS APPROVED BY:
G/
Qk-3 C. J. Ifli_lf,k Chi e f, RSS Date INSPECTION BASES AND SCOPE:
A.
BASES:
GE Topical Report No. NEDO-11209-04A and 10 CFR Part 21.
B.
SCOPE:
Status of previous inspection findings, design verification, and followup on the following items / requests:
(1) 10 CFR Part 50.55(e) report (River Bend project) stating that the heat loads provided by GE to Stone and Webster (S&W) for sizing the heating and ventilating (HVAC)
(cont. on next page)
PLANT SITE APPLICABILITY:
Plant docket Nos. 50-259, 50-260, 50-296, 50-322, 50-410, 50-416, 50-417 and 50-548.
h40g99ENVGENE 76 870323 99900403 PDR
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 2 of 13 SCOPE:
(cont.)
system in the high pressure coolant injection (HPCI) system diesel generator room were about 1/3 of the expected value; (2) licensee event report (Browns Ferry) regarding a common mode failure of HPCI high steam flow differential pressure switches; (3) 10 CFR Part 21 report (GE) stating that safety relief valves failed to comply with IEEE-323-1974 environmental qualification test requirements; (4) request to determine the basis for GE qualification of Rosemount 1152 transmitters to IEEE-323-1974 when the transmitters were qualified by the manufacturer to IEEE-323-1971; (5) 10 CFR Part 21 report (Grand Gulf) regarding internal and external corrosion in DikKers' safety relief valve actuators; (6) 10 CFR Part 50.55(e) report (Nine Mile Point) stating that shipping clamps were used erroneously for piping clamps in the control rod drive (CRD) system; (7) 10 CFR Part 50.55(e) report (Shoreham) regarding error in cata supplied by S&W to GE affecting rotational area response spectra and rotational time history of reactor vessel and associated components; and (8) request to review GE design process controls for verification of two computer programs (SAFER and GESTR).
A.
VIOLATIONS:
None B.
NONCONFORMANCES:
1.
Contrary to Section 5 of Topical Report No. NE00-11209-04A and Sections 4.1.2 and 4.4 of Engineering Operating Procedure (EOP) 42-6.00, " Independent Design Verification," design verifications of Nuclear Control and Instrumentation Division design documents are being deferred without controlling procedural requirements being implemented.
2.
Contrary to Section 5 of Topical Report No. NE00-11209-04A, Section 5.7.1 of NEDE-20586 and implementing procedure MP 5.07, GE did not request that Rosemount, Inc. issue a deviation disposition request (DDR) when Rosemount notified GE that they could not meet the IEEE 323-1974 environmental requirements imposed by a purchase order for Rosemount 1152 transmitters.
This res.lted in GE receiving and accepting purchased equipment that did not conform to the procurement document.
3.
Contrary to Section 5 cf Topical Report No. NECO-11209-04A and Section A1.1 of Appendix A to GE E0P 65-2.10, the CRD clamps supplied by GE on all the BWR-6 plants were classified as nonessential components without assurance that failure would not cause a loss of the integrity of the reactor coolant pressure boundary.
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO..
99900403/83-03 RESULTS:
PAGE 3 of 13 4.
Contrary to Section 5 of Topical Report No. NEDO-11209-04A and Section 2.3.7.1 of GE BWR Quality Assurance Manual, GE did not communicate needed design information to S&W that the CR0 clamps supplied by GE were nonessential components and could not be used as ASME qualified items in the analysis of the CRD piping system.
5.
Contrary to the requirements of Section 5 of Topical Report No. NEDO-11209-04A and paragraph 4.2.c.3 of E0P 42-10.00, " Design Record Files" (ORF), dated June 23, 1980, a DRF index (Form SD-006) or equivalent was not established and/or maintained for DRF Nos. A00-1160 (SAFER 01) and A1002 (GESTR08) as follows:
a.
A00-1160, the date entered and author's name were missing.
b.
A1002, the date entered was missing.
6.
Contrary to the requirements of Section 5 of Topical Report No. NEDO-11209-04A and paragraph 3.3.2 of Supplement A dated August 1, 1979, to EGP 42-1.00, " Introduction-Technology and Design Control," mathematical analysis contained in Section 8 of DRF No. A00-1160 was not prepared and documented so that a technically qualified person could review and evaluate its accuracy without recourse to the originator; e.g.,
the identification of the purpose, references, originator, reviewer, date, etc., were missing.
7.
Contrary to the requirements of Section 5 of Topical Report No. NED0-11209-04A and Supplement A (page 12) dated August 1, 1979, to EOP 42-1.00 which designates a functional specification as a design document subject to the requirements of ECP 42-6.10,
" Engineering Document Issue and Application," the functional specification for SAFER 01 was not controlled in accordance with E0P 42-6.10; e.g., (a) no identifying number, (b) no revision number, and (c) identification and signatures of originator, reviewer, and approver were missing.
C.
UNRESOLVED ITEMS:
None D.
STATUS OF PREVIOUS INSPECTION FINDINGS:
1.
(Closed) Nonconformance (82-03):
Documented instructions or procedures were not utilized to communicate quality requirements relating to the dispositioning of potential design action items.
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS.0PERATIONS SAN JOSE, CALIFORNIA
' REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 4 of 13 E0P 55-4.00 was revised on July 14, 1982, to formalize the requirement that the Change Control Board (CCB) maintain a list of potential design action items.
This E0P requirement was supplemented with a " Procedure for Potential Design Action Items" (latest issue June 21, 1983) which provides documented criteria for the disposition of potential design action items.
The CCB also reviews and approves the disposition of items.
2.
(0 pen) Nonconformance (83-01):
Use of the " Design Memo" was not delineated, accomplished, or controlled by any document such as a procedure or instruction.
GE issued procedure PDS-008, " Design Memos," in May 1983 which effectively documented existing practices for the control of design memos and a Quality Assurance Newsletter was issued in June 1983 to emphasize proper control of design inputs as committed.
This item will remain open pending NRC review of evidence that the control of design memos has been discussed in ongoing Nuclear Engineering Division Quality Assur:nce training and that a GE internal audit has included the control of design memos in the scope of the audit.
3.
(Closed) Unresolved Item (83-01):
It was not apparent if a GE specification (22A4019) requirement, assuring that the use of manifold and common piping is within the limits of physical separation and common mode failure, was considered or required on some BWR designs.
During the 83-01 inspection the NRC inspector was not able to obtain the GE specification for piping and tubing process instrumentation which applied to Browns Ferry.
A licensee event report had stated that HPCI high steam flow iso'lation switches were both rendered inoperable by one equalizing valve leaking past its seat.
During this inspection the GE specification for Browns Ferry was examined to determine requirements relative to instrument manifold piping design.
It was found that GE designed the piping according to applicable specification requirements at the time.
4.
(Closed) Unresolved Item (83-01):
It is not apparent that GE is in compliance with Section NB-3672.7 of the ASME Code which states, in part, "Where assumptions are used in calculations or model tests, the likelihood of underestimates of forces, moments, and stresses, incleding the effects of stress intensification, shall be er luated."
For clamps and supports in the 100 KIP category, GE has
- r. s. performed a formal evaluation of the effect of clamp induced local pipe stress.
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS
!J.N JOSE, CALIFORNIA REPORT INSPECTION N0..
99900403/83-03 RESULTS:
PAGE 5 of 13 The NRC has completed its initial evaluation of this problem.
The Division of Engineering has concluded that certain loadings induced by these specialized pipe clamps can result in significant localized stresses in the piping if not properly evaluated during design.
The NRC is now considering several courses of action for identifying, correcting, and controlling problems in this area of piping design.
When these actions have been defined, we will evaluate GE's design conformance; therefore, we consider this unresolved item closed, but it will be inspected further during future inspections.
E.
OTHER FINDINGS OR COMMENTS:
1.
Design Verification - The intent of this area of inspection was to conduct a review of design process control activities for the Nuclear Contrcl and Instrumentation Division (NC&ID).
During this inspection the NRC inspector concentrated on the design verification of changes to verified designs.
It was noted during the review of E0P 42-6.00, " Independent Design Verification," that the deferral of required design verifications is allowed for original design as well as for changes to original design. When a verification is deferred, a " Design Verification Status Change Notice" (DVSCN) form must be processed to identify the document, the scheduled date of deferred verification completion, design record file reference if applicable, and distribution identical to that of.the issued document (includes project in most cases).
The project managers / program managers are then responsible, based on DVSCN input, to notify the external user about the deferred verification status of applicable design data, together with schedule for verification and any limitations on the application of data or product hold requirements and to notify the user when verification has been completed. A review of design / design change documents on the River Bend project revealed that DVSCNs were not being prepared for verification deferrals in most cases and the external users were not being notified about the deferred verification status of applicable design data.
This lack of control of deferred verifications was identified as a nonconformance (see Section B.1).
In addition to the future closecut of this nonconformance, this area will be reviewed further during a future NRC inspection to access GE program for tracking and closeout of deferred verifications.
2.
HVAC Heat Load Sizing for the HPCI System (River Bend) - This area of inspection resulted from a 10 CFR Part 50.55(e) report stating that the heat loads provided to S&W by GE for the sizing of HVAC in the O
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 6 of 13 HPCI diesel generator room were about 1/3 the expected values. This item was reviewed during the 82-02 and 83-01 inspections and remained open pending the notification of all affected projects with final heat load values.
Based on actual testing done by one of the diesel suppliers, GE has provided the revised specifications and/or revised vendor manual data to all affected projects.
This item is considered closed.
3.
Common Mode Failure of Differential Pressure Switches (Browns Ferry) - This item resulted from a licensee event report which stated that the HPCI high steam flow isolation switches were both rendered inoperable by one equalizing valve leaking past its seat.
These switches have a common high pressure (HP) and low pressure (LP) sensing line, but each switch has its own individual HP and LP isolation and squalizing valve.
If one equalizing valve leaks, it could cause both redundant switches to actuate at a higher steam flow or not at all.
Plant designs (BWRs) later than Browns Ferry have separate instrument taps and sensing lines for each switch which eliminates this problem.
This item was reviewed during the 83-01 inspection and GE personnel were not able tc immediately obtain the specification for piping and tubing process instrumentation for Browns Ferry. During this inspection, the specification for Browns Ferry was examined and it was determined that GE designed the piping according to applicable specifications. Also, it was noted that GE issued a Service Information Letter (SIL No. 335) in July 1982 regarding the " Control of Differential Pressure Sensor Equalizing Valves." One of the GE recommendations contained in that letter was to remove installed equalizing valves and cap the low and high side pipe stubs.
Such removal would prevent equalizing valving errors and also prevent sensor errors due to leaky equalizing valves.
No violations or nonconformances were identified in this area of the inspection and this item is considered closed at GE.
4.
Solenoid Valves Associated with the Main Steam Line Saftey Relief Valves (SRVs) - Prior to 1979, SRVs were snipped and tagged as not having passed equipment qualification (EQ) testing. These SRVs had AVC0 solenoids. An engineering evaluation test performed on the solenoid /artuators showed certain deficiencies.
GE recalled all SRVs, specified a new solenoid (Crosby Model CVG-01), and proceeded with EQ testing. The new solenoid failed the EQ testing.
The CVG-01 solenoid could not be actuated with minimum available dc voltage during a postulated loss of coolant accident.
The inability to actuate was due to inadequate magnetic properties and the
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 7 of 13 increased coil electrical resistance at elevated LOCA temperatures.
GE reported the foregoing in a 10 CFR Part 21 report.
The valve was subsequently modified and subjected to a qualification program per IEEE Standard 323-1974.
The qualification was approved by the NRC (Equipment Qualification Branch of the Office of Nuclear Reactor Regulation).
It appears that the original qualification requirements were implemented by GE.
During the review, in the 1979 time frame, SRVs were shipped by GE to the following plants under construction:
Perry 1 and 2 Nine Mile Point Black Fox 1 and 2 Grand Gulf 1 and 2 Clinton 1 and 2 As noted above, these SRVs had been EQ tested to criteria in effect at the time.
Subsequently, NUREG-0588 was issued causing the imposition of new EQ requirements.
In 1982, Perry and Nine Mile Point transmitted to GE new radiation requirements which were generated by requirements in NUREG-0588. GE was contracted to perform EQ testing to the new requirements.
Certain sealing materials in the SRVs failed the test. GE took the following actions:
a.
A Potentially Reportable Condition (PRC) memorandum was generated and evaluated, b.
In their evaluation, GE concluded that the equipment was environmentally qualified to original requirements (pre-NUREG-0588).
For that reason, GE concluded that the described condition (failed test) does not constitute a deviation from the specification or a substantial safety hazard per 10 CFR Part 21.
GE notified by mail all of the affected plants (except Black Fox c.
which is a cancelled plant) of the failure of the subject valve to perform its function after being exposed to the test radiation.
d.
Nine Mile Point and Perry wrote 50.55(e) reports concerning the failure of the SRV actuator during EQ testing.
l l
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 8 of 13 In their evaluation, GE concluded that the SRVs were qualified by test to the pre-NUREG-0588 requirements, thus, were in compliance with applicable specifications, standards, and Regulatory Guides prior to the TMI event and the subsequent issue of NUREG-0588.
In their evaluation, GE concluded that because compliance with NUREG-0588 was beyond the original contract requirements, 10 CFR Part 21 does not apply to this situation.
After the failed test GE notified all relevant applicants who were using the SRVs.
Two of the applicants notified NRC through 50.55(e) reports.
Thus, nn snacific violations or nonconformances were identified.
The GE conclusion that the condition (failed test) does not constitute a substantial safety hazard simply because the SRV passed requirements in place before the promulgation of NUREG-0588 is incorrect.
The reasons put forth for GE's conclusions are unsatisfactory, even though 10.CFR Part 21 requirements were satisfied in this case.
Even though the requirements of NUREG-0588 may not apply to a basic component, test failures of such components should be evaluated to determine if a condition exists which could contribute to the exceeding of a safety limit (defect) and is, therefore, reportable.
5.
Qualification of Rosemount 1152 Transmitters - This area of inspection is a continuation of the 83-01 inspection which identified that a more detailed review of GE Control and Instrumentation Division (C&ID) needed to be made.
In the previous inspection the NRC inspector identified some concerns in the C&ID scope of work.
The first concern was that GE accepted equipment that did not meet purchase order requirements.
The inspector reviewed the purchase order file for the Rosemount 1152 transmitter, procurement 282-XEG55.
This review included all design documents and specifications that were referenced in the purchase order.
From this review, there was no evidence of a change in the purchase order requirements prior to delivery and acceptance of the purchased equipment that would have relieved Rosemount from qualifying their transmitters to meet IEEE 323-1974 requirements.
However, approximately 8 months after the delivery of these transmitters, an Engineering Change Notice was issued by GE to reflect a qualification requirement change from IEEE 323-1974 to IEEE-1971 on all previous and future procurements.
This resulted in one nonconformance identified (9.2 above).
The next concern was that Certificates of Compliance (C of C) issued by Rosemount did not certify that the purchase order requirements
ORGANIZATION: GENERAL ELECTRIC COMPANY -
NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 9 of 13 were met and GE accepted these limited C of Cs.
The inspector reviewed GE purchase specification 225A6635 entitled " Purchase Spec.
for Essential Components." This specification details what the vendor shall include in the transmitted certificates of compliance for the procured items.
A review of the Rosemount 1152 transmitter C of Cs revealed that they contained all of the required information
{
imposed by GE. GE now requires that the C of Cs contain a statement certifying that the product meets the requirements of the purchase order and referenced documents and be signed by the supplier's authorized QA representative.
Five C of Cs with these GE require-ments imposed on them were reviewed and found to contain the proper information.
In this area of the inspection, ne noncentormances were identified.
The next area of concern was that the retrieval of procu ement documents were very cumbarsema.
The C&ID procurement activities have been combined with Engineered Equipment and Installation (EE&I) procurement.
The responsibilities have been transferred, yet the procurement documentation centralization has yet to occur. This separation of documentation causes difficulties in retrieval activities.
Until this documentation is transferred, retrieval concerns will persist.
6.
Corrosion in Dikkers Safety Relief Valve Actuators - This item concerns a 10 CFR Part 50.55(e) report by Mississippi Power and Light to NRC Region II of internal corrosion of safety relief valve actuators on Grand Gulf, Units 1 and 2.
This corrosion was discovered during routine maintenance of a Dikkers' main steam iine safety relief valve.
Six of twenty installed actuators were found to be internally corroded.
In addition, corrosion was found in six of eight spare SRVs for Unit 1 and one of eight spare Unit 2 SRVs. All of the evidenced corrosion was on galvanized steel.
The NRC inspector reviewed records of the Dikkers' SRV for actions taken on this reportable item. Wyle Test Labs were contracted by GE to test one of the corroded SRV actuators to determine if the specified Class IE function of the device would have been compromised by this corrosion.
The results of the test showed that leakage rates were within designated design specifications.
GE concluded that the test provided a basis for demonstration that the noted corrosion products will not affect the required SRV Class 1E function.
a
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 10 of 1.*>
Corrective action was initiated by Mississippi Power and Light to clean and return the affected actuators to their original condition.
Fifteen actuators that were corroded have been rafurbished, tested, and returned to their original condition.
The six installed Unit 1 actuators were replaced with Unit 1 and Unit 2 spare actuators.
The Unit 2 actuators that have not been installed will be inspected prior to installation.
GE supplies these Dikkers' SRV actuators to the Clinton and Nine Mile Point, Unit 2, projects.
GE's engineering stated that these projects were made aware of cossible corrosion concerns on the Dikkers' SRV actuators. As of this date GE engineering has received no information from these other potentially impacted projects on any
{
corrosion detected.
Because of the seemingly isolated nature of the corroded Dikkers SRV actuator to the Grand Gulf, Unit 1 and 2, projects, GE engineering has concluded that the cause of the corrosion was storage conditions at the Grand Gulf site.
Region II will be notified of GE conclusions for ary actions deemed necessary.
There were no nonconformances or unresolved items identified.
7.
CRD Systems Clamps - This area of inspection was perft rmed as a result of a 10 CFR Part 50.55(e) report from Niagara >> hawk Power Corporation (NMPC) in June 1983 concerning the CRD sys.em clamp on l
Nine Mile Point, Unit 2, project (NMP2).
In the abovementioned report, NMPC stated that the CRD system piping clamps were included with the reactor vessel internals iupplied by GE. The clamps restrain piping in the area of CR0 housing.
Reactor Control, Incorporated (RCI), which was a subcontractor for S&W, utilized the clamps as ASME qualified components in CRD piping analysis.
It was stated in the 50.55(e) report that GE informed S&W that the clamps were intended for use only as shipping clamps and are not ASME qualified components.
During the inspection the NRC inspector examined numerous design and procurement documents relating to the CRD piping system and its components.
The following is a summary of this review.
a.
GE's scope of work for the CRD hydraulic line is from the CRD c
housing up to and including the attachment coupling at the periphery of the CRD housing pattern.
O
1 ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 11 of 13 b.
The CRD hydraulic lines are to be be designed, fabricated, inspected, and material selected and examined in accordance with ASME E.iler and Pressure Vessel Code,Section III, latest edition and latest applicable addenda for Class 2 components.
Design considerations for CRD hydraulic lines include the c.
following:
Normal and upset conditions: design pressure, static weight, operating basis earthquake, and design temperature.
Faulted conditions: design pressure, static weight, safe shutdown earthquate, and design temperature.
d.
The CRD hydraulic lines are classified as essential components in accordance with GE spec ##ication 22A3762.
e.
The insert and withdrawal lines are to be installed in a preplanned sequence that considers the access limitations imposed when the CRD housings and in-core housings are installed.
Framing and ciamping the insert and withdrawal lines, and their orientation and weiding to the CRD housings, is defined on the CRD hydraulic line installation kit drawing, f.
The installation kit' drawing was classified as an essential component drawing.
g.
The installation kit drawing did not indicate that the CRD clamps were shipping clamps and had to be removed.
It is noted from the information listed above that the CRD hydraulic line was classified as an essential component (an ASME Class 2 piping system) and its failure would effect the integrity of tha reactor coolant pressure boundary.
The CRD clamp which was designed by GE as a connection between the hydraulic line and the CRD housi419 structure was classified as a nonessential component but no assurance was provided that its failure would not cause a loss of the integrity of the reactor coolant pressure boundary.
In addition, during the inspection, no evidence was identified wnich indicated that GE communicated in writing that the CR0 clamps were nonessential components and could not be used as a permanent structural item in the CRD system piping analysis performed by RCI.
i
(
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 12 of 13 Nonconformances B.3 and B.4 above were identified in this area of the inspection.
The generic implications of this item are still being evaluated.
8.
Errors in Response Spectra - On September 27, 1982, Long Island Lighting Company (LILCO) notified NRC Region I.of an apparent discrepancy in the Ghosh-Wilson computer program used to develop the response spectra for the Shoreham project. A review of numerous documents by the NRC inspector indicated that the discrepancy occurred in an internal subroutine used by S&W to calculate the stiffness matrices for triangular finite elements.
In determination of the triangular element stiffness, the program divides such an element into three triangular subsections, then it calculates the stiffness of each subsection and combines them together to formulate the stiffness matrix of the overall triangular element.
In performing this function, the program incorrectly ignored the stiffness of two subsections, assigning the stiffness matrix of one subsection to the entire triangular element.
The problem subroutine has been corrected to include the stiffness matrices of all triangular subsections.
In addition to the error in the above subroutine, on February 15, 1983, LILCO reported an error that has been identified in the data transmitted by S&W to GE affecting the rotational response spectra and the rotational time history computations for the reactor pressure vessel and its associated piping and components.
The NRC inspector found that the error consisted of mislabeling of the units used in the response spectra.
The rocking acceleration data transmitted were labeled radian /sec', whereas the correct unit was g/ft. GE has been informed of this problem and is presently reviewing the Mark II confirmatory analysis.
This item will be examined during a future inspection at S&W.
9.
Computer Code Development and Use - This inspection was conducted in response to a request from the Division of Systems Integration, Office of Nuclear Reactor Regulation concerning the development and use of the SAFER and GESTR computer codes used for ECCS analysis.
The objectives of the inspection were to determine that these codes are developed and used in accordance with NRC requirements and guidance for design control of computer codes and that procedures exist that ensure that the Commission will be notified of matters reportable under NRC regulations 10 CFR Part 21 and 10 CFR Part 50.55(e) as applicable.
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.:
99900403/83-03 RESULTS:
PAGE 13 of 13 The preceding objectives were accomplished by a review of:
(1) applicable procedures from the E0P Manual; (2) the contents of design record file (DRF) A00-1160 (SAFER 01); (3) the contents of ORF A1002 (GESTR08); (4) ORF A00-01320 (SAFER /TLTA Qualification);
(5) SAFER 01 User Manual; and (6) GESTR08 User Manual.
The review of the preceding documents disclosed:
(1) both codes were developed and used in accordance with procedures that were effective during the related activity; (2) the procedures applicable to computer codes have improved significantly since the initial inspection in 1978 (Ref. Report No. 99900403/78-03); (3) the development and testing of both codes were independently reviewed by a design review team; (4) the verification tests for the codes involved data from simulation tests and/or actual plants (Vermont Yankee and Peach Bottom); and (5) the DRFs were well organized and contained adequate documentation of code activities.
Three nonconformances were identified in this area of the inspection (see paragraphs B.5, B.6, and B.7 above).
O
Inspector D.
Qld.dh181 lllN._.
f,f; h,'
6 Scope /Modul e__5TAIVS..-.d f._. fM Vl005
'~
DOCUMENTS EXAMINED INSPECTl0H FINDIH(rS
"~~~ ~~~ ~~~"
1 2
TITLE / SUBJECT 3
4 1
3 EoP 55~-4.00 alan (,6 coarnot 80ARD_
.A'25.83 2
3 DEGIGul rnEr/LO.S._ PDS=.00%
S16_3...
ASS IBdNC6.st6kSLLTTLR # 62._
6/_83.
3 QUALITY' L
4-3
$80LEDURF F0R 90 ftB11&L_oLS1Ghl.._ALTLoIL _LTLillS...-....... ff.Z//G.
N~
fi 56CTIoN L DESIG.DLA&_ TIM..LlST_
1/M/_83 1/288$
_.h
__S
_C0H1[LETIer4S QE6l.Gtl.AC.TJLH__ Ll(;iT
.7/_,2B/[63
~7
_8 5tCTIoH ]T 06.S!Gd. ACDDN Hh7 6
15 D6L6TI0HS Dk6IG.Lt-.Alf.10N L} 51.
..7/ZW63 i
Document Types:
Columns:
1.
Drawing 5.
Purchas Order 1.
Sequential Item Number 2.
Specification 6.
Internal Memo 2.
Type of Document 3.
Procedure 7.
Letter 3.
Date of Document i
4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revision (If applicable) l 1
inspector v. cunrnocru.n tiv neiortno.gj Sccpe/Hodule NclID of5}GN Page J.
of _f DOCUMENTS EXAMINED 99900403 PK0 CESS i
1 2
TITLE / SUBJECT 3
.4' 1
S RnVER Blno STATuoH MPL 18H506604 6-9-83_ REV.T 2
L EL6rdENTARY DIAGRArn
$28ES34 AA 865100AL llEAT IEevAL.
861/; 3 SYST6td j
3 L
ELLrnEnTART anGRBrA 82%E li3G AA HIGH PRESSI)RL cnR6 R6V. 7 '
SPRAY SYSTErn l
4 S
EoP 42 - 6.00 tuotPEHOENT DESIGH VfRIRCATioN 4 /3 0 /81 5
L ELtrr\\tHTARY Dan 6RArn
$2%ES31AA HPCS PoaLR svPPLY 6 83 REV, 6 SysTEra l
6 8
ECH no n3 39663 A005 ISOLATOR To TA60LATuN ukItcd is 4 83 0%to on Rc L15 t/o 7
ECH Ho. n339I83 camGE SIANG
]I-2 4 - 82 8
8 Eer/1 log no.
Arno-1204 RHR 9-2-77 9
ECr4 No. H534I26 A00 7tnw1 BD. pts 5-1442-10 fld HO. N337287 CtlGD El C006 D6L6(6D MfGS (Urflf 6 - lb CoHTROL CIRCUIT 12SVDC POWER lI 3
ECH N0.
N.T 37224 coR6Ec7 ORAFTraG ERROR 7-3142 8
ELrs H6.
n334024 CHAMGL 6LtGTRO SWITcti 3-29.g2 i
Document Types:
Columns:
1.
Drawing 5.
Purclias Order 1.
Sequential item Nu 2.
Specifica tion 6.
Internal Memo 2.
Type of Document 3.
Procedure 7.
Letter.
3.
Date of Document 4
4.
QA Manual 8.
Ollier (Specify-if necessary) 4.
Revision (if appli i
lusspector t).
LttFlribbtKLtllN ling >$Nt N.}3 Scepe/Hodule N C l l D 06SIf,N Page 2 of _2 DOCUMENTS EXAMINED Proc 6ss 99900.403 5.
t l
1 2
TITLE / SUBJECT 3__
.4 13 8'
ECM H3 417%3 cannas sworuissna comicom 5-3-83 l
14 S
Ecn NI 41790
/15 BdtL7 S-/7-83 15 1.
184-C5458 coHQ_DIA&RAr/\\
HIGH PR6SSURL ort SPRAY local 3-R-$ l R6/, O_
PANEL
{
16 var no.
E22-30 DL5IGhl VERIFICATIoM s(Irner1ARY II 8 I L'1 8
H311(o34 cnArg,6 R6 LAY T1PE CFD, SElSrntLALLY Nor 00Allfito 2-2 7-82.
tAllTd ' RELAY P\\lD. SEISrnICALLY 00ALifl6D i
18 1
184C5467 Ass 9 RtsInvAL H6Ar RErnollAL 11 local fAnLL L S1 9611. o i
I9 8
ERM t#.
AML-1379 issveo Asnes L-I2-81 g
20
.i 147D7877 RtSID0AL HEAT RErrnollAL LOCAL FANEL in 8-lJ-8I ItBl.1 21 L
762EA2bAA FCD RESIDt)hL llEAT Rtrnol/AL SYS Iky. 2 '
22 S
Ecr4 no.
n3 18516 mc. Mt ratino0S cunests nocco egos. ac.
G-9-81 i
I i
i Docuaient Types:
Colunwis:
1.
Drawing 5.
Purclias Order 1.
Sequential Item Nim i
j 2.
Speci fica tion 6.
Internal Memo 2.
Type of Document i
3.
Procedure 7.
Letter 3.
Date of Doctanent j
- 4. QA Hanual 8.
Ollier (Specify-if necessary) 4.
Revision (If appil.
1 i
I
Inspector D. Oldfd Ofd idlN_._
t i Scope / Module _}{E&T_1.0 AD._foR..sl.21W6 i
---DOCUMENTS EXAMINED ~ ~ ~ ~
1 2
TITLE / SUBJECT 3
4 1
2-23Alboz vtniu_ aims. cocunc ano wArsN& (nme-z.)C-3-83 2
S 30+A2720 nn5Teamtut 'Ano PARTS _.tnerquA)
(ame-1)_ 4 -2L-63_ 1_4LL..
3 R
204 A271o nasrRort\\Enr Ano
@ers imag_al-(4airtS digg)_ 4 -21_TJ K -
.5~
304 A 271l IHSTROmEn1 Sup PORTS _mauUBL (swg Oy 0 A -2 I-63_
_f 2
RiftAT ITfw1 20 7
S 304-A325'l IHsievent_nT_. Ano PneTs menvat_(BtAcK_Eox 2) 4-11-53
'8 2
RffEA T HtrA 20 4-21-6 3 so+A2712 Instevmsnr Ano pagth_mnuGAL (CUNTON))
9 6
23AI589 VENTILATLG&_, C000aG AND_BL&TlH6 (tuNTOH S-l9-83 lo 1
11 304-A2'il5 It4STRUMENT AND PARTS in6tilLAL (5MnD G0U 1) 4 53.
)2 2
23 A I55'?
JENTILkTl4b [00DWa AND fl[Afuk(6_ghn0 GdLO _ f_.L1-13 13 8
304A3252 InsraumEni' Ano PnRTS run0% (GRAno GULF 2)4-21-83_
l 4' 2
RtfEA T
- F ITirn i2-i 1.5~
304A2719 JNsrRomEnr Ano PflRTs tilnafg_(LnSALL61]
4 % 3 l
1.6 1
22A2114AA vinritAr,a6, conuac Ano atAms'(usetE). L-e-7L l
17 8~
304-A 3155 IH57R0rnEuf Ano PARTS ttlRHVAL(L SALLL Z}
4-2l-83 A
l i
Document Types:
Columns:
I 1.
Drawing 5.
Purchas Drder 1.
Sequential item Number
)
i 2.
Specification 6.
Internal Memo 2.
Type of Document j
3.
Procedure 7.
Letter 3.
Date of Document 4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revision (If applicable)
Docket tio. 99900402 l
Inspector D, GHdrd66_k lt]___
Reimrt No.
J3{
d Scope / Module _))&d.T_ l.0_AD_ _foR. 512146 Do_c_u_ntnTS cxAn_i.n..tD.
E~-
4 2
TITLE / SUBJECT 3
4 1
l 15 2
R6fulT IT6r/l IL l
19 304I272 l IHSTRVen6NT Aan PARTS rn6HohL [fERRT_l)___ 4-2L-13_
i
_20 2
23A1609 VLnTItATtab. CoolLHG_AND HEA1ING._@fRRT)_____ d:2_6.-83 21 3
Bo4 A 3257 19sTgurn6nt AND PAgts_remat_.ggggLO._. A-gh31
}!
22 2
REfERT ITErfL 1 0 l
23 3
304 A 2722 issTRUr46_NT AND PARTS Jy1ANDAL(gtv4R 86801)_
4-21-83
_CQAl.idb AND NfAlld6 4-22-63 23A 1591 VENTILdTMG_,T Ano PARTb_tino. VBL-{DKB.G.LT) __
}
24 2
304 A 2723 iss1RotoGn H
4 3 3 25 8
l 26 2
REf6AT of IT6rn L2
_21 8
304A2724 Insitorn64T AHo PARTS TMHVAL {TVA-XI'l)4-21-83 1s 2
29 8
30+ A3258 IHSTR0rMa7 Ano PARTS t'nAH0hL (TVh-X16) 4-21-83
\\
30 2
~~
~
l Bl 304 A3254 INSTR 0 ment AND PARTS rnquv6L (TVA -XI9) 4 2)-6[
l 32 2
i 83 8
Rod AE260 INSTRM6ni ANO PARTS rAhnvAL (rdA-X20) 4-2I-83
)'
34 2
i Document Types:
Colunes:
1.
Drawing 5.
Purchas Order 1.
Sequential item Number j
2.
Specification 6.
Internal Memo 2.
Type of Document J
3.
Procedure 7.
Letter 3.
Date of Document 4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revision (If applicable) i l
Inspector 0, c8ar/186RLAIN__
U",',M [', 7-.ff i
Scope / Module __]IE87 f.0AD_f0R.Sizi46
- 3#
\\
~DocuntnTS cxnMiNED
~~
i 1
2 TITLE / SUBJECT
,_ _3
. _ 4._.
35 S
304A32Cl IstST60 MENT Ano PARTS merI26_L__.(TVB-2h-A-21-83 w~
-a l
_3_7 304A32L2 msTRomEHT AHO PARTS. mam/AL (T&22)_.f-Al-33. _ -.
-38 L-l 39 9
GEWP-2-13-I49 t0PPSS HMFORK_^5~TiPCs D_16565 6 5 1.1_~~
j t;Er4ERATOR llEAT LGAD (PRC 81-43) i i
3 l3 Document Types:
Columns:
1 1.
Drawing 5.
Purchas Order 1.
Sequential item Numl>er 2.
Specification 6.
Internal Memo 2.
Type of Document 3.
Procedure 7.
Letter 3.
Date of Document j
4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revision (If applicable)
I m.p.. I 6 L). ttU AV R lis pi rf tin. g,.y Se tipt /11<wlisis _._
M W R H l'a i MHlm Il I
1
?
1111 I / stilt 11;ci 3
4
.._f_ _. E%.Fg 4
.;y W.fW %.%.J_
m.g e 7h/@
T.,
.. walt ~m.PW -
9/c/ri
_ _.3 _ _.
r=op dt-3. in h&op r_
f t$
t)8!. P~'
bAu _15p.
EP-SAW74 ~ urJa< Sp. p.m#2 re y..d. A L
. _ j_ _ _.c. a - m W % h_c23...JL PA RA ad. PrM+ - 9.Jk G h'TU <.
~3_ _ __._._it N AD 70.-t7..'.Qh.S h e*di..
As
. ___ _ I. _.. _ ___.I_lfd - O:I. I 5[??/ ~7G.
l
~
_.!I/s.VPi 3
_ _ L_ _.
_7. 'M M29 !. _. _...
.__@___7 P6 & X S 9fML... _... _... _..
QT/#/~O I
.____l
. E C_9 _ I.. N3 9.5.6 p_7._ _. _...
i0/1/W WDA.T7<W.?Lb L.#bb<d w.b M n 1 @-.E.b M J*... l[l9[78.
'T
__ S t
T:
&[@[7R O
_ G CN_ *.9 % M'
. _ R_.. _W~. mo:m e'1 Iz/!he f.. __
. qwtA._c-w b,>..w mJ__. c a~E..J wam,,
a/fjaa 9.
.. o y.J>3 4 _........
.. @ ~'tl6 ' kur.A U p 5 g b." M __.._ _..
- /_.t.7 gr._
L d
1 Document Types:
Columns:
i 1.
Drawing 5.
P.urchas Order 1.
Sequential item Number 7.
Speci fica tion 6.
Internal Memo 2.
Type of Docianent 3.
Procedure 7.
Letter 3.
Da te o f Documen t l
-4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revision (If applicable)
i inspect >r D. fdp.eAq-Hepr>rt. Nn.
,9.,.,~'
j Ed'l" 'A> f
. i.
Scope /Hodule-...
DOCUMINIS_EX_AMINED 4
I I
2 TITI.E/SilBJECT 3._..
4,
?
-Q$ KL3-DStt b2)f$m2 h
.pWc_ifyy
.__O_.______.
/
- W /M C B't.7_8IdGL_
1
.22.L_-
[
Y $ oE_C\\-..PQ Nf_S h /
,(.,fitflC-
._z {2.t q.
E' S&
h
$cu.b uLb_0~DDR )2. If>L~ !?'ifl........
_Q.....
urF an29-r pJ.at _t/A.r. t&,.,_q(ar....' ' _.. _ _ _.
%t - cn oa.
W.,mt-n..16.mng.
._spp.
- $ub : t}&rac0_ g_ic t-G M.-~
Mu,ak%,,,, wwh St)
$(,.sp 2___
G Ma j
brae.<VW ec_W '
S
."$L&dt1<-.TLklet.<llO'
{al3 (e.
~
~
G Mme-
%A
- tad, 4.<h ~Lb Aw, A MaZi[ --a/
pljp [r
\\
0 NA K fr - V k _ _<f P 3 ST. -
~
5
"'" M ';
TG19 @_~Ze g
g 9
FOB //
" rp,P-o'o
<r uc u-e s
i Document Types:
Columns:
1.
Drawing 5.
Purclias Order 1.
Sequential Item Numler 2.
Specification 6.
Internal Memo 2.
Type of Dociment l
3.
Procedure 7.
I.etter 3.
Date of Document i
4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revision (if applical>1e)
I
!l l
l
..r~--
a w uv :_.
Report No.
E?.
.c, t Pd9e T~~ of ~1 T ~~
k ope / Module - - - - - - - - - - - - - - - - - - - - - -
010MJ RSJ q l y
. I.-.
2_
.. 1111 f/ SUBJECT., __ _ _ _ _ _ _ _
- 3. _.
.. _4
_2
_ GP -.r4 E t L h[a[W
. $-- -- _.%<t-.012A. 9b. /4&'!( tJGDr - Wf4_. _... _ _ _ _ _ _ _ _ _.
/?-//G/iC -
If(..
J __ _Ec>J m2.-m= n str4M.
O.
. 2 --_
.F % _ -*'CA R ".) W S b t.
YWh3 0
. B_. _..... B<edt Ch ! L3 D. !D. # w'V T fr,c<
% i 5' <-
'~/;V/F s
_ff__.__.
. 69F_ $... MA 1. ( 2. <
M r.,0 MW 2
._ff_. _
AesannonA_kyds ' b -( PQ'b A L 1 3 0 S'/3i[9%
._8._
.--.9A__ % & X=-
-o k & k T ~ t W I M 't D a Y w cA
.G/3jh-f 3
f
. }M.le..J)lD k. T. G6W 39_.. __. _....... _.--..._
..l.
. - - -..~
M d
_N-3/97
._ 9 u-Document Types:
Columns:
1.
Drawing 5.
Purchas Drifer 1.
Sequential item Number 2.
Speci fica tion 6.
Internal Memo 7.
Type of Document 3.
Procedure 7.
l.c t ter 3.
Dale of DocumenL 4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revision (if applicable)
i ilocF.cl flo.
Inspector P. #sc A iz '
Report No. ;s,s j}-{
Vane t_ of
_L
~~
Scope / Module- - -
DOCUMENTS EXAMlitED j
1 1
1 2
TITLE / SUBJECT 3
4 L
J_
C 47 i - G/12.T. o.1 : i o --- i9 2eV l j_
G Wav as I's a1 G l u - T.s e E L A u_Q "i.)
Z.
G Wm_ = t ;. A s t r G. _ y ' c A.&. c cnt4nge, t
( 0 r *.&_)
i M Acir. E c u. r.&_s '.m o M Ari c acJ.u e ' ^lisL__ 3 G M _0
-'I ['8 _h d I
)
3 g
TasT
, d. ro.2 T
's w.o..J c
,w a a _si_ i_._ c nuv 1.
i s
- 3..< af o. o l
P.T w c n e.g. c.
1 A L i A
Gu i. t J_LL_.... #_.h.iau_f1_<9 s f
r3 v. t c,e s yAc m 3 - c.,. 4
.2 c u-c, t
(<-c Aq ;.s s M vi 'Pi - )
7 [n [7 '?
5 1
4 2
c.a s.
a A L -'* a Q.. P e to E. c1T".>
Cc. A T a <g o iW Eh w:.. I v P g L i c_.-
JA LVd.
- 7. I A 'I's M A 3 Sh.M5 3
is' y
G e.
To ri a m i ss i c i'. a.sua.e :( t_.iG 64 7
<_ v
.sii.o, reaA r c c,1,a c3 6 vtIT t.aJ A G rd ori a iG G oi-t Ai s_L ib Si?.v 7/83/31.
c i
- c. a r,,
r u_uLc.e, Pueea cv
.3/" / D t
i 7
S Mc.a T d c do ec s GG L orecs ic4cv a i.dC E LL s.J g. %
Pt.u s p. -
t<n r.u2 s.o v ir t>m.or.im r u su c.oq I
c.,a 40 r...c o ca__.aro a 1/. /u __
2 C
Lc.',o.. a
- r. Jgeiwott
.oad : P 2c n-t 1
_s
-t rA. css
$l t 3[3 3 j.
Ce R (. Ah.,1. el C i c.
M oT Q E i"t> R T. edC FA ntopC OF sin l
As PART 2t i
j j
Document Types:
Coltanns:
i 1.
Drawing 5.
Purchas Order 1.
Sequential Item Nianber 2.
Specification 6.
Internal Memo 2.
Type of Document j
3.
Procedure 7.
Letter 3.
Date of Document 4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revision (If applicable) i I
l l
i
I Inspec ter __ _P.
SE AD__.___ ____
[ fd,-k 'g-Patie i.
of ' g, ~ ~
j Scope / Module DOCUMENTS EXAMINED 1
2 TITLE / SUBJECT 3
4 l
- l 2
Ge_Ma eat e.teu i eic. E.dVi eo4 McN rAL. GeA L.,
1 J Ad dS ),
Phi R AM -
- t. ig__,1 Si d C T6t'stAL imper'T dED(24321. *?
e J
lO R
E. ed% Ro e4 F4G d TA_L___ CCdbiTeoQ L QAT_A 9_1gs
~b R ' 5 8 4 Po13 __.L'Oi4 Pa P-Ci__ t 4 2 _ __ _____
~
)
11 ErlViRoed FIENTAL. < Ce t4 D L Ts ctdfj_ DAT A "st{cc_T s Sf2-k_Q
% D 6 D 83 c;cy ; E O C. (_T ) {
I j
a j
i I
i 1
l 1
l -
1 I
l Document Types:
Columns:
j 1.
Drawing 5.
Purchas Drder 1.
Sequential Item Number l
2.
Specification 6.
Internal Memo 2.
Type of Document 3.
Procedure 7.
Letter 3.
Date of Document 1
- 4. QA Manual 8.
Other (Specify-if necessary) 4.
Revision (if applicable)
. - - - _. - - - _ _. =
l'ar.e nt R Iespector: k t ( H A A D f. PJ G U Y E d Docket No.:
9 'l C) 0 0 40 3 Scope / Module:
CRO CLA m P Report No.:
I3-o2 Res feedse SrscTftA Item Document TITLE / SUBJECT Date Revision No.
Type 1
LETTER Fftern C. 6. L EWI S dF G. E To R. E. m its. cit.
4 - 4. 93 of 54W Ae>ooT rdM P-2 N oc t.cAn. fbwe PLANT Z
?
LETTEft Fgom 8.. E.
M I L t.e g oF S k W ro c. G. L ewis oF 3 2s. 23 C4. E.
AP>ouT CKD C LAM PS 3
1 DR6 t4o.
?c,9 E YM - INSTA ttATrod M T5, H YDRAULi c S.(q_ M LIME CKD 4
i DA.6 No. 13 7C534-o 6A#JD C LAMP, HYDRAvLic Linc5 o.zt..Tl 2___.
5 T
LE TTEst _.G__E A. Ze 88, P;D I - 116 oooz - l'7 z ct.
It zs_82 C.
8 FDDR t4 0.
KGf of t 7 t-is-83 o
1 E
FDDft tJo.
K G I - ol'L l 2-ZE -83 z.
A A
FD P F.
too.
KGl - of %
S-31-83 J_....__
i 9
2 5FcciF CAT o,J no.
Zt A884S S_ict _7c t
E 12 I
DftAwsN6 tJo.
'L8 E 354-tr_zs-a s la t
Of Awic/(4 t0s.
IS ? C 54 04 PolRcH Asc PART, STEAf,
So_ra__7C. _2 _. _
>>w O 12 i
OfAwi,44
~ % 7 E.lE4-FITO R Aut.t'c Lf9E., CRD f
238 X n3 AF 2-n-8 2.
_ _f.
ll Document Types:
- 1. Drawing
- 5. Purchase Order 1
- 2. Specification
- 6. Internal Memo
- 3. Procedure
- 7. Letter
- 4. QA Manual
- 8. Other
Parc 2 or If mc m NTS m MINED Inspector: biGHAFP 8 tJGUYEd
- 1 # 1 o O_4 o 3 1
Docket No.:
Scope / Module: C ED CNC Report No.:_
B3-02 Ac5fbross syscTdth Item Document TITLE /s0BJECT Date Revision No.
Type Itp.
g MPL - 23g x g n AF _. E> J h. REacTom system. Item s zs-82 z s. _.
i t40.
00~18 WYPAAutic LINC. CRD 284 X'241 Goo l O.C.. H VORAutic Linc.ClO pczI A 884 C HYpRAouc LIME. CRD ZZA4 L5lo A6 HYDRAutt'c LiN E, cRD
~7b9 E 311 Foo I HYoRAutic Linc. cRD 7b 1E ~124 Poof-gg g
RocKiq tJ-s c Hu6 c, rM 12.esFoN5E Stec.T(A is-g-gz i f-1 LE.TTe st.
FRom P T.
Hb f_DEsd OF G.E-To F. l-.
Z-8 83 L68, RE O F__S & W GEA - Sc 24 i1 1
LeTTec Fgom D.J.
HKOM ADA oF S t W To
- w. J.
g _zs.s3 m ussi.EE 11 8
SHo EEH AM FJ Ed SRV[locA idoO At_
ARS cdoss FLoTS z zs'_ X3 l
19 8
pWAmic LoAp E vat unTiorJ A B, - oco 32 - I t- &_A3 zo
(,
LETre* Fgom V. E.
Fou S EMrs
- ..le.- __n_
i z.
L LETTER Fgom E.T.
TowscaD s_3 J+
_ 2 2,..
1 LeTTef. TRom C. G. t-E(Mis To
'T. T.
tasE2A B 4 To w S Ki L
- 5-13 E3 8
DE516M SPEC fl~t CATsoM rio.
El A 8845 5 $
g Docyment Types:
- 1. Drawing
- 5. Purchase Order
- 2. Specification
- 6. Internal Memo
- 3. Procedure
- 7. Let ter
- 4. QA Manual
- 8. Other l
n=a y,c p no w I0ME
-NbUYEd
""#3 """
Inspect or:
nockze No.:
9 Pt oo 4 o 3 Scope / Module: I65 Poe'se SPEcTsto Report No.:
82,,-o2 cpp'c La m ts l
Iteca Document TITLE /SUIUECT Date Revision l
No.
Type 24 8
x-PLors otp i NEd T. H.
A RS FAcTorcs A N r>
i-s_s3 Assess m eMT Z.5 Z
5 PE ci F: cation No.
24 A 8485
- 1 29 #z
[
IC 2
De5164 SPEcificATrord ZZ A 6734-, M PL abzi/Ps51 -oo l z -iG -53
_i_.
Pi PiiJ 6, m an,a s T c ^ m i Recis cuLA Tiod
)
r1 S
ftpield, MA f rJ STEAM f [dEcGECULATroid, tdo. 22 AG~l34-A A Z-if 83 2t 8
91Virl(s, MA sh STEAM & VEClit Cut. ATE DAl -
z jo.g3 Dc22 A6134. AA 2.9 8
DypJAMic LOAD MEfo4TS, S E15m s'c, Lo tA, SR L/ AMP ANrJU L us PEE 550 RMATe oM A41-54+o 30 B
COMPo Tc2 te6 - S ungc H Am FAcTaft. A55cm 6LE 2-z4 83 3l 8
S Hoyt.E H AM F^croc STooY l-21 83 31
~
8 PisYs comroTeg. PROGRAM mArouAt NcoE-24o n 3_ ; g 33 g
AsO51s 7 Pro 6 EAm u s eg's mAravAL Ngoc-2 3518 l-2-83 3+
8 S sr + G o~1 vs EK's matuUAL
^
_ _ z_ _~} q_
g 3G 8
S Ho LEH AM REce6cutATeevo B - SAr4 Fogccs Asco y _ic _sz M D M EeJTS Document Types:
- 1. Drawing
- 5. Purchase Order
- 2. Specification
- 6. Internal Memo
- 3. Procedure
- 7. Letter
- 4. QA Manual
- 8. Other l
l
f Pety.c 4 cf M
'CHA @
WUYd.
Docket No.:
- 1'19004 o '$
I;:::spector:
Scope / Module:
cFl> C LAMf Report No.:
8 h - o 2.
(tesrodse. SfscTFA Item Document TITLE / SUBJECT Date Revision No.
Type 3C 8
S FtoR EH A M tv1AirJSTEAe1 llNE 8 - $AP4 f0KCES ANI) g_zo_gz monA EMTS F1 B
M AlenTcAm Liac B
Pif'ING sTszess Recoer sz 6.32.
po.
ZZA 84 8'l 3g i
DRAtuirM
~7 6 1 E '5 4 9 Steam P re susPewsiord 3 to.3 7s _. c. _ _.. _
M PL no. P,2I Gooz S urs I,2, r 2A 8
Mash steam E2 Pir>E tu sTI A Lt ? AT# oA)
- 8. (q. 82 l
4-o 6
class _jftc4 Ticel ay CRD P8PE CLAMP.5, TRem L.T.
G.3 13 C Hoc ks'E TD po mesTic fito JccT DErr JAN ToJE CA LI foC#ds'A l
f Document Types-
- 1. Drawing
- 5. Purchase Order
- 2. Specification
- 6. Internal Memo l
- 3. Procedure
- 7. Letter j
- 4. QA Manual
- 8. Other
l Ikicket No. 977dovd3 Inspector EN.Egif-/r/47--- ---- -
ReporLNo.yy-gg]
Scope / Module G / d. C h g [s/r [,/,,
~
- ' ~ ~
D0_CMMyy l
l i
l 1
2 TITLE / SUBJECT 3
4 so,e so-ao*,emp L q--M2%ft,m,
,,-7f7,r,s' f^~~
s
,.4;,
aorw:,.a.,rg =wr--ya.na m ir>+1rn:
- - = - -
3 3
I j
m 7, grgeog e,
- xrzw r--) c y-,1 ww- -- - - -- --- -- -- ---
-77E/irr
~~~;---
soe 42.-In.ao Q^~~WMYu
~
~~~~ **~~~~
~ ~~~~~~
s T1747Wi ~
' = ' * " ~ ~ ~
C 3
l 2.".%eards Mfsee A fa 6 3 f'8K-/c
' ' ~ ' ' ' ' ' ' ' ~ ~ ~ ~ ~ ~
~ -~
~~~~
^' '/W/f 3
~ 's~' ' ~~'
4-1 sep 2a-eMss =~2P:#%-naturcoiscfr~o~jsnerbhpfsrs-o y/ silt 3F~
~~
ir.~
7 3
cy L'e^^}"~EY14~T fan ~.ifM.~~+dPEiza/ -4svrIe x/r/k s M c P A b t T & ~s k F 5 M o o 5)iffl'~
~ X ~ ~ ~~
t e
r l
Esf 485&s*t'.f - 4Ansto a staE/r' S ~
s I
so E
t'y s,s.6sJe d2' M.* JnTso-'Y
~575/Ei~~
~~h '~ ~ ~ ~
swA >*EATro sq
' ' ' ~
</=RI' ~ ~
~ ~ W ~~ ~~
t
- 1 r
ym ix 1. a.# i;yr... -uren*& br/
- a. m m w r Cc;r^
M* b*r -.3Ve sal 1E,1 g ymm
.,74 -
- ~3 E
,a g,
=m. go, ig.cowsros
's/*V!!. _ - - -
~
{
u- :':M QN&p MPEKol - FD$.al-Y/
~V ?llYI'
~ = ~ ~ ' ~ ~ ~
yrwmo, rwr-. ----- -
y f,,
= _f.Ag
_ -TM_ :.-}.cfE&m :::- _
s t.
~S flW87-3 FKAEB1
~
i I
i j
Document Types:
Columns-1.
Drawing 5.
Purchas Order 1.
Sequential item Nimler -
j 2.
Specification 6.
Internal Memo 2.
Type of Docimient 3.
Procedure 7.
Letter 3.
Date of Document i
4.
QA Manual 8.
Other (Specify-if necessary) 4.
Revision (If applicable) i 1
4
l Inspector T/.//.7Js,c/cfr g,
.l Scope / Module &fsg/of
.;/.rpMc+
P#N" E "f A-g g3 g g
)
i
+
i 1
2 TITLE / SUBJECT 3
4 f
y m iz p~. 6aevturvww vrLE==h~pAjr w - ~fr~
- l nz.=a$@%gg7 m y h=,+= ?
--- -,.. i-
- 1. - -
~
I1 8
, a;,po,.,g.
T%
N
- _^
& 9te* # ^ "~?: ] ff f
' ~ - - ~ ~ ~ ~ ~
~
mm cear-en
-=
s.a
= - - - -
incM-o*/-k3; $XYMMbTY
' if k Q - f 3 5 '~ E ~~'~~~ ~~~
~
sfoji5r ~
'. ~. ~ ~ ~ ~ ~
xec-as-zz,pfu4f Cs='A"'A ^~. $
J + _ ^
en- >*l'. JEW _ _
'N'Yl
~
ADAS. 2n d/
Z3 s*retz ? - Q W.
~ 7 5Nrs.
~;'~'
s Sa/
e, ggof-22tn.T, eAFKd6'r ~ds rE*s Mear.mei e, j yy_ *
~~ b *'~ ~
~~
2$
1
\\
ecr na
-s.eevt3r o.
<1s isimp
=--
i Z6 Y
I KC PAhtt4AeT-6EfrTd67
/d /3/'7 s
~~G~~~-
i
'~' 22 1
1
---' W W M ~jglGifgJ-_ A 7w s4 Mig.>__=
--y n
~~
~;,-----
=== )t/
21 1
ORF h- RS-ify M
to/9/
d'320s ***'K'tho___A'~4^ $ & w
~
~ ~ ~ ~
- Y n -' ^ ^ = -
~
y a,n u,-n-....a;7yr m.- m ui,,in
.~^ 'g =" weretur fsyds[oAw)- GMYttdYs(45WMRey
'~
~ w/az)7/
' - ~ ~ ~ ~
W fke*s- & CliWm~-
2V m' ffrfr7'~
- ~ ~ ~ ~ ' '
weasur" (stir #r' W w m aptzr 6
IFA 2 ~2 *3 Y "" =^4 LkL & $66Goedef & ffna fm s,/spfr/
B y4 fa,-
i i
{
Document Types:
Columns:
1 1.
Drawing 5.
Purchas Order 1.
Sequential Item Nimaber 2.
Specification 6.
Internal Memo 2.
Type of Dociment 3.
Procedure 7.
Letter 3.
Date of Document j
- 4. QA Manual 8.
Other (Specify-if necessary) 4.
Revision (If applicable)
\\
,l i
Dot.ket flo. 999looges inspector 7.H.Bs sck/#1 Report No. g p Q g.,,
Scope / Module.C.p_/ e* ) *J_g_ 9 p/hfr (,,/s*
DOCUMENTS EXAMINED
.'~~
~
j l!
t
~-
TIlLE/ SUBJECT 3
4 1
2 sasraor rm w w:>u== rdntmpfw;wy%&
sin 1Fi 36
, sasrnos/i~c~sf7t*43V~,~ Lamaign Ma*<asal~fsit,f=_ ~~'2^'~
~~ ~~
~&~P 2 ]iri ~ ~E' ' '~ ~
^^
nec 1zasco w 3 f-xf, c.;-==j-4 ~' M a a- *c-.
-....Ytt~
4/rf/tt--
2 2 A c, ro-scos
- Gas E Z E T E~E a' W G & & Pii M o 4 f d E W /k b Y / : = ~-~' = f " * ' ) f '}[][/
- ~ ~o
" * ~ T } nWA 38 5 Ksedssa' ~~ z/s a7ff ~ ^ ; : ~ ~' 1 iiifar d 7-n_d 2 W~fR & $ My*<-K 64-r-M X g/Ar7ff "~6 ~~~ i nonC ?Seitr meWasfk'~&
- E 5t't E Krlis's~ Yk " ' Y ~~
af,. so-m-** s4eeA*<- e Mw />m g~ K M1-f *~ ~~ 3-!09 xse <searofaC~EMiM'4m.4Gil as/sy/Vi~ ~
- b ~~ ~ ^
'ssoa.ift ~ em ei'~d6ynhiW/6K677 tar'~~ ~~kej z zf d " 'o' "~ ~ i m i tL_ a' ) je e-? 4 9 sdirie6 Y Y m m ~4~2" w + M s. - G ~~~ spff% ~~5 ^ ~ ~ ~ 9/r/fY T * ~ ~~ } Wof Osee-f F**s**stXWy GEsMERM5YRR*T ~ Y# ~~ gnrgros A mnraaes pC W~? = mm f CU2W-rm :-- _ - 'a~ l so 4 1 ~7&m ~e Glass. '1d--- $ Ner471 -2 2a4 > p ~ t 4 l i i l Document Types: Columns: i 1. Drawing 5. Purchas Order 1. Sequential Item Number 2. Specification 6. Internal Memo 2. Type of Document 3. Procedure 7. Letter 3. Date of Document
- 4. QA Manual 8.
Other (Specify-if necessary) 4. Revision (if applicable) t
~ PERSONS CONTACTED Company G6N6Rhl 6L60YRID Dates $/2@~$Af6.5 Docket / Report No. 9790040 $2-Inspector D. rHAr/)66RLAIr4 Page of I NAME(Please Print) TITI.E(Please Drint) ORGANT7ATf0N(Please Printi Tkap W9 m.e n 5'R EdGwCEg Mcdr rpo get_rD All Mia WiWik 6MA!WWL Ndi / PDo EP 41a Su Rescnc sa Eu m g NctiD Ed IvELes tn p e E ac,a/., Sef# m A/c u Poe xnm b /sms Semns r NC/IPDo Y 5 3 711 fDWARD MARM6RON6 SF6clA!.157 N c t. IO H D P,. u // Pr.-j m,- DPD - c i -,. r.,. a g R. A. CICLARLI.LI SENICR pro 1ECT ENGINE 6R DPD - Rn16R B6ND
PERSONS C3tTACTED ~ 5/29-9 N s3 Cacany (~ Std %% Cates Docket / Report No. 9'/*Iowo 3 Inscector DG 3/24(lX Pa9e i of l ' LAME (Please Print) TIT 1.E(Please Drinti ORGANTUTTONIDieese C*inti S' ?,.G y's co.,' .rs:, - o :, O :.' E* Sa ff 9I G.L. IQudm % eda &/ da/. %,. AAre"6.[ ' K Pc w k L e. />>. < - c.n L i a e:79 2E s r / / J.M. Cus.r Mee, Ons OHeRC /.*/' /.E~
- ?. ^? 4 'I '
. A u C / 7' & > C..T' /." C C'. 7 c /? - '. ;* ;',1 ' 'Q ' ., ' c.. - .i.. x..ota. y'*>'~ e F 2 o h u e.'- ! ' h E 4 4 ntr.t 2 - V k A*-3 A ~T / h JC. /1 r1 C o '. O 0 L l.~.- e p r a od W n T O f ? 4 _'L "~ kr /bNi?, c b'. r... l fn ( **/%' ,:,'hi)~f fr) // h / $/'0 / ./ G.k' Agosasen SW Bovcn s9+me i I I
PERSONS CONTACTED V29-9/2/8'3 GEM 6RAL ElfCTRIC Dates company O, C#Ary?86RLAINIMA 19900403/58-Inspector Docket / Report No. I Page l of d NAME(Please Print) TITI.E(Please Print) ORGANIZATION (Please Print) "I~K % l<h m,,,ca.6e45 WEso SVFisisaAa $.Genean Mc4to NMD 8 A G in sr em, c A i f10 G A t R. o J. M. C#st M u, axs o n.+ n o f T (/Rlsucit 51 dv4/2 de s'fo l hYs , % kw //h
- 4+$6 f&.u.%,sa.
Lshi..L -inn / T s Ef r-A tJK lhAcrot c emida=l? f)P 'L ! A W 'P H, S e A G2% v 8 J bL L L,; L.. H. n psm f P G TA P L E Rea Ma'c f.di L, sj:s cn J J 'Roseru Ad TecatU,r'-use.s' u psed A. 0. ~ A M C5 WNEOsN'% VhsEO. a s,n s ).c<-.., r 1. - s2 o CA C A M e2ced MG2 SA;2rv s um. Pac S i c. C J. LTL cmo o, m a s Pep w A u t g ve.sro kP LO d LnL<, b m %. E.b o A nesen u y i 4 i l e D l
Pcg3 cf PERSONS CONTACTED kih AO h NUP6Al Company: & ElecTMic. Inspector: Docket / Report No.: C u ePC Date: f[21//sf13 NAME TITLE ORGANIZATION (Please Print) (Please Print) (Please Print) N gad e s sx.sio Sr. digressar s~oyk,. f M/ Jew /sXe<.' \\ w A/ lsond1-- Pr%._h r t. WMP z - /. c; e+ ~' v (4.J. L le m a Pr > A.l L, CAS _.4 6ALRn smf GM sf en f te T.C. W o o D Perut' w at A9 Lou . wia cain er MPscb b b k %AY b/Vyi kt f k bD I E9 GI60 Ca.ECSR. OPSED 0 V, SotAW4L M.Alc.nre ft NikR h \\ 7,~4 A> 6- $K. Ewe R. /Li psEb l i beP 'a h 2 p el d.b. koh*p3 o's O"A 6-f5 8 A W ? $1 AC5 j5] N'] fopinjfosy / V > es.w.w me. x_ _.:2, ::s 'h M T PcPl d' W w rt< A. L.,A/2 u.c Ay 7e K. 30 eA % tes-PLM.T Pipn.7, avaLYut C. S. B ARRcid.i.y s An4f r6 Pu'/r Pipic; Amy.ur g t-\\ L the m Ag %.su, T k s b.) _.. < M.Q ~ d P!& Dy4'c h-L kL A in_MY l l l 6
PERSONS CCNTACTED o r,suaal Elac}me Dates th9 - 9 h /r3 Ccmpany Cocket/ Report No. Oopsedss/r3-61 Inspector 7 N[dskk/sy Page d of / 4AME(Please Print) TIT 1.E(Please Printi ORGANTIATION(Please Drinti G A 4 RO B A 5mMW Sr E $c FE AltoEnvs Cpec 1AL m7
- FBO Fh SHum QA/L pcGb AR Goacms ca aw.
vm l 4 g e
DERSCNS CCNT?,CTE]
- cmpany 66NERAL ELECTRIC ca es 9- /- 83 2ccket/Repor: No. 99700403 83-03 Inspector D. U S M 6fNl.AIh/
Pace ~~ of l Pre-Inspection Conference X Post-Inspection Conference 3ME(Please DM nt) TT 1.E(please o
- ti 09GANT?2-CN(o'=ase_2 9.L._
L D. (HAmbERLAIN RLACTOR ENG1NEER US NRC REG. tit UCRA@ h NGUYEAJ REACTOR ENCWEe/t US rdRC reg'DZ' 3AN1G. G.'"EGGAOY EFAr me Emiedp.t:# U S NR C. Ec GM - AT ia ac. v
- $ E A 25s I'
- 17. H. T %..;c x le 9 i<
ai a/ f f.: ?, :, a s.:/c - * .... m; c.:- .i-j'. w%r v n. &,: 4. " e..,........., ng, ~ i t:. Y. H' k)4L om M M J~tf. f*,Umi.u e,e n G d' N C > Z - /' P Q ..' k' 1*. w l.: 1 -._ n l gj.. 6 n g:09I /N A, & b,*- k b (Y\\
- $,- (~ ;x m ' r-
<* @ ~ G W*.kC I-L l" O i.* V' ( $4r {, r?
- /*-
- (,?}A & VfD t t b'.' thy Mw[ 2] ri:,'/*" Nd # 4* M$. b[- 4'[$[.h s %' O # ') "A,*- I t) M
- p1 I ( /, e j.p pQ..,/
I.* $O 1,
- '?**
8 $L kW //IctA h) lf.W W 7'22 A 1 L cse.O: H u,z de d P:x n c.p_e 2 t. w. - d w p.- w ns A /e <<,, 3 Vr /D ' c O C :' - t ',3 W R.1 ilALEMch. Ga Snp CA de J. J. TW;em,J L C% /ree1.,J,- cw -wesen 1.'c.. ! c - 5 r. m -, s, E a n. e c A Vii%. /1 e, dukt ps.,4 dra44 Ws 4 o 9
- [*dii*.
.!. A M ,,,,,", i, A.,,,,;.; ., e,. 't ! ' b {. ?r o. r s t a... '
- SO Us*
IvRC romw 700 U.S. NUCLEAR REGULATOaY COMMISSION l pa'%Ca.mset:* cam, e uEs. ee. ;,.. b-INSPECTOR'S REPORT Office of insoection and Enforcement ' '"* * '** ' D. G. 8RLA0X R. H&I)i&H R H, 68 t cRLEY P. 56AR5 l' 'a**5,a,p o* oce,,,,,,,,,,,,,,,ve,,,, i .r, ss.:: :..: vC =selivi% Don =0 isv eao0vCw ev.- g,o i :.. ' 66N6RAL 6L6(, Trit 20.
- I ' - *55" q ig s og mog! i ; i i V
w. 900i8v j I j i 8 l t i I t I I O - OtLt's i j j i 6,,' ; a. age'.*CE l l l l ; } l ! j .. hs ,,1 i
- tai 00 08 inv tstigatio%vm setCtio%
.gsett' cm et**cewsc ev CnGam 2A' ON (. :t 08 st0 cs..c.,::s:..- 4C act v.tv ssee tw; vg. Paow to ,( i. st 310N AL C88'Cl s ta.s jct >(a ,g. w,,,,y,,,,y,,eg:: r f, e Wo. O!.T } Va. WO Cav \\ va 3. ags@ggtigsegCtCa DL CN ~~ I' D w.- ~ dl$ 2RISl3ldlO Cl2.! fi.3 3 't'80**a%C8 a'aaa's*6.v 4v /r-b 3B l 38 3t l 32 l 33 3a ,g D t aIQiONa6 Act'ON 'V 't O' 'C' V G N 0
- Cit 3 ' ;* ** * **' '* * **
'C'*"***"*" les.sasavv os. wowt v s.t ic. stA%t s ec. 4 sc. i. i. =ac ronu ssi i ca.. ::::: ? [ or. sencia6 it. wvist. vie os. ve= Con C in sweva%t,tsecat s. sv ts-cat > s _; g 3. neoC546cesicettttaa ~")o..svencevest 4 ~1 os - vovt au0 9 es. war acct G is..v co l = n. .% mag.y gg;pa py,ou sa ..,v,ves. i so:.: vie Co ui. %ci as.co ::stn a m ,g i. n M,~.a w ~.,3.. 4l0.Cl0 C' v 0.A' Ocss : ssas at63 ~N8 0* Va t'CN Ogv A* g g,e,., g,. . g e;.. g ;.,. t CLlaa 'I I 'E *$ #I* i 3.- VCLAfC4 '.t"t # 'l l.C 3 a.* C d' ii
- 3. Qtv'af 04 a i e i C 3
a e'C 0 AI S !C 3! wo i Da,. ve v0
- Ae re i
l j 4 = WCt,AtCm & DtyiAtCM g,gj j i t. vts , j g i. vst jgg }j{3 ,s. j w.,, n 4c. 4. ,,js: i WCOWtt '%f CovaCN wec.tt Necev.'c%
- ts oo0ut uo.. ~s, i
io,hy i :: u i.io...te %.
- ti
.e0vti wo.. ss. ! t I c.... :.:..:,... I !o,h.,.5 B5 l.e I~ ', e ' F., I. I S e a:. !. x,e e z s:t e g e:: v 's : ;. i 3 c. a F s = 3 1 s i nr x a.j s c .n =11
- O
- P l p=,.;5.
t - s s p;o. 23: e:
- sic ci3 ;' i s :i t
M2 9t2l7,0t2lS!'l 0,M,,l!l! l,,I ofMA S Ol d,3'5 8 I 1 4I l 0 i,,_L] l 8 ! I t !,t ! t t t l t i t i, i 1 i t t t, I l t t, C , 9 j 0 !e I I,,' t 10 , t s ! Al 2 9,217,0,518d 0,7, l l,, II,!,,! .I, !,, ! i,,,l,,Ii t I t i t I ! t, t ! i t E I 'I t t t I i , t t li,l OI l 1 t t ! t t t t 42 9.217,0,418 9 045,, i l i. I,, I I,, I H !,, i.,1 -!,i..i a i W !!',I,,1 it i,, : i,.t I l,,i!',i,,l
- Il,,i,,
t l 83 l,,lli !,,l 2! ' I, , i ! d2 3,ol7,0,3!B!d oil,0',, ! I I,I I i , I,,Iii,,i,,,_i i,.'.. - l,, t t t t t , f cl i I ! lI l
- l i
lt ,lt t I, t i t t ' t 4 . t sCL(if 09 %Cf '8
weso m A. xcxiw o..,,,caues sg at.ou vocat wwav i y' '['g 40 (tv **CowCDtt3a getsi 2hM h@jl ho SEQ INSPECTOR'S REPORT 4 4 4lolo 410 3 Ii F 3td M vo'a' c~ u"~' ca t s* ;' c m,,g 5, a ,l . l, il (Continuation) I I i iI ) 3 a c-Offica of Inspection and Enforcement 'ii '( i c j % Do[ t6 i iii i = x-v,ou v. o osmio, w.m.,.mo -,=,.r. .,.ua .e,a....u a,a,. ~-,., au.u.y .,..~n.4 ,,. a.a.,u,.,,..,a. 9 C\\lTR s. 3 I' htm t, M' 5 l,M- [6"1ha6Do.nye..m d4/& ?! 2 J s.s'.., g ?"'u.~"mn Ne>?t l~~. o .t DRzriJ an(gnp) s.g _ j n I^ A' l 1' .l 'M m' ~~M.7,; I i AS" $N.
- i,y) es pg$. ?ll'g j"'7D'Mla wL,
,\\ ,"M k,; ,z,
- c. I 1L t3
,4 it l I ,,. l ,. I ,, l ,I 31 1 U 33 l 1\\ l . 79 as to .I ,. I i =, uh ,. I 6! 1 oI
inc roam MS A ie si o. u E EPoM WCDAE %wSE A oOCXEt N,o il egCri o s e,C..E.NSE
- ,,, gg7,ggg j';;'.
=ois==oo ,0. INSPECTOR'S REPORT '? '4 4 !OIC '4!013 ! I i g' 3 oisi a ,l,1,!,j,j,;c eu o c:ne~:,,sp,','. ~ i i i .I 't a (Continuation) 'J j, ; j j i {i _i g Offico of inspection and Enforcement - ' ! 'i i i i i t i i 'c ' i ii IiIo m i, v ur s o. ..r.~,,,,.,.,,,,. ~,-,.,,,,,.-e.,.-,,.....,.-.,..,~...,.......,, ..,,,,,...t i. 6\\/TR z 0,Lnn% %v$d 5J % D had Ylh. N6Do-ll2@-00 s\\ lutd K.9IJ N604Non'k d "J A v.G w n%l mP '5.07 CF' J),2 s2 chd t/L)- SwAA k, i n% l G2d Gwhi') b,d (cnD +.Ju~ Sw.r.: o u : L ib r,F nr b':/ c,3J J su.d XL IFU =P Fu s MA nn, r.9~A nn-Jclib 49 A-u eda 3 c7)n ~ I k (Rmi iit2 5 4 %. X" neLJK a,c! i "A 'ni a rk A ) ors n h's swM worA Tif J,) \\ , l, s4 trJLw t,-2'd e L5 d in,%)J e 's 19i l 't i ,,.I 't
- o l I
21 't. u; I 24 1 71 24 ,,I l 6 n i n. It ui I n i 34 30 l 6 O 1 1
senc ec.u as A ~ r me.or woouta=vveta one,,,,e,,,lc.,on uerusa f %o.isv'aoo ruis a.o.isi ,1 g,1 g,qig,7tgtgtg n INSPECTOR'S REPORT 9 9!@ d'o!8 019 513 0 Si a vo a c~ ia,na' c= :sge s,gp,. ,l: ,l, (Continuation) I i i i i
- 3 i I :;
Offico of Inspection and Enforcement I I I c j Q [e o[- i , uvio v r ,.e. u,,,,,,, 6VTR 3. 1 lu ? c.oM Fowan c es : g,g 5 ) Q fggf g, s, goo:;;ygq. p o &. cow 7tLAP.Y ro c4V%. ^. :, 'I k
- q p L n S 7:
i w wc s c o~ )' A4..fF SECT #od JAf.I er M /) m ory A To Gr E To;S 6 5-2.10, j. ; 7 ' N ldkf C/kO CLA M PS 89 L,4 f? OL l'C..O. "$ Y 68 o tJ /\\ L(,. " P F. C/s jl.? - f, i s. 'htlChl &N' W C 0- C C GA$% h~ t.2 IS,* % HON C $ $ C.M ** h*C Com StN CN~C W lhet-'3 L,L T' A S( t,) fE A rd C E., "i '. ' /\\? 8'A I L L,i t?. E WOLtL.D tv c '" C / h> '. C. Av LOSb 0 5. 7 L an* W T E G /7., *T** OC T'.Mt [2.EA CTo IC. d' co L /mJ n. ~' 12. Y b t C 5 V rt s '7 0 t t s c A n y, '3 l .. I 1 ,.. I f 17. I to is l =I
- 21. l 22.
l 23. i 3e H ,e I ,,i 28 al n ~ 11 IT i w l 2, ! 6 6 t - -.. -. -, ~. - -... - - -. - -. - - -,
,,e,,,,,,,, ,,,oa uc.=,sa ,,,,, y,4,'y, 7, g g) (**o27
- cow t av"*ta Nee soamm a.
g'Q',,, acaevnace em us.en. ,o INSPECTOR'S REPORT 9 'l 4 0 OIA 0.3 Si 3 o'3t a 6 c'a' case o
- =:t...:~>,,s ;;g I
.l. in (Continuation) 3 Office of Inspection and Enforcement l { Ji:'[' c i ...a 1,.. ~,,, 1,,,,,,,, 1. CUTR 1 ^ z ' 3-L.14 s.J.%e< cJ faal fle. se>d'll2o9 og A i+ ls (1.)'CoyntekM i ~.:%I-s---tfr n eacwo.< h te w u ic., a u i t . Ano s e c. n en) za 7* I cr se p,w e o u.a u v Asru n e, ~ cc I
- kNNANA, 05 Of Q %*CY ('L'\\,v'M *)s] t CAQ N'
$*Q I e' r . S A iA./ wwA-r m% c,rt.o -c e rs: surgueo ey 10 r.1 Cr'6 We-ft.t No rJ GS)c^.s*Tt5L. c 0 M f o n c ru't"S A-N C., ,;) ' I io. _W # ' W CAGi.i.O NCv Ib C. 'u&C O $r5 N 5 M *" - 6 11. I $ U.'N liv,'; O ' ~r t w 5 iG R C.= A N A LY 3 t's CC 'WC l q N9 @ ' # s'A/ 6 S Y S7",;r ', v ,3. t.. l ,, i ... I 17. ,, I 20. 21. al I np i 3 nl ,,. I .I .I 3e l I 3, al sI I ,i 61 -l
7,C,'** * **
- aEPo t ScouthuweEa oo.e.o i., is mi.i c.a. uc.e,,n,se nst...coac1, ggo,y,,
ec INSPECTOR'S REPORT 910 o to lo W ol3 g 3lo vaaro~sa.i= c m p.a ;5 e n a (Continuation) l l e ' k-lN-Offl20 cf Inspection and Enforcement, I I c tI o U -1 JE veur,on o. oeure, anw on m anco enereews w enen no.n. or une rest eacms unos namoor. ** -m ee necmerv e onrooniese s =>< o nee w so enerecters eacn, 0 VTE t-l Contrar.y to the requirements of Section 5 of Topical Report No. NEDO-11209-04A and Parascaph 4. 2. c. 3' o f Engineerins Operatine Procedure (EOP) 42-10.00, "Desi-sn Record Fil es, ** (DRF) dated June 23e '1980, a DRF Index (Form SD-006) or equivalent was not ' established and/or maintained for DRFs No. A00-1160 (SAFER 01) and A1002 (GES*fR08: as fo ! ) ows: A00-1160-the date entered and author's name were missins' a.
- b. A002-the date entered was missins.
21 sI 5I l
- 5. l 2
l i si l 3 4 ,i i Il-i e# ) l s I I i i I i i
g' enc eow m A ooexer so,,,5c,,nia...rws: n o::ve ' E W, WoDAE WMBE4 1sy =o <ennoo i ,o ,,,,. gg g g,q INSPECTOR'S REPORT 9!919!olole/lol? I I ! 8151o 2 a ~ ' c es u 7 m. :,, y c ;,,s;E,,. ,}3 ge (Continuation) i i l e ' !+ c , lj j ; j Qp:[ Offica of Inspection and Enforcement-i l II n voaron on oemren werer un ra seco cnerators ror een nom a ree rut usua ns numur. a -.a u noenury to urnonene uma s.nu oc so ene,urees our,, I. CVIA t 3. Contrary to the requirements of Section 5 of Topical Report No. NEDO-11209-04A and parasraph S.3.2 of Suppiement A dated Ausust { 1e
- 1W9, to EOP 42-1 00,
" Introduction-Technolosy and Desien Co,ntrole" ma t heina t ica l analysis contained in Section 8 of DRF No. A00-1160 was not prepared and documented so that a technically qualified persco could review *and evaluate its accuracy without . recour'se to the crisinator e.g. the identification of the
- Purpose, references, orisinator, reviewere date etc.
were missins.
- 11. l 1L l 13 14.
s.I ,. I
- 17. l
,.. I ,,. i 20. 2,. I al mi 24. 3 28 11 l al i w! si ! I n. 33 ,, 1 bl e!
l = I ' macm=M apont vocas ~uwesa ooe.g,,e,, i m a..e..,,, ,, v.' gig,,, nois*enco =o-I sea. 2i9 IZ 17 'o !4 Ie ~ INSPECTOR'S REPORT 9191o b b Wid 3 EGl olz <**ncs<i=':acorc'., ;,g a ,l.
- y. :j (Continuation) 3 g
y _ja [ Office of Inspection and Enforcement c =rio rio .mm a .-,u..,,,,,,,,,,,., 1 i C.VTR t 1 Contrary to the requirements of Section 5 of Topical Report No. NEDO-11209-04A and Supplement A (Pa9e 12) dated Au9ust 1,
- 1979, to EDP 42-1 00 which desisnates a Functional Specification as a
desisn document subject to the requirements of EOP 42-6.10, "Ensineerins Document Issue and Application," ; the Functional . Si=eci fica t ion for SAFER 01 was not controlled in accordance with ECP 42-6 10 e.e. a) no id+ntifyins number, b) no revision numb +r. c). identification ai,d sisnatures of crisinator, revie93+re. and approver were missine +tc. ,1I m t ,6. ~ it l ,I .l i a i 31 21l t i n, 2 s. 5 to I U i nl l i t nI I m ,, l ,I =l ,l ,i 4i j el U.S. NUCLEAR REGULATORY COMMISSICN
Docket No. 99900403/84-01 g Q% ./[lll f COA General Electric Company Nuclear Energy Business Operations Attn: Mr. W. H.'Bruggeman Vice President & General Manager 175 Curtner Avenue San Jose, Ca. 95125 Gentlemen: This refers to the inspection conducted by Mr. P. M. Sears of.this office on March 12-16, 1984, of your facility at San Jose, California, and to the discussions of our findings with Mr. J. J. Fox and members of your staff at the conclusion of the inspection. The purpose of this inspection was to review the status of previous inspection findings, preloaded pipe clamp applications, and QA requirement / implementation in relation to certain piping supplied to Hatch, Units 1 and 2. Areas examined during the inspection and our findings are discussed in the enclosed report. Within these areas, the inspection consisted of an examination of procedures and representative records, interviews with personnel, and observations by the inspector. During the inspection it was found that the implementation of your QA program failed to meet certain NRC requirements. The specific findings and references to the pertinent requirements-are identified in the enclosures to this letter. Please provide us within 30 days from the date of this letter a written statement containing: (1) a description of steps that have been or will be taken to correct these items; (2) a description of steps that have been or will be taken to prevent recurrence; and (3) the dates your corrective actions and preventive measures were or will be completed. Consideration may be given to extending your response time for good cause shown. The response requested by this letter is not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511. i i RSShh ASC:RSS BC:VPB PMSears/jj C, yHale UPotapovs y/t)/84 bip/84 + /n /84 C Z 3522G326 64G430 PDR GA999 ENVCENE 99900403 PDR \\
General Electric Company In accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter and the enclosed inspection report will be placed in the NRC's Public Document Room. If this report contains any information that f .you believe to be exempt from disclosure under 10 CFR 9.5(a)(4).it is necessary that you.(a) notify this office by telephone within 10 days from the date of this letter of your intention to file a request for withholding; and (b) submit within 25 days from the date of this letter a written applica-tion to this office to withhold such information. If your receipt _of this letter has been delayed such that less than 7 days are available for your i review, please notify this office promptly so that a new due date may be established. Consistent with Section 2.790(b)(1), any such application must be accompanied by an affidavit executed by the owner of the. information which identifies the document or part sought to be withheld, and which contains a full statement of the reasons on the basis which it is claimed that the information should be withheld from public disclosure. This section further requires the statement to address with specificity the considerations listed in 10 CFR 2.790(b)(4). The information sought to be withheld shall be incorporated as far as possible into a separate part of the affidavit. If ) we do not hear from you in this regard within the specified periods noted above, the report will be placed in the Public Document Room. I Should you have any questions concerning this inspection, we will be pleased to discuss them with you. l Sincerely, c'ened 12 l ..a g.
- 9. a. n.. -
Uldis Potapovs, Chief Vendor Program Branch Division of Quality Assurance, Safeguards, and Inspection Programs 1
Enclosures:
- 1. Appendix A - Notice of Nonconformance
- 2. Appendix B - Inspection Report No. 99900403/84-01
- 3. Appendix C - Inspection Data Sheets (6 pages) bec:
JNGrace, IE JGPartlow, IE MIS Section (J. Perry) VPB Branch Chief VPB Section Chiefs VPB Inspector DMB-IE:09 i l
APPENDIX A General Electric Company Nuclear Energy Business Operations Docket No. 99900403/84-01 NOTICE OF NONCONFORMANCE Based on the results of an NRC inspection conducted on March 12-16, 1984, it appears that certain of your activities were not conducted in accordance with NRC requirements. Section 9 of GE Topical Report NED0-11209-04A, Revision 4, states, in part, " Procedures and practices are established and documented to provide assurances that special processes... are accomplished under controlled conditions. These special processes are accomplished in accordance with applicable codes, standards, regulations, specifications, design criteria, and other special requirements, using qualified personnel, and equipment." Contrary to the above, GE did not assure that pipe bending done at a vendor's facility was accomplished by qualified personnel nor did GE assure that the pipe bending was accomplished using a qualified procedure for the bend rate, heating, and annealing. l M 40522 m 40430_ PDR GA999 EMV0ENEPDR 99900403
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION INSPECTION NO.: 99900403/84-01 DATE(S): 3/12-16/84 ON-SITE HOURS: 56 CORRESPONDENCE ADDRESS: General Electric Company Nuclear Energy Business Operations ATTN: W. H. Bruggeman, Vice President & General Manager 175 Curtner Avenue San Jose, California 95125 ORGANIZATIONAL CONTACT: Mr. J. J. Fox, Senior Program Manager TELEPHONE NUMBER: (408) 925-6538 PRINCIPAL PRODUCT: Nuclear steam system supplier. NUCLEAR INDUSTRY ACTIVITY: General Electric Company (GE), Nuclear Energy Business Operations (NEBO), has a work force of aproximately 1,000 people with approximately 98 percent of that force devoted to domestic nuclear activity. NEB 0 currently has 26 reactor units under construction and 2 units under contract. NEB 0 has approximately 125 service contracts with various clients. ASSIGNED INSPECTOR: T.E-w 8//u,/pc/ P. Sears, Reactor Systems Section (RSS) Date OTHER INSPECTOR (S): D. G. Breaux, RSS Server Sadik, EG&G, Idaho APPROVED BY: h Rs C. A Jale, Acting Chief, RSS Date INSPECTION BASES AND SCOPE: A. BASE'S: GE topical report No. NEDO-11209-04A and 10 CFR Part 21. 1 B. SCOPE: Status of previous inspection findings, review preloaded pipe clamp applications, and review of QA requirements / implementation in relation to certain piping supplied to Hatch, Units 1 and 2. PLANT SITE APPLICABILITY: Hatch, Units 1 and 2 (50-321 and 50-366), Limerick, Units 1 and 2 (50-352 and 50-353), Nine Mile, Unit 2 (50-410) _ _ _... ne mmt um.ml"uAC vaa.v-c,o m oa n o ac PDR OA999 EMVGENE l 99900403 PDR 1
ORGAN 8ZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.: 99900403/84-01 l RESULTS: PAGE 2 of 7 A. VIOLATIONS: None B. NONCONFORMANCES: Contrary to Section 9 of GE Topical Report NEDO-11209-04A, Revision 4 GE did not assure that pipe bending done at a vendor's facility was accomplished by qualified personnel nor did GE assure that the pipe bending was accomplished using a qualified procedure for the pipe bend rate, heating, and annealing. C. UNRESOLVED ITEMS: 1. GE's remedial actions concerning crack / indications in replacement recirculation piping shipped to the Hatch nuclear power plant were reviewed. GE reported that fourteen 12" risers were penetrant tested at Hatch by GE personnel after receipt and were determined to have indications. These risers had been tested using a die penetrant examination and were passed at a GE subcontractor's facility. GE's remedial actions on this item have not been completed and those actions will be reviewed during a future inspection. 2. Representative samples of preloaded (stiff) pipe clamp applications were selected for analysis as to their effects on piping. That analysis will be done by an NRC consultant. The stresses induced in the pipe by the clamp will be calculated. Those stresses will include thermal, preload, and dynamic stresses in areas in the pipe under or near the clamps. The object of the analysis is to determine if the total stresses are within ASME code allowables. The results of this analysis will be included in a future inspection report.
ORGANIZATION: GENERAL ELECTRZC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.: 99900403/84-01 RESULTS: PAGE 3 of 7 D. STATUS OF PREVIOUS INSPECTION FINDINGS: 1. (Closed) Nonconformance (83-03):. Control rod drive (CRD) clamps supplied by GE on all BWR-6 plants were classified as nonessential components. As noted in GE design specifications for hydraulic lines (21 A 8845), GE does not have design responsibility for the CRD hydraulic lines. A part of the lines is manufactured by GE and shipped to the site. Clamps are provided by GE to support the lines during shipment and subsequent construction. GE has advised all Architect Engineers (AEs) and customers that any postulated failure of the clamps must be evaluated by the owner /AE. GE also advised the owners /AEs that in their opinion the clamps could provide support up to the limits specified on the interface control drawings. 2. (Closed) Nonconformance (83-03): GE did not communicate needed design information to Stone & Webster (S&W) that CRD clamps were nonessential components. When GE became aware that certain owners /AEs had interpreted that the CRD clamps were essential, they notified all customers /AEs that the clamps were noncode and nonessential. 3. (Closed) Nonconformance (83-03): Design verifications of Nuclear Control and Instrumentation Division design documents are being deferred without controlling procedural requirements being implemented. GE has initiated an action plan to review all documents listed in the Engineering Information System (EIS) to assure that current verification status is correct. The inspector also reviewed customer notification of design documents currently in deferred verification status as required by Engineering Operating Procedure (EOP) 42-600. GE Quality Assurance and Reliability Operation (QA&RO) conducted an internal audit of the implementation and effectiveness of the deferred verification control systems. This audit resulted in two corrective action reports (CARS). As of this inspection, one CAR is still open.
ORGAN 8ZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.: 99900403/84-01 RESULTS: PAGE 4 of 7 4. (Closed) Nonconformance (83-03): Receiving accepted purchased equipment that did not conform to the procurement document. The inspector reviewed E0P 6.10 " Supplier Charge Request," Revision 1, dated December 16, 1982. This allows the supplier to formally submit exceptions to purchase order requirements. QA conducted an audit of purchases similar to the Rosemount 1152 transmitter to assure that the supplier complied with the IEEE qualification requirements specified in the purchase orders. The audit resulted in no further examples of receiving and accepting purchased equipment that did not conform to the procurement document. 5. (Closed) Nonconformance (83-03): Desing Record File (DRF) indexes or equivalent were not established and/or maintained for DRF Nos. AD0-1160 and A1002. The NRC inspector verified that all committed corrective actions had been taken. 6. (Closed) Nonconformance (83-03): Mathematical analyses were not prepared and documented so that a technically qualified person could review and evaluate their accuracy without recourse to the originator. The inspector verified that additional information was added to the analyses as committed by GE. A letter was also sent to all responsible engineers to remind them of procedural requirements pertaining to generation of analyses. 7. (Closed) Nonconformance (83-03): Functional specifications were not controlled in accordance with procedures. The inspector verified that committed corrective action had been done. The inspector reviewed the revision to E0P 40-3.00, " Engineering Computer Programs" (ECPs). The revision includes more specific controls for ECP specifications. 8. (Closed) Nonconformance (83-04): Design change documentation was not initiated for approved Field Deviation Disposition Request (FDDR) HH1-1467. The inspector verified that all committed actions in response to this nonconformance had been taken. The design change documentation has been initiated as part of a larger design change package. The change is scheduled for completion by June 8, 1984.
) ORGANIZATION: GENERAL ELECTRIC. COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA f REPORT INSPECTION NO.: 99900403/84-01 RESULTS: PAGE 5 of 7 9. (Closed) Nonconformance (84-04): Engineering services failed to process an FDDR into the EIS data base to reflect field implemented design changes. QA&R0 conducted an internal audit of the adequacy of the FDDR system. Audit findings relating to this area have not been finalized as of this inspection. The current EIS data base reflects the field implemented design changes authorized by the referenced FDDR in the i nonconformance. The NRC inspector reviewed the revision to procedures which will aid in preventing this type of nonconformance from occurring. E. _0THER FINDINGS OR COMMENTS: 1. Replacement of Recirculation Pipino Risers On or about March 3, 1984, the Hatch plant received 14 12" piping risers. It was reported by GE that these risers were then inspected by first being surface smoothed by flapper sanding and then penetrant inspected. All showed some indications (microfissures). Their manufacture was described by GE as follows: a. Plate, fabricated by ARMCO in its Florida facility, was rolled into tube forms and welded. The ARMCO facility has a code certification and was audited by GE in April 1983 and put on the approved vendor list. b. The pipe was shipped to the Johnson Controls, Clearfield, Utah, facility for bending by a special machine designed and made in Holland. The process involved induction heating and bending of the pipe. Preliminary inspection (die penetrant) was performed on the risers. It was reported by GE that the bending of some of the risers was observed by GE metallurgists and QA personnel and a representative from Hatch. (The Clearfield facility is not code certified.) c. The risers were then shipped to Johnson Controls' Compton facility, which has a code certification to be inspected and NPT stamped. The inspection consisted of die penetrant examination. i
ORGANIZATION: GENERAL ELECTRIC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.: 99900403/84-01 RESULTS: PAGE 6 of 7 Review of purchase documents and specification referenced therein show the following: (1) no specific qualifications for the personnel operating the bending machine were required by GE, and (2) no specific bending, heating, or annealing rates were required by GE. The nonconformance in B. above was identified in this area of the inspection. Further inspection in this area is necessary. Information yet to be obtained includes: a. Are the heating, bending, and annealing processes being accomplished at the Clearfield facility considered by GE to be a special process in the context of 10 CFR Part 50, Appendix B; b. Are the exemptions to N8 4213 provided by the ASME Code for Austenitic stainless steels applicable; c. The basis or criteria used by GE in classifying " cracks," " indications," and "microfissures" and the significance of the latter; and d. A review of the revised process to be implemented at the Clearfield facility. 2. Specialized " Stiff" Pipe Ciamps As noted in IE Information Notice No. 83-80, it has become apparent that certain loadings induced by specialized " stiff" pipe clamps can result in significant localized stresses in the piping that should be considered in the piping design. In developing these stiff pipe clamps, clamp vendors have incorporated several innovative design concepts that can detract from the piping integrity when they are not properly considered by piping designers. GE has specified in several of its designs, stiff clamps. These clamps require, during installation, a preloading of the clamp bolts I to achieve the desired stiffness properties and to prevent the clamp from lifting off the piping during design load application. The bolt preload value is determined analytically by the clamp vendors and its magnitude is extremely large. The clamp vendors have qualified the clamp stresses only and no evaluation of the effect on the piping stresses has been made by clamp vendors or by GE. i l L
ORGANIZATION: GENERAL ELECTRlC COMPANY NUCLEAR ENERGY BUSINESS OPERATIONS SAN JOSE, CALIFORNIA REPORT INSPECTION NO.: 99900403/84-01 RESULTS: PAGE 7 of 7 Representative samples of stiff pipe clamp applications were selected for analysis of their effects on piping. That analysis will be done by an NRC consultant. The stresses induced by the pipe clamp will be calculated. Those stresses will include thermal, preload, and dynamic stresses in areas in the pipe under or near the clamps., The object of the analysis is to determine if the total stresses are within ASME code allowables. The results of this analysis and the effect on GE designs will be included in the scope of a future inspection. ) 1
i Dotte.T do. (TToO( 03hY-ol It4sPECToR M bEA9S I I StoPE DOCOtiEt4TS EX AMIN ED REroRT tio. TI. - Of PnGE l 05: 1 ('*" 'M&y
- g" sist.
pnts TtfLE / sob.McT 7[z4/gl PO Ib E SNSVEMS To R C LAMP [0RCtiA P. O. 2.os - x.J(#3 o 't> [34 t4EMo c. otic.t.Erds40 C. L A ti? 14DOcE0.STEESRs 2 id d H[C. MI i wi 3 6b./E 1- ?E C i E C. Loot > 5 0 G PE d.S to d U ST E N hl M E._. M i c E '5 DwIC 'IUT E.~712- ~7 s4T 2 4 DcAJG %m 2 2 ~1 G/'l/% 2 R.E cwac. t_ooP % O '> PEdGo ^3 WTEM __hb.cJg ,H it E,, i sip z 2 2/st /sc Rec _tec.. Loop Pt Pt <d G --6 Doj c ocu zw Pacu Rc_ tooP S'Ti?CS S P,E Pr> RT L S E. StAGsn. O H AR. i% ~1 SPEC. Diao731 io 's. -D E
- J W S T E H s HT L.
5PEc si nv ^ g2 ts DWC 16 778 a ,- $_SVGTEids C.L A M 'P /\\ Ste. M_h LY .i E SYSTE H S C.L A,M P AGSE M IS LT. 4 DWG iG ~#~7 S+ s,[gr,I gi P @ E. C L.AKD D4STAL LATiDk Io Dtd G I 9 St. A At(81 E. %4 STE ys vou 41 \\ ' l'4 8" pip e. srmm PE Fo(2T PERRY Li SR 2tMi ss M4T 2 8' 12 Otd C, 79s e44 3 1_ 6 l3 f 60 Mnid syeAel PiPr Coc:Peccio e _L_ Dah wi c asr 4-io /3/p Re_c.i rac. L no n c oe. ee cd su ed a ac .z. m n e id. LTs C66 33$1 Gf24k3 DRL Yo C M ii L MoTi W tdG THAT Liu q
- 6..n 2 Ee,Poea<iBt_6 f o E.
JO',T I F Ys td G C L AMi's F o? Ei'Ptic A Tio d TYPE OF DOC; DWG-DRnWING LT R - (:ETTF P. st LM, R.E POR T stet-spectricnvion! -s R _ - j reo-proce.Diset p, qh nnwoAL i, QCD - f)t DOCUMEtsT ]
t INSPECTOR DOCKET NO. St. OPE DocOMENTS EX AMIN ED REroR.T t10. PRG E. 05: T $$$gy
- g wr asv.
pesvE TtTLE /suBMcT Mff.T Cc (T L.T R o2.igH.cw0 t h [33 pied T o r Rp M S11m4 SAtoc AS Doc JHCMT s f _, _ _ _, _ gb Spec. 2.t A S% M l 6fi9l'Ib D C. S L 6a d SPE.C 14 Y DCAUltc t i tdE.S CRb et[g 3 p g <re,- Pipi d G s poo e pa ge7o e g,c c. a c. ws 17 Dd itz.03 p p i 4 lo f =t[S3 i' 18 DuJG t i 2. D TZ.7o o Vf2(,lB P o. r_o v 2 24rJ G P 02c (4 A 96 OF 2 512.2. Q@o LS., _.,,, I 'l PC> To4 YE '7G G O was A suc. v,e. c c_ + u s e. a re %,..as-men ea ^dte PO. Ee", k.10 (- D i2[i9[E3 ?o _ P e fiseo.d C. vkp., M., red O E e. scEM T PcdATEAof [NSP.:. ,, o F W t s L O. -5Pe>otS liflo(E3 '$ pdc tv i?. bd STE d (T a c. f,T As tat._E.5% STe EL. P P O G,,,,__(.G %,,1,_ [k S PG C. 2 3 Al b7 6 2. ( do_(tedMM.,CAtLTh / ~1'L' S p e c. Sfpo 2ot 2-9 i '11 ' G Pt (.. F 0 P. L t ca. PE.46 Ti2 ACT IMSPE cT soe4 2.3 d R. ASSC;C e #\\TE13 PiPidG k'. E OG.Ifd C G.2 i N G dd DJ_I ~O?QC.6 d h._3 24
- 1. N M 36 M H0i?R AV k'KLG3 To SHe.e toco D c o ac o R ed vedG P_RC...qd. _ _
MtC.;203:L6SO RiedG Id B I C. M O C LE A52 C.E Ai36 pip,sedf v er sr 2.6 SPU.c. 93o g. (,4 -l l il '60 D I26V.To P '2.oc CD tJ2 tf c.o ve.e i ed G HF6.oF Rtsa2 SPoo.LS........_ TYPE OF DOC; ETTER. - T R - 1.At/ s7 t r 12Ec c,i2:3 FILt.:. DWG - DRAWING SPEC-SPEctFIC ATaod i2 PRO-ProcEDO RE GAH-QAHANOAL dco - q c oeconswr
f INSPECTOR R S c A rc? s oocear 90. 4 W o o J o :s SccPE DOCOMEt4TS EXAMidED REronJ He. Ed -o/ PnGE 3 OF Ak*" NMgy
- 7r asV.
Oma Ttn.E / sos.McT w 71 FtLG G O PPU E. e Fit E Fce e A R M_c.c; sgg e _Q se..z Pgel l TYPE OF DOC; DWG-DRAWING LT R - 1.ETTE R. SPEt-SPEct FIC ATeok! peo-ProcEOostE. j Att, g h H A*3 0 A L. I D - O C DOCUMEDIY
- n. - 6esersensw n onro
INSPECTOR Ob6IOk DotkET do. @900403/F40/ StoPE Doct)t4ENTS EX AMirJ ED REroRT t40. fM - O/ p n s e. / o s: 2__ T M fqlgy *g" nat. Onts Tsit.E / sos,)incT Cw,.noT T-4 4 2-C co b 12 /3/10 Tune en uDG rJT__.hti&da t) Mft_lf:1 f. ATJ 0Q _. o osRoFicAT!& [3.x2t_5_) ?- t3 E-Jo/,h3 hvD T oP A'FF t.s2ED onsec,o 3 t.T(? 9/z1/9) 3E,CC-PRCiO tJE-f 2 : F o C.A T I Oh. Y hoc, t ;~ Q 2'81 5 Ill:. h3 AuDir af D r.=rutw-b DFhisA/ \\/ttJ2t CA7eod 5 0.s om god 42 -4.m n ' /t /M (o ya u ca4 i2 !G Q oA t. iT4 p %%> R aut 2 M mA L.GT'it'R-- _L7 f th.T 'i>J I DewmD UceoFocA1 od coReEcT've Acroon) I 6 , d-e:'ltsl83 1mu s u s.)oleFtCA Ttor.) OP._bg FFG s2G.O._.lfS2rF r CWLO e(9/s4 Te caowg -mw.en uvsrec., oikoirrious ,o Worecr s ys w s.. w.t._. i '3 a e. IU PEcc. b. Tep 4t e,.o I iki;/ft. L oft.i'* P C H bi%'i PMQC-M 99.0 f.-of*4t!.-6.ao 1 il[s/W3 Dt-0t ATion) DISPONTsoed ModtSI 19DM 5094L EEs l f_TV 1!<*o/S$ Q v A:.u T Y 2 + J khtr) oF SJffLIGR ChurcilHAnw To ve60 Ro ReysteM6+5TS. .j l b II /t[83 9 %iueG#ioco Dcv_utas,et i W 3 G: AOD APPt ji',ATrod hO '~ P 4 7-6.lO .o ALO GoP 47. 2,.o3 i Mh2[L rJ tX,t Ow n gusa ( otAFu'1elt_ pstoe gA,ys TYPE OF DOC; DWG - DensitNG LT R. - 1.ETTER. SPEC-SPEttFIC ATio*I PRO-PROCEDURE i net qh tinssont- .CD-p,D E {,,- n
i t j i i i l l I l l f I i l l j + l l q@ i l' I c s l O Dd l T I Ct-o-y u. ,e o O7. d2 DW i U f,. @ O Of g oW M !b S 2 9% O C b Q S E e 3 e E R O G u. ul N o Q
- Z w
{ d d 1 e F N k 5 4 3 tu p LL 9 2 O h! w C I E d 3 o s U N k C ~.- O s' c0 W g ? 4, k )*8 4, W g e 'l II at D M $3 8 5 z
- 2 l'1 1p l
kg.J 3 O A .{ g. EWC W eUpoZ 8 Q O 2 u., C 2 o D 30 4 dw E '8{ D k ot h w t d g$ d s o O o O* arc 8 et i d g3 ) y EL 6 0 C 30 g y 7 5' Tj P G "A d 14 @ M l
1 l PERSCNS CONTAL.:D 3!!6!84
- cmpany S c5 At 612 A L 6 L u_.Ti2
- c Dates l Jocket/ Report No.
449ooSo3/4-08 Inspector E A P<; / G.x < r MeErnic '*'9* of 2NEfDiease 3*inti U R E(Please D*dnt) ORGANTU TION (3 Tease := int) TA14L&% N ' o)( e V/f41H/Axf Whl/4M kf hkW$0 ~ kmt T UAlencIA "Jc/ Eas N # '6E QA4Ro YK Poals dne Me a - &Af6tr C, E i/Eso 9.2 inic S~N fwse GE OA diec // f B 4R c-LA 7 Auorr e o v>w. Cf Nro /xSM {$. W W/4-P m AD $ C h % - l'PQ Gy cfAd. CMsE pqp - emo.y cystw GF GM+/r0 L.3. BoyL Mu Ge QA42D i G. 6 -5fra.,,,bnk & f du EnJ.Jlm B.,,,n,. Mr (# N srL 0 J.L.%4w, Yh v. R,o,QL). ' GF. NZS D J). G. Iex'G Sd-lhGXf'/.NGd. d6 - GA/AD r-
PERSCNS CCNTAC7 D GENEN GL6cTWc Cates 3//2/TrY Company l Occket/Reper..'lo. 9 99 oo4o 3 [E(-ol Insce::cr Ee.A R S e.gy/2ArJcs MEE MC page 1 of I a r m..s. = 4ne n um. s. : 4,e a m n m iten m ees. : 4,e L. s. &,at mn., "ElD,'X1;;'&DL "" *' '"vgi y D "' ' ' * - 3 %d4 a>uutL/ A psac "$$$< '$bsbYA.d. usm s~e L~ A.- GrMrs @Me e]. M. CASF Ie, OfA Sts m k 'G f MrBo df t /?O 7). c, eraa sewe c.,n,e e uwec &c,,eu 1r I 1 ,,--.__--.---.--....\\
PERSONS CONTAC7 D Company 0 Ed E2Ill EL GC 72 c Cates 3 /k-l6 8d Decket/Reper: No. 999 eo 40 9 [fft/-o / Inscecter _/'ESEA2S / / Page g of NAME(P7 ease Print) TIR E(Alease 3rd9:) ORGANTI2 TION (Digese 3*4nti UeSf Ihorspson %. Pips'~s Ana l. Gene->\\ Gled-te (Q o'X SA fA 6stA m WJA/#4 & $ f F W /~ $$ N b>1.f k 6'JAl C Gd/ l [e$ h & R4& %d RO MOD %/ 14e&d 3AvAd GAn/Utt S r. q,gg rt (pg,d6 ) " G.E - , hvagwt fvT4 Gp d b si-Av (h b 66 .s. u. g L p s gi n.e o., ec Q' 0 f' F~~,9: w ~ GE k. FA A L-4,v e n t Sa W CE E 'l GiB a & Gnca-CE 3 C. Csazom &m a, c s. btecy c. i N e u_. e -Pe BSa4 h Crs Ebs+ E}l5.esde<e Mbr~ Se.mes //us,a, Gf i v J r Po~/ esc < ^%e -cr-i.rs,i r cd ZHDM Pwicu oc Eua,e (LE 1 a ,l t l l l m
1 PERSCNS CCNTAL. -D i 'lcmpany % F*JE RA L L'LECTGt C Cates 3 ll2 Jocket/ Report No. Inspec cr D. WA'JK Page n of 1ME(Please Drinti TT 1.E(Please 3r%:) OAC-ANTI 2 TION (Diesse C=% ) 0AJ fois 3s fuse QAn (Q A e' e6 ) 5 602G, R E. Novak 5<. % ncaw % e, CA A - Oh 4 Ro 6 n+nn dan &N9mb u A/ef.E PD W rx wn ow~ se em w c >r - roc S.T. Be //ows 5,, P ~,. E ny e h DPy GL.SocMA% NC. Aact Ath N B E D_ RU VALENCIA St. Enc (L_ G2A a R.o e.A 5 ~ v T).C. %, uxA kenou &w Fi n H m x Ai,, lac. .}}