ML20215H180
| ML20215H180 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 10/17/1986 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20215H178 | List: |
| References | |
| NUDOCS 8610230002 | |
| Download: ML20215H180 (33) | |
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INITIAL OPERATING LICENSE READINESS ASSESSMENT FOR BRAIDWOOD STATION, UNIT 1 PREPARED BY UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III l
8610230002 861017 PDR ADOCK 05000456 A PDR
BRAIDWOOD STATION, UNIT 1 INITIAL OPERATING LICENSE READINESS ASSESSMENT 1.0 Introduction 2.0 Summary of SALP Reports 3.0 Region III Inspection Program 3.1 Construction and Preoperational Inspection Programs 3.2 Open. Inspection Items 3.3 Enforcement History
- 3. 4 Qualifications of Licensee Personnel 3.5 Regional Staff Concerns 4.0 Quality Assurance 4.1 Organization 4.2 Audits 4.3 Stop Work 4.4 Independent Evaluations 4.5 Conclusions 5.0 Hearings 6.0 Allegations 7.0 OI Investigations 8.0 Braidwood Construction Assessment Program 9.0 Summary and Conclusions
OPERATIONAL READINESS 1.0 Introduction Braidwood 1 is a 3425 KdT four loop Westinghouse Pressurized Water Reactor. The plant site.is located 50 miles Southwest of Chicago, Illinois. Braidwood is owned by the Commonwealth Edison Company (CFCo).
CECO presently operates the Dresden Station (2 units), Quad Cities (2 units), Zion (2 units), LaSalle (2 units), and Byron (1 unit).
Based on regional review and the results of our inspection efforts, we have determined that construction and preoperational testing of Braidwood Station, Unit 1, have been completed in substantial agreement with docketed commitments and regulatory requirements with the exception of items delineated in Attachment 1 of the Braidwood Station, Unit 1, Fuel Load and Precritical Testing License. This attachment was provided to your staff by memorandum dated October 17, 1986. This report provides the basis for the above findings.
Since issuance of the Construction Permit in December 1975, the NRC has conducted approximately 237 inspections at the Braidwood. site. To accomplish the inspection program, over 22,000 inspection hours of direct inspection effort have been expended. As'a result of these inspections 144 violations have been identified by NRC inspectors at Braidwood. One Civil Penalty was issued regarding violations identified in 1982.
Section 2 of this report summarizes the Region III assessment of licensee performance during SALP periods one through five, which covers the period July 1, 1979 through November 30, 1985.
Sections 3, 6, and 7 describe the Region III inspection program at the Braidwood site, resolution of allegations related to Braidwood, and the results of investigations performed by the Office of Investigations.
Section 4 describes the Commonwealth Edison Company (CECO) quality assurance program and its evolutions throughout the construction period.
This section also deals with independent evaluations performed for the Braidwood site.
Section 5 deals with the ongoing hearings for an operating license in which one contention is being litigated.
Section 8 provides an overview of the Braidwood Construction Assessment Program (BCAP).
Section 9 Braidwood'provides s readinessthe for overall conclusions of the staff's assessment of operation.
2.0 Summary of SALP Reports The performance of CECO at Braidwood has been evaluated five times by means of the SALP (Systematic Assessment of Licensee Performance) program.
The five assessment periods and the licensee's performance are summarized below:
SALP 1 The first Braidwood SALP addressed performance during the period July 1, 1979, to June 30, 1980. A management meeting was held with the applicant on November 25, 1980, to discuss the results of the SALP evaluation. The NRC concluded at this meeting that the enforcement history of the applicant during the assessment period was not of significant regulatory concern and that the number and severity of the violations identified were low relative to other comparable construction sites in Region III. A need for improvement was noted in the areas of design and procedural controls, communications and interfacing, audits, and corrective actions. Overall licensee performance was judged as adequate. Increased NRC attention was net. recc'nmended for any areas evaluated.
SALP 2 The second Braidwood SALP covered Braidwood's performance during the period from July 1, 1980, to December 31, 1981. The management meeting with the applicant was held on May 18, 1982. The licensee was rated in seven functional areas. The NRC concluded that the overall regulatory performance of the Commonwealth Edison Company at Braidwood Station was satisfactory during the assessment period; however, licensee management needed to focus attention on ensuring that the significance of nonconformance was being properly assessed.
SALP 3 The third Braidwood SALP addressed CECO's performance during the period from January 1 through December 31, 1982. The management meeting with the applicant was held on June 13, 1983. The licensee was rated Category 1 in one area, Category 2 in four areas, and Category 3 in two areas, Safety-Related Components and Quality Assurance. Problems identified in the Safety Related Components and Quality Assurance areas pertained to deficiencies in the control'and documentation of mechanical equipment installations. The deficiencies identified.in these areas and the applicant's corrective actions are discussed in Section 3.1.
Region III has reviewed these actions and found them acceptable.
SALP 4 The fourth SALP evaluation covered the period from January 1, 1983 l through June 30,1984. The management meeting with the applicant was held on November 26, 1984. The licensee was rated Category 2 in seven areas and Category 3 in three areas, Piping Systems and Supports, l Safety-Related Components, and. Quality Assurance and Administrative Controls. The applicant's performance in the early part of the assessment j period concerning the identification and implementation of corrective
- actions demonstrated a need for improvement. However, performance in this' area in the latter part of the period improved considerably. The NRC concluded that the applicant's performance was satisfactory and that overall performance exhibited an improving trend.
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SALP 5' The fifth and most recent SALP evaluation covered the period from July 1, 1984 through November 30, 1985. The management meeting with the applicant was held on March 14, 1986. Of the 13 functional areas reviewed, one was rated Category 1,11 were rated Category 2, and one was rated Category 3, Housekeeping and Equipment Protection. The licensee's corrective actions regardingthehousekeepingandequipmentprotectiondeficiencies' included a plant cleanup and a 'Model Areas Program" which prepared three specific plant areas for operation and then used them as examples for plant personnel.
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The NRC concluded that the applicant's improvements in overall regulatory performance identified in the SALP 4 Report had continued resulting in improved performance particularly in the three important. areas in which the applicant had previously been rated Category 3.
3.0 Region III Inspection Program Starting in 1976, following the December 1975 issuance of construction permit, a number of inspections have been conducted at the Braidwood facility. These are summarized in Table 3.1 and Figure 3.1.
3.1 Construction and Preoperational Inspection Programs The initial pre-construction inspection (October 17, 1973) at Braidwood Station considered construction status, project status, project
~ responsibility and the issuance of a common Quality Assurance Program for Commonwealth Edison nuclear generating stations. During the construction period from 1973 through 1981, 77 inspections covering 2,051 man-hours were performed resulting in 41 violations and 8 deviations. The number l and type of violations were normal for construction projects at the same stage of completion. In January 1982, the resident inspector program was established at Braidwood.
A special regional team inspection was conducted in May/ June 1982 to determine if there were indications of construction problems similar to those experienced at other problem sites. This inspection assessed the adequacy of certain ~ aspects of Braidwood quality assurance / construction activities. The scope of this assessment included audits of quality assurance program interfaces and overviews, corrective action systems, l
design change control, material traceability of installed structures and components, electrical cable installation,.inprocess inspections, and effectiveness 'of quality control inspectors. The overall team inspection findings at the time characterized the applicant's quality assurance program as good.
, Thefirstsignificantinspectionresultinginmajorfindingsanda
- subsequent Civil Penalty was conducted during the period of April 19 through July 20, 1982. During this inspection, significant deficiencies were identified in that written approved procedures had not been used for the installation and inspection of safety-related equipment. A Confirmatory Action Letter dated September 8, 1982, which was issued by Region III because of those deficiencies, identified the corrective
- actions the applicant would take in correcting the deficiencies.
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The licensee took immediate, aggressive, actions to correct the deficiencies found during the Region III inspections. These actions included the initiation of a back-fit program to reinspect previously installed equipment to verify the adequacy of the previous installations, the training of personnel involved in the installation and erection of mechanical equipment, the reorganization and dedication of additional management resources to provide a greater involvement in contractor work and quality assurance activities, and the establishment of written approved procedures for ongoing installations.
Region III has followed up on the licensee's corrective actions and has verified that the actions committed to by the. licensee have been completed.
Actions taken by Region III included a review of the back-fit procedures, review of the documentation associated with the inspection of installation activities, and a visual inspection of installed equipment.
Region III inspections since mid-1982 have resulted in the identification of. additional violations, some of which have been potentially significant.
None of the later significant violations are considered to be derivative from the specific deficiencies which resulted in the Civil Penalty. The Region did believe that the lack of early and adequate involvement in, and oversight of, its contractor's QA/QC programs contributed to subsequent NRC inspection findings in 1983 and 1984. The number and type of violations identified by Region III at Braidwood since 1982 have been normal for construction projects at the same stage of completion.
Region III conducted a special quality assurance inspection during the time period of mid-1983 to early 1984. The inspectors spent 300 inspector-hours assessing the effectiveness of the quality assurance programs of the piping contractor, the electrical contractor, and the heating, ventilation, and air conditioning contractor (HVAC). The inspection revealed deficiencies as'sociated with the verification of correct material for ASME piping components, control of HVAC welding activities, and design control of field run small bore piping and associated hanger installation activities. On December 20, 1983 and March 7, 1984, Enforcement Conferences were conducted regarding these deficiencies. A civil penalty was considered, but was not issued since the extensive corrective actions carried out to resolve the deficiencies did not identify significant hardware problems.
As a result of the Enforcement Conferences and CECO initiatives, the following corrective actions were instituted:
- a. The licensee substantially increased the number of CECO site QA personnel.
- b. A new position of Assistant Manager of Quality Assurance was established.
- c. The Ceco Braidwood QA Superintendent was replaced.
- d. CECO site audits were improved in technique, depth, and scope.
- e. The piping contractor's project management was replaced.
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- f. Major revisions were made to the piping and HVAC quality control programs.
- g. The reporting level of the Manager of Quality Assurance was changed from the Vice Chairman to the Chairman and President.
- h. Overinspection by the Independent Testing Agency at Braidwood was incra sed from approximately 10% to 25%.
- i. Communications between the site and the Corporate QA Manager were improved.
- j. Communications between CECO Project Management and the NRC were improved.
- k. The licensee established the Braidwood Construction Assessment Program. This program is discussed in detail in Section 8.
- 1. The Material Traceability Verification (MTV) Program was initiated to verify that the correct materials were used in safety-related piping systems.
- m. The National Board of Boiler and Pressure Vessel inspectors were brought in by CECO to audit ASME Code-construction activities.
As discussed in the SALP 4 Report, the corrective actions resulted in significant improvement in both CECO and contractor organizations. This report further stated that licensee management was'providing a clear and concise course to assure that all retro-fit work and future construction work met regulatory requirements and licensee commitments.
The MTV program provided for a 100% inspection of piping installations to verify acceptability of materials. The NRC conducted a special inspection of the MTV program during the period of July 1985 through January 1986.
Based on that inspection the NRC concluded that the MTV program was conducted in accordance with applicable procedures and that the program was an effective method to determine the traceability of piping materials. A small insignificant quantity of materials were cut out when the review could not conclusively prove that the specified materials were installed.
An evaluation of the removed materials indicated that if left in the system, they would not have resulted in failure under design conditions.
During December 1984 and January 1985, the NRC's Office of Inspection and Enforcement (IE) conducted a Construction Appraisal Team (CAT) inspection at the Braidwood site. The purpose of the CAT inspection was to evaluate the management control of construction activities and the quality of con-struction. The appraisal involved approximately 2600 on site inspector-hours and consisted of a detailed inspection of selected hardware, a review of selected portions of CECO's QA program, examination of records and procedures, observation of work activities, and an examination of project management.
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While the IE CAT inspection noted no pervasive breakdown in meeting construction requirements, it identified construction or QA deficiencies in a number of areas. These included vendor tanks and heat exchangers with deficient welds, vendor radiographs not meeting required weld or film quality requirements, failure to identify the required weld sizes for pipe supports and restraints, installation of unqualified switchboard wire and bolts of indeterminate material, failure to identify deficient seismic pipe support and restraint installations, and failure to provide adequate electrical separation criteria in quality control procedures. They also observed that CECO was implementing some good construction practices at the Braidwood site. These included active CECO management involvement in the construction of the project, the use of an independent test agency for inspection overview and unit concept review for construction adequacy, and the initiation of a Quality First Program.
Region III subsequently issued four violations to CECO based upon the CAT inspection. None of the items were found to warrant escalated enforcement action. Region III also followed up on CAT concerns that did not result in violations to assure their satisfactory resolution.
During 1984 and 1985, a number of Preoperational Inspections were conducted.
As discussed in the SALP 5 Report, satisfactory licensee performance was noted during these inspections. In March 1985, the licensee presented a comprehensive action plan designed to improve preoperational . testing performance. Follow-up inspections have shown that the licensee has adequately implemented the program elements. ,
Regional inspection of the Integrated Hot Functional Test revealed no significant hardware or operator performance problems.
3.2 Open Inspection Items A review of all open items has been completed and there are no open items which would preclude issuance of a Fuel Load and Precritical Testing License.
In addition, there are no open or unresolved inspection items which Region III has recommended to NRR for consideration as license conditions.
There.are additional items which will be open past fuel load and are not license conditions. These are listed in Table 3.2.
3.3 Enforcement History Notices of violation have been issued to CECO, when appropriate, during the construction and preoperational testing of the Braidwood facility. Table No. 3.1 summarizes the number of inspections and violations identified.
The licensee has been generally responsive to enforcement actions to correct the violations and to take steps to preclude repetition. Subsequent inspections of corrective actions have confirmed tSese actions to be proper and generally timely. No outstanding enforcement actions currently exist which would preclude licensing of Braidwood.
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i 3.4 Qualifications of Licensee Personnel The shift staffing levels of licensed and nonlicensed operators are adequate to support startup and power operations of Unit 1.
The minimum shift for Unit 1 operations at power is as follows:
1 Shift Engineer (Shift Supervisor), SR0 1 Shift Foreman (Unit Supervisor), SR0 1 Station Control Room Engineer _(STA), SR0 2 Reactor Operators, R0 2 Auxiliary Operators 1 Radiation Chemistry Technician 1 Health Physics Foreman The plant staff is currently on a five shift crew rotation. Six shift rotation will start in January 1987.
The first Operator and Senior Reactor Operator licensee examinations were held in March-April 1986. The second group of R0 and SR0 examinations were held in July-August 1986. Results of these two examinations are:
33 SR0 Candidates 28 Passed (85%)
14 R0 Candidates 13 Passed (93%)
Based on these first two examinations the training program has been effective.
4 l Currently Braidwood has sufficient numbers of experienced Senior Reactor
- Operators to meet regulatory requirements of one experienced individual on-
- each shift. Three on shift SR0's currently meet the experience requirements.
Additionally, as of October 1986, three Shift Engineers are each within one
, month of meeting the requirement for operation PWR experience. Two of
! these Shift Engineers will complete the experience requirement at Catawba Nuclear Station and one will finish requirements at Byron Station. There are however, three other fully experience qualified, Braidwood SR0's in the operating Department who are currently available for shift duty until the three Shift Engineers complete their training. To provide additional startup experience shift advisors who have had Byron startup experience will be utilized.
3.5 Regional Staff Concerns Each Region III professional was requested by memorandum dated July 11, 1986, to identify concerns which might restrain the issuance of a license, beyond those already addressed by inspection reports. No concerns are currently known which would preclude the issuance of a Fuel Load and Precritical Testing License for the Braidwood Plant. Items remaining to be completed after fuel load which neither preclude issuance of a license nor are included as a License Condition are identified in Table No. 3.2.
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- 4. 0 Quality Assurance During construction, a number of NRC inspections have been conducted to review the adequacy of the Braidwood Quality Assurance Program. Following, is a brief description of the evolution and actions taken by the licensee since inception of construction.
4.1 Q.A. Organization From the beginning of the project to the present the Commonwealth Site QA organization has undergone various changes commensurate with the progression and modification of site activities, and in response to identified deficiencies.
The Region III inspections in 1982 and 1983 identified weaknesses in Braidwood contractor QA, and in the Commonwealth Edison overview and involvement in its contractor's QA programs. As a result, Commonwealth Edison took action to increase staffing and improve training of.its contractors QA organization, and made significant changes in Commonwealth Edison site QA management and staffing. In SALP 5 the Region III staff concluded that these changes were effective, resulting in improved regulatory performances.
From the beginning of the project in December 1975 through December 1976, the basic QA organization on-site c ".sisted of a QA Supervisor, reporting directly to corporate QA, in charge of a small group of QA Engineers and QA inspectors. In late 1976, as the construction activity increased, the organization under the Site QA Supervisor was modified to provide for Coordinators in the structural, mechanical, and electrical areas to administer each area and provide improved interface with project and contractor personnel. In the Spring of 1979, as on-site documentation reviews became more extensive, a separate Coordinator, reporting to the QA Supervisor, was designated for this work. During the period of the Construction shutdown (September 1979 to March 1980), the Site Quality Assurance organization was reduced to a skeleton staff which primarily focused on record retention and maintenance of each contractor's document file. At the conclusion of the shutdown, staff was again added and the organization returned basically to that which existed prior to the shutdown. In early 1981, the position of the Site QA Superintendent
, was established, which elevated the level of the senior on-site Supervisor. Two QA Supervisors covering the Mechanical / Structural and Electrical / Documentation / Independent Testing Agency /HVAC/ Welding areas were assigned to report to the QA Superintendent.
In early 1983, a separate Coordinator reporting directly to the Site QA Superi:tendent was assigned to administer the Independent Testing Agency activities. Specific responsibilities relating to on-site design activities were assigned to the Mechanical / Structural Supervisor as the on-site Architect Engineer workforce increased. Also, the position.of Administrative Assistant was added to the organization. Beginning in early 1984, six new positions which affected the Site QA organization 8
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, were established. The corporate position of Assistant Manager of Quality Assurance was established on site. The Assistant Manager reported
- directly to the Manager of Quality Assurance. The new position of i General Supervisor Quality Assurance was established. The General l Supervisor reported directly to the Assistant Manager of Quality Assurance and had responsibility for the QA overview of the Braidwood 4
Construction Assessment Program (BCAP) and site design activities. In addition a full time Audit Coordinator was assigned,.and reported to the
, Site QA Superintendent. -The number of supervisors was increased from two to five and the work load redistributed.
I The Braidwood Construction Assessment Program was completed in late-1985 which resulted in the elimination of the position of General Supervisor
! of Quality Assurance and other QA personnel working on this activity. In addition, the position of Assistant Manager of Quality Assurance was 4
replaced with a new position of Assistant to the Manager of Quality Assurance with functional control of Site QA activitie's and direct t control for licensing activities associated with preparation for the Hearings before the Atomic Safety Licensing Board. Also, the Site QA
. organization was restructured to provide coverage by type of work i activity.
l I The Braidwood Station QA Section was established in August 19, 1982. This section is supervised by the Station QA Supervisor, who reports to corporate QA, who served in this same capacity during the startup of the LaSalle units. The section is fully staffed being organized into two groups: one responsible for testing and operations and the other for station maintenance.
t j 4.2 Audits Ceco Quality Assurance has conducted approximately 575 audits of the project organizations, construction contractors, and off-site vendors. CECO Corporate Quality Assurance has conducted another 26 audits, which included.
i the Site Quality activities, to assess the implementation and effectiveness of the Quality Assurance Program. In addition, 5765 surveillances have been i
performed by Site Quality Assurance.
! 4.3 Stop Work
- Since work at the Braidwood site began, there have been 22 stop work actions i including three at off-site vendor plants. These have been initiated by
- either Quality Assurance or Project Construction.
There have been no stop works ordered by the NRC.
! Table 4.3 is a list showing a brief description of each stop work.
l Region III considers the stop work actions initiated by Ceco to be l
appropriate for the conditions identified.
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4.4 Independent Evaluations by Third Parties i a. INP0 Self Initiated Evaluation During November 1982, a self-initiated evaluation of the design and construction of the Braidwood Station was conducted by CECO using INP0 guidelines. The results of this review determined that the overall quality program was clearly defined, understood and effective.
INPO Construction Project Evaluation During' July 1984, INP0 conducted a Construction Evaluation of the Braidwood Station. Beneficial practices and accomplishments noted during this evaluation included (1) use of piping features to determine hanger locations thereby avoiding tolerance accumulation, (2) piping contractor's welding qualification programs enforce high standards for performance and (3) practical approach to NF code boundary definitions; thus, code compliance is easier to obtain, an effective method for specifying FCR's and ECN's on working drawings, and an effective method is used to ensure that commitments are entered and maintained in operating department procedures. Recommendations dealt with (1) increased supervision to identify potential problems promptly, (2) timely correction of problems, (3) increased protection for installed equipment, (4) enhancement of craftsmen, operator and test engineer training and (5) upgrading of the industrial safety program.
INP0 Radiological Protection Special Assistance Visit During February 1986 at the request of the Braidwocd Station Manager, INP0 conducted a Radiological Protection Special Assistance Visit.
The purpose of this visit was to review the operational radiological protection program in support of fuel load. INP0 noted that senior station management is strongly committed to the implementation of a high quality and effective radiological protection program. Areas cited for improvement included operational ALARA program, development of detailed action plans for the ALARA and health physics groups, operational responsibilities of health physicist and additional radiological awareness training. As a result of this visit, detailed action plans for the ALARA and Health Physics groups were developed, presented to Station Management and are being used as guidance to implementation of both programs. Also, the responsibilities of each Health Physics Group member has been identified and reviewed with each member individually and as a group. Enhance'd Radiological Awareness training sessions are being conducted within the Radiological Protection Groups. Plans have been developed to expand this training to cover specified station personnel.
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i INP0/NT0L Assistance Visit During May 1986, INP0 conducted a NT0L Assistance Visit of the Braidwood Station. Beneficial practices and accomplishments noted during this assistance visit included (1) station personnel are professional with a high level of enthusiasm, (2) excellent succession planning for key station positions being filled with qualified people, (3) a model space program is used to effectively communicate standards
-for housekeeping, labeling, material condition, preservation and industrial safety, (4) system test engineers / operators are very attentive to verbal communications and record keeping during testing, (5) procedures clearly identify the steps to satisfy LC0 re actions and (6) an effective baseline program for airborne / quired surface contamination. Recommendations dealt with various issues, including (1) improvement of the Corporate oversight.of the On-Site Safety Review Committee, (2) improve the On-Site Safety Review Committee's quality of assessment of some problems, and (3) enhance the scheduling and planning of maintenance activities.
- b. National Board of Boiler and Pressure Vessel Inspectors On November 19, 1984, Commonwealth Edison requested the National Board to conduct an independent audit of the Braidwood station to address specific NRC concerns about ASME work at Braidwood. This audit began in February 1985 and continued through February 1986, with subsequent periodic visits by team members continuing into September 1986. The audit was an in-depth examination of site practices as they related to ASME Code construction. The National Board's audits resulted in concerns and findings which Commonwealth Edison responded to and which were resolved to the Board's satisfaction as documented in their Final Report, dated June 6, 1986. This audit provides additional assurance, over and above that at other nuclear plant construction sites, that Braidwood station construction is in accordance with ASME Code requirements.
4.5 Conclusions During the construction and preoperational phase, a number of inspections were conducted by the NRC to review Ceco Quality Assurance functions, including the Regional Special Team inspection in-1982, and the Inspection and Enforcement (IE) CAT inspection conducted in 1984/1985. These inspections identified that CECO and its contractor's Quality Assurance programs had significant weaknesses prior to 1982, which were subsequently resolved resulting in improved performance. The various corrective action programs.and BCAP have provided adequate assurance that these weaknesses did not result in design significant safety related hardware problems going uncorrected.
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5.0 Hearings Initial hearings on the emergency preparedness contention were conducted on October 29, 1985; hearings were completed for this contention on March 12, 1986. The parties have submitted proposed findings on this contention and the matter is pending before the Licensing Board for its decision.
In its June 21, 1985 Order, the ASLB admitted a complex contention alleging inadequate QA/QC during construction of the Braidwood Station. Directed Certification to the Appeal Board of this Order was requested by the applicant and supported by the NRC staff in its July 23, 1985 filing.
On September 6, 1985, the Appeal Board denied the grant of directed certification by a 2 to 1 majority. The applicant filed a request to waive the regulations prohibiting an appeal to the Commission af the Appeal Board denial of the grant of directed certification. This request was supported by the staff, opposed by the intervenor. On April 23, 1986, the Commission dismissed the quality assurance contention.
An additional issue was accepted by the ASLB on July 23, 1985 concerning harassment, intimidation, retaliation and other discrimination. Hearings on this issue began in May 1986 and are continuing (completion estimated as November 1986).
On August 18, 1986, the applicant submitted a Motion for Authorization of -
Fuel Loading and Precritical Testing to the ASLB under 10 CFR 50.57(c). On September 18, 1986, the ASLB issued a Memorandum and Order authorizing the Office of Nuclear Reactor Regulation to issue a limited license to Commonwealth Edison for fuel loading and precritical testing of Unit 1.
6.0 Allegations Fifty-nine allegations concerning both safety-related and nonsafety-related areas at Braidwood have been received, have been inspected or are in the process of being inspected by the Region III staff.
Each allegation received was reviewed by regional management and a response based on the actual potential safety significance was determined. All allegations were reviewed by regional personnel and/or the Office of Investigations.
A breakdown of allegations by year follows:
l Year No. of Allegations Received j 1979 1 4 1980 1
, 1981 0
. 1982 1 l 1983 1 1984 11 1985 25 t 1986 19 l Total 59 i
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At this time, eight of the above allegations are still open. All open allegations that.are material to the fuel loading and precritical testing license have been inspected to determine significance. No safety problems were identified which would preclude the issuance of a' fuel load and precritical testing license.
The open allegations are:
- AMS No. RIII-84-A-0021 Inspector intimidation (awaiting 00J action)
- AMS No. RIII-85-A-0032 LKC Mylar control (awaiting 00L action)
- AMS No. RIII-86-A-0131 EQ of equipment supplied by Johnson Controls-turned over to vendor inspection Branch
- AMS No. RIII-86-A-0137 Security Concerns
- AMS No. RIII-86-A-0139 Cocaine sales
- AMS No. RIII-86-A-0155 Eight LKC concerns
- AMS No. RIII-86-A-0167 Electrical Cable Storage and Quality First In November 1984, the applicant implemented a Quality First Program to provide individuals associated with Braidwood an independent group to receive, review, and act upon concerns that may have an adverse effect on the quality of the plant. Region III has reviewed the applicant's implementation of the Quality First Program and determined that the program is effective in resolving employee concerns. Additionally, the applicant's QA organization performs audits and surveillances of the Quality First Program.
7.0 0I Investigations There are currently four active OI investigations relating to the Braidwood site. One is a vendor investigation. Thesubjectmatterofthese investigations cannot, at this time, be publicly identified. Nonetheless, investigators from 01 and the the RIII technical staff have been working closely to ensure that any technically significant issues identified during the OI investigations are provided to the RIII staff for technical evaluation. To date, none of the information developed by 01 would preclude the issuance of a fuel load and precritical testing license.
8.0 Braidwood Construction Assessment Program The Braidwood Construction Assessment Program (BCAP) was a program of reinspections and reviews undertaken by the applicant in response to concerns regarding the overall quality of construction of the Braidwood Station.
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BCAP was developed by CECO to provide an overall assessment of the quality of safety-related construction work at Braidwood. Thestatedobjectivesof the BCAP were to assure that:
- No unidentified or unaddressed programmatic design-significant construction problems exist;
- Onsite contractor's safety-related procedures address all applicable design and regulatory requirements; and
- Significant corrective actions have been adequately implemented ano documented for past construction deficiencies.
To accomplish these objectives BCAP utilized the following three program
! elements:
- . Construction Sample Reinspection (CSR) - a visual reinspection of a sample of safety-related construction work completed and QC accepted through June 30, 1984, and a review of the associated documentation;
- Reverification of Procedures to Specification Requirements (RPSR) - a review of onsite contractor's installation, inspection, and personnel qualification and certification procedures for ongoing and future safety-related construction activities as of June 30, 1984;
- Review of Significant Corrective Action Programs (RSCAP) - a review of methodologies, implementat. ion, and resulting documentation associated with nine significant corrective action programs in progress during BCAP.
! The BCAP was implemented under the control of a Commonwealth Edison Company (CECO) task force. A group within the CECO Quality Assurance (QA)
Department was established to conduct reviews, assessments, verifications, audits, and surveillances of the implementation of the BCAP. In addition, CECO retained the Evaluation Research Corporation (ERC), an independent organization having no prior connection with Braidwood, to provide an independent overview of the BCAP program.
Region III assigned a dedicated inspector to assure that the BCAP was properly implemented, that identified deficiencies were properly processed and evaluated, that potential adverse trends were detected, and that the results of the program were accurately documented and
! evaluated. From August 20, 1984 to the end of June 1985, the assigned inspector was at the Braidwood site monitoring the BCAP program and the j review and evaluation of identified discrepancies.
Based upon the Region III inspections and the review of the
" Report on the Braidwood Construction Assessment Program (BCAP)",
dated November 1985, the NRC concluded that the BCAP was satisfactorily
, prescribed and implemented and that the results of the BCAP provided j additional confidence in the acceptability of the past, ongoing, and
! future construction activities at Braidwood.
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1 I 9.0 Summary and Conclusions Inspections conducted by Region III have determined that the applicant'is generally responsive to NRC concerns and that the applicant applies adequate management overvi.ew of the plant processes and personnel.
During review and inspection of the Technical Specifications, the NRC found a high degree of consistency between the plant Technical Specifications, Safety Evaluation Report (SER), Final Safety Analysis Report (FSAR),
as-built configuration, surveillance. requirements and Preoperational Test Acceptance Criteria.
Overall, Region III has found the construction and testing programs at the j Braidwood site to be acceptable. In addition, the steps being taken by
! Ceco to complete actions necessary for fuel load are being taken with sufficient management overview and thoroughness.
i We therefore conclude that Braidwood Unit 1 has been constructed i substantially'in accordance with Construction Permit No. CPPR-132, the
- i. FSAR and NRC regulations, and that Commonwealth Edison Company is ready to load fuel and conduct safe precritical testing operations.
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BRAIDWOOD STATION
! NRC Rlll INSPECTION STATISTICS
]
1976 - Violation s 7
1977 - 3 Inspections
- 1978 - 34 1979 - 33 1980 - ',3 '
1981 -
34 1982 -
1983 - '$o I ,
1984 43 1985 30 1986 - 34 o 1o 20 so 4o 50 so 7o FIGURE 3.1
BRAIDWOOD STATION NRC Rlli INSPECTION STATISTICS AVERAGE AVERAGE NUMBER INSPECTION CITED HOURS PER HOURS PER YEAR INSPECTIONS HOURS VIOLATIONS INSPECTION VIOLATION 1976 8 124 11 16 11 1977 8 222 7 28 32 1978 14 510 8 36 64 1979 15 384 5 26 77 1980 13 267 11 21 24 1981 14 411 6 29 69 1982 8 1233 16 154 77 1983 20 2705 19 135 142 1984 43 5251 33 122 159 1985 60 7840 25 131 314 1986* 34 3846 3 113 1282 TOTALS 237 22793 144 96 158
+ Ending with inspection Report No. 456/86035; 457/86027.
Inspection Report No. 456/86023 has not been issued to date.
Date: 10/1/56 TABLE 3.1
Table 3.2 FRAIILOOD CCNSTRUCTION 10:451HURSLAY, DCTOBER 16; LIMITED REPORT hRC ITEM STATUS
-.__ ---SCHEDULER CAT =106---- bD- r_W_i_r_ed__M_)e__@_qd _eled_____.
prior to initial criticality CSS ITEM N'JrEER SUBJECT STATUS CLG31NG REFCRT 78 456-100-03-07-03 kRC UNRESOLVED ITEM CN CONTROL READY CHILLERS NOT EElhG INSFECTED FY PART OF REINSFECTION FROGRAM.
79 456-100-83-16-02 NDC UNRESOLVED ITEM 04 50LR FAN OFEH COOLERS IN UNIT f CGNTAINMENT CAMAGED.
80 456-100-83-17-03 ARC 0 FEN ITEM CN EATTERY CELL READY MCNITCRING AND HYDRCGEN MONITCoING REGUIREMENTS.
81 456-100-S3-17-04 NRC UNRESOLVED ITEM CN NAMEPLATE READY INFO 60T CCNSISTENT PCTL'EEN AS-BUILT AND DRAWING.
82 456-100-94-06-01 h?C L%RESCLVED ITEM CN INACEQUACY OFEN OF LXC FROCEIURES REGARDING CONTRUL CF '3En0VED ITEM'.
83 456-100-84-09-03 NRC UNRESOL\ED ITEM CN VT OF WELIS READY Af1ER PAIhTING AND CECO LAIVER OF <
FINAL VI AFTER NDT.
54 456-100-84-42-01 NRC CPEN ITEM CN SYSTEM FOR OPEN IEENTIFYING DESIGN CHANGES THAT EFFECT UPDATING OF FEAR.
85 456-100-84-42-07 NRC UNRESOLVED ITEM ON F AST LKC READY IR 86-039 ICR'S NOT INDICATING CCARECTIVE ACTION TAKEN.
86 456-100-54-42-10 NRC CPEN ITEM CN L,%C SYSTEM FCR PEADY IR 56-039 REINSTALLATION OF REMOVED IIEMS.
i S7 456-1C0-55-007-C1 NRC OPEN ITEM CN LKC AVO AND GPEN IRAWING CCNTROL FROGRAM.
SS 456-100-E5-007-04 NRC CFEN ITEM CN CS itnP AND MOTOR READY IR 86-03?
ENVIP.0aMENTAL QUALIFICATION ISSUES.
.E? 456-100-85-C07-05 NPC UNRECOLVE0 ITEM ON LACK OF CTEN RECCROS AND EPECIAL CCNTROL FOR ELECTRICAL PENETRA1 ION INSTALLATION 90 456-100-85-025-05 NRC GiEN ITEM ON DG-10 TEST NOT REALY INCLUDI4G R/G 1.108 CRITERIA.
ERAIDWOOD CONSTRUCTION 10:48 THURSDAY,' DCTOBER 16, LIMITED REPORT NRC ITEM STATUS SCHED"LER CAT =106-CBS ITEM NUMPER SUBJECT STATUS ClG41Nr. RFPCRT 91 456-100-85-008-09 NRC UNRESOLVED ITEM DN INDEPENDENCY READY OF DIVISION 11 AND DIVISION 12 ELECTRICAL SYSTEMS 92 ~ 456-100-85-015-09 NRC CPEN ITEM ON REVISED QC READY INSFECTOR REINSPECTION PROGRAM.
93 -456-100-85-019-02 NRC CPEN ITEM ON REVIEW CF FGCP-48 READY PROCEDURE FOR FINAL WALXDOWN.
94 456-100-85-021-02 NRC UNRESQLVED ITEM, ACCEPTABILITY BEADY IR 86-049 0F LKC WELD INSFECTORS WORK UNDER QUESTIDNABLE CERTIFICATION.
95 456-100-85-021-03 NRC UNRESOLVED ITEM, DOCUMENTATICN OFEN CF HANGERS INDIVIDUAL WELD ACCEPTANCE AND NDE REQUIREMENTS.
96 456-100-55-021-04 NRC VIOLATION FCR LACK 0F EVIDENCE READY IR 86-049 THAT REJECTED' HANGER WELDS WERE CCRRECTED.
97 456-100-05-026-03 NRC OPEN ITEM ON NRC INSPECTOR NEED READY TO REVIEU APPROVED SI-10 TEST RESULTS PACKAGE.
98 ' 456-100-35-032-01 NRC UNRESOLVED ITEM CN DEFICIENT READY STRUCTURAL BGLTING IN THE AUX BUILDING.-
99 456-100-85-032-0E NRC VIOLATION ON FLEX METAL HOSES OPEN INSTALLED WITH FORMED TRAPS.
100 456-100-85-038-01 NRC UNRESDLVED ITEM ON PROCUREMENT READY CF SAFETY-RELATED LOP INSTRUMENTS.
101 456-100-85-038-04 hRC UNRESQLVED ITEM DN ROUTING READY IR 86-039 0F CAELE IVYO?2.
102. 456-100-85-039-05 NRC UNRESOLVED ITEM ON LOCATION / READY IR 86-039 LACK 0F QC WELD INSFECTIDN RECORDS FOR CAELE TRAY SUPPORIS.
103 456-100-85-03"-06 NRC OPEN ITEM CN DISPOSITION OF READT 1R 86-039 LKC NCR 4302.
BRAIDWOOD CONSTRUCTION 10:48 THURSDAY, DCTOBER 16 LIMITED REPORT NRC ITEM STATUS SCHEDULER CAT =106
. OSS ITEM NUMIER SUBJECT STATUS CLOSING REPCRT 104 456-100-85-045-01 NRC VIOLATION FOR INADEQUATE READY CORRECTIVE ACTIONS FOR PROTECTION AND CLEANLINESS OF EQUIPMENT.
105 456-100-85-048-01 NRC VIOLATION FOR IhCORRECT SETTING OPEN CF. TORQUE SWITCHES ON SAFETY RELATED MOTCR OPERATED VALVES ,
(ICV 83559 ISIBE07B, 1S18814) l 106 456-100-85-04S-05 NRC VIOLATION FOR FAILURE TO READY IR 86-049 PERFORM ADEQUATE INSPECTIONS DURING BUTT MPLICE CORRECTIVE ACTION PROGRAM.
107 456-100-85-053-03 NRC GPEN ITEM CN LACK OF ~ TECH SPEC OPEN SURVEILLANCE FOR DIESEL AFU PUMP BATTERIES.
a 108 456-100-85-053-04 NPC OPEN ITEM ON DIESEL AFW PUMP OPEN
. BATTERY SELECTOR SUITCH NOT BEING
- ADDRESSED BY PROCEDURE.
109 456-100-85-054-01 NRC UNRESCLVED ITEM IN THE AREA 0F OPEN j ELECTRICAL WORK ACTIVITIES.
110 456-100-85-060-01 NRC OPEN ITEM TO TRACK DETECTION CPEN AND ANALYSIS OF CASES WHERE CONDUITS OF DIFFERENT CLASSES ARE IN CONTACT WITH EACH OTHER.
111 456-100-65-060-03 NRC CPEN ITEM TO TRACK REVISION OF READY IR 86-049 CALCULATIONS FOR MOTOR EFFICIENCY BASED ON ACTUAL VENDOR SUPPLIED DATA VS THE ASSUMED YALVES USED.
j 112 456-100-86-017-02 NRC OPEN ITEM TO TRACK COLLECTION DPEN ,
CF SAMPLES AND THE OPERATION AND CALIBRATION OF CN-LIhE MONITORS WHICH WILL SE OBSERVED BY THE NRC.
l 3
113 456-100-E6-025-01 NRC VICLATION ON FAILURE-TO CONTROL OPEN SOME NONCONFORMANCES DURING PREOP TEST ACTIVITIES.
4 114 456-100-86-025-03 NRC UNRESOLVED ITEM ON READY ADMINISTRATION OF THE MAINTERANCE' P.ROGRAM INCLUDING.ISI, TRENDING AND l
BRAIDWCCD CONSTRUCTION 10:48 THURSDAY, DCTGLER 16, LIMITED REPORT NRC ITEM STATUS
- - -- SCHEDULER CAT =106 OBS ITEM NUMBER SUBJECT STATUS CLOSING REPORT' VORK REQUEST 115 456-100-86-027-01 NRC CPEN ITEM TO REVIEW THE METHOD GPEN
. CURRENTLY BEING UTILZIED TO TRACK THE USE OF MEASURING AND TEST EQUIP. EMPLOYED IN PREOP TESTS.
i 116 456-100-86-037-05 NRC OPEN ITEM TO TRACK CCMPLETION OPEN
' AND USE OF HRSS FOR EAMPLIts, OF REACTOR C00LANT AND DISSOLVED GASSES.
i 117 456-100-86-043-01 NRC OPEN ITEM 10 REVIEU UHETHER THE OPEN ENGINEERING JUSTIFICATION TD ALLOW
! A 10% TOLERANCE ON ThE ESW PUMP TOTAL DEVELOPED HEAD WAS SUFFICIENT l
118 456-i00-E6-046-01 NRC OPEN ITEM TO TRACK COMPLETION READY OF THE TECHNICAL SUPPORT CENTER (TSC) PRIGR TO FUEL' LOAD.
119 456-100-86-046-02 FRC OPEN ITEM TO CEMONSTRATE THE OPEN SATISFACTORY USE OF THE HRSS FOR PRIMARY COOLANT SAMPLING UNDER SIMULATED ACCIIDENT CONDITIONS.
120 456-100-86-046-03 NRC CPEN ITEM TO SATISFACTORILY CPEN -
DEMONSTRATE THE USE CF THE CONT.
AIR SAMPLING PANEL UNDER SIMULATED ACCIDENT CONDITIONS.
121 456-150-84-04 PART 21 84-04 ON RUSKIN FIRE READY DAMPERS FAILURE TO CLOSE.
122 456-150-85-02 DEFECTIVE AIRLINE CHECK VALVES IN LE EN MSIV ACTUATORS ANCHOR DARLING (QC 21-61) 123 456-t50-85-04 PART 2i ON P0TENIIAL PROBLEM CPEN RELATED TO CONNECTRCN NU2 TERMINAL
-BLOCKS FURNISHED W11H HYDRAULIC ACTUATORS.
124 456-155-83-12 55(E) 83-12 FAILURE OF ANACONDA READT IR 86-059 FLEXIPLE CONDUIT C0VERING (JACKET) 125 456-155-85-02 55(E) E5-02 INADEQUATE TANK / HEAT OPEN l
> - _>_ .m_._. _ ______________._m.._. .
i -
d e
ERAIDWOOD CONSTRUCTIO.N 10:48 THURSDAY,OCTCPER'l{
LIMITED' REPORT i
.hRC ITEM STATUS i
i SCHEDULER CAT =196 2 !
CBS ITEM N'JMPER SUBJECT STATUS CLOSING REPCRT I
i EXCHANGER WELDS.
i 126' 456-155-86-06 55(E) 86-06 CN RECEIPT AND USE OF READY
!- FASTENER MATERIAL SUPPLIED BY
- CARDINAL.
i t i
I 1
l 1
i i
i l
4 I
l.: !
1 1
e.
l t
i
, , . 4,. .
FT BRAIDWOOD OPERATING 11:29 THURSDAY, OCTOBER 16 LIMITED REPCRT NRC ITEM STATUS SCHEDULER CAT =106---
CBS' ITEM NUMBER SUBJECT STATUS CLOSING REPORT 6 456-101-78-04 IE BULLETIN 78-04 ON LACK OF CPEN ENVIRONMENTAL QUALIFICATION FOR SCME NAMCO LIMIT SWITCHES.
7 '456-101-80-06 IE BULLETIN 80-06 ON ENGINEERED GPEN SAFETY FEATURE RESET CONTROLS.
8 '456-104-85-05 NRC GENERIC LETTER 85-05 CN READY IR 456/96-039 INADVERTENT BORON DILUTION EVENTS AT PURS.
9 456-122-86-00005 RCFC C00 LING COILS AND SX SUPPLY / READY RETURN LIhES
-10 456-122-86-00017 CATEGORY 1 MANHOLE COVERS READY 11 456-122-86-00020 125 VDC BREAXERS READY 12 456-122-86-00323 REACTOR COOLANT FRESSURE BOUNDARY READY CCNTROL VALVES.
13 456-122-86-00024 PROCEDURES TO DEPRESSURIZE RCS READY 14 456-122-84-0002E SEISMIC QUALIFICATION CF POR'V'S READY 15 456-122-86-00030 ESF SYSTEM DUCTWORK TESTING OPEN
FRAIDWOOD CONSTRUCTICN 10:49 THURSDAY, OCTOBER 16 LIMITED REPORT NRC ITEM STATUS
SCHEDULER CAT =109- IteE_requir_Ed_ta_be__C0019101031 -!
prior to 5% power CSS ITEM NUMPER. SUBJECT STATUS CLOSING REFORT 127 456-100-84-06-07 NRC DEVIATICN CN FAILURE 10 ENSURE OFEN DESIGN TAKES SEPARATICN CRITERIA INTO ACCOUNT.
128 456-100-84-08-04 N9C OPEN ITEM ON PREQUALIFICATION OFEN OF JOINTS BY NAPCLEAN.
129 456-100-84-08-07 NRC UhRESCLVED ITEM ON WELD EETAIL READY BEING SELECTED AND DOCUMENTED BY CRAFT INSTEAD CF ENGINEERIRG.
130 456-100-84-09-01 NRC VIOLATION ON TIE FAILURE TO OPEN PRESCRIBE PHYSICAL CLEARANCE CRITERIA PRIOR TO INSTALLATIONS.
131 456-100-84-44-01 NRC VICLATION FCR ACCEPTANCE AND OPEN INSTALLATION CF VENDOR PROCURED TANXS WITH IMPROPER WELDS.
132 456-100-S4-44-0E NRC VIOLATION ON INADEQUATE OPEN CCEREC11VE ACTION FOR LKC NCR 37.
133 456-100-85-019-01 NRC CFEN ITEM CN BCAP DISCREPANCIES READY ON THE THREADED PORTIONS OF BCLIS LCADED IN SHEAR.
134 456-100-85-023-02 NRC UNRESCLVED ITEM ON READY ACCEPTABILITY OF ONE EMBED CONNECTION EOLTING.
135 456-100-85-036-01 NRC CPEN ITEM GN CONTROL AND POWER READY IR 86-949 CAELE LEFINITICNS AND CLASSIFICATIONS.
136 456-1C0-85-036-02 NRC VIOLATICN ON INADE; TATE OFEN CLEANLINESS OF ELECTRICAL JUNCTION ECXES.
137 456-100-85-053-06 NRC Of EN ITEM ON FIRE FARoIER READY PEhETRATION SEAL MATERIALS AND CONFIGURATICN.
138 456-100-95-053-07 HEC OfEN ITEM CN INSTALLATION OF READY FIRE STATION NO. 272 AT CCLUMN-RCW L-14.
137 456-100-85-053-C8 ARC CFEN ITEM GN ACCEPTA5ILITY OF READY
IRAIDWOOD CONSTRUCTION 10:48 THURSDAY, OCTOBER 16, LIMITED REPORT NRC ITEM STATUS.
SCHEDULER CAT =109 OBS ITEM NUMBER SUBJECT STATUS CLOSING REPORT DEVIATING FROM NFPA' STANDARD NO. 14 FOR FIRE SYSTEM YALVE.
140 456-100-85-056-02 NRC UNRESOLVED ITEM FOR LACK OF READY DOCUMENTATION AND CONTROLS REGhRDING TRAINING OF DAD PERSONNEL AT BRAIDWOOD.
141 456-100-85-056-03 NRC UNRESOLVfD ITEM ON THE USE OF READY APPROPRIATE TE9T PROCEDURES FOR OAD ELECTRICAL CONSTRUCTION TESTS.
142 456-100-85-056-04 NRC UNRESOLVED ITEM FOR FAILURE TO READY INCLUDE GAD ON DISTRIBUTION OF STATION ADMINSTRATIVE PROCEDURES.
'143' 456-100-85-056-07 NRC DPEN ITEM GN THE PRACTICE OF READY IR 86-049 UTILIZING GENERAL USE EQUIPMENT VS.
CERTIFIED INSTRUMENTS FOR CAD PERFORMED TESTS.
144 456-100-85-057-02 NRC GPEN ITEM CN THE LACK OF CPEN C00RDINATION BETWEEN TECH STAFF AND MECH. MAIN
T. PROCEDURE
S IN TESTING PRESSURIZER SAFETY VALVES.
145 456-100-84-002-04 NRC OPEN ITEM TO TFACK THE TESTING GPEN AND CALIBRATION OF UNIT 1 AND COMMON AREA RAD MONITCRS AND PROCESS RAD MONITORS.
146' 456-100-86-002-08 NRC DPEN ITEM TO TRACK COMPLETION READY IR 86-054 0F INSTALLATION, TESTING AND CALIERATION OF HIGH RANGE NOBLE CAS EFFLUENT MONITORING SYSTEMS.
147 456-100-E6-002-09 KRC OPEN ITEM TO TFACK THE POST GPEN ACCIDENT EFFLUENT SAMPLIhG SYSTEM AND THE ANALYSIS GF IODINE AND
' PARTICULATE EFFLUENT SAMPLES.
143 456-100-86-032-10 NRC OPEN ITEM TO TRACK INSTALLATION READY IR 86-054 0F CONTAINMENT HIGH-RANGE RADIAT10N MONITOR SYSTEM SUPPLIED BY GENERAL.
A10 HIC CCMPANY.
147 456-100-86-002-19 NRC OPEN ITEM TO TRACK FR0XIMITY OPEN
FRAID'400D CONSTRUCTION 10:48 THURSDAY, GCT0EER.16 LIMITED REPCRT NRC ITEli STATUS
==-
SCHEDULER CAT =109 OBS ITEM NUMEER SUBJECT STATUS CLOSING REPORT l
j 0F MANUAL FIRE FROTECTION ISOLATION VALVES TO FILTER HOUSING AND LOCATICN OF TSC ISOLATION VALVES.
150 456-100-86-013-01 NRC CFEN-ITEM TO TRACK COMPLETION OPEN OF SILICON BR0hZE WELD INSPECTION ON HVAC CCMPANION ANGLE TO DUCT WELDS.
151 456-100-96-017-01 NRC OPEN ITEM TO TRACK INSTALLATION. OPEN OF 3 ADDITIONAL AIR SAhPLERS IN THE FIELD BY THE FALL GF 1996.
152 456-100-86-020-Oi NRC OPEN ITEM TO TRACK THE STATUS READY OF WATER SEEPAGE IN THE TENDON
. GALLERIES.
~153 456-100-86-021-10 NRC OFEN 11EM TO TRACK COMPLETION OPEN j OF THE EMERGENCY OPERATING i FACILITY (EOF) PRIOR TO FUEL LGAD.
i 154 456-100-86-021-11 NRC OPEN ITEM TO TRACK THE PALANCE OPEN
- 0F DOCUMENTS REQUIRED 10 PE MAINTAINED AT THE CORPORATE COMMAND CENTER (CCC).
I 155 456-100-86-021-27 NRC OPEN, ITEM TO ENSURE PROTECTIVE READY ACTION RECOMMENDATIONS ARE IN PLACE AND TRAINING COMPLETE SO ALL 4 RADIGLOGICAL ACCIDENTS ARE COVERED. .
f I 156 456-100-86-021-34 NRC OPEN ITEM TO COMPLETE CPEN h DEVELOPMENT OF AND TRAINING TO THE COMMUNICATION SERVICES PLAN.
~157. 456-100-26-021-26 NRC OPEN ITEM 10 COMPLETE SIREN OFEN SYSTEM FOR THE 10-MILE EPZ AND l COMPLETION OF TRAINING FCR AFPROPRIATE PERSONELL.
158 456-100-S6-037-01 NRC OFEN ITEM TO TRACK DEVELDFMENT OPEN
- OF ACCEPTANCE LIMITS FOR RESULTS I 0F ANALYSES OF STANDARDS FERFORMED BY RAD / CHEM.
159 456-100-S6-037-02 KRC OPEN ITEM T0 REVIE'J ADDITIONAL OPEN RESULTS DBTAINED FRGM THE i.
-. - . . . - . - - - - - . - - - . . - . - - - - - . . . - - - - . . - ---- . - - ~ - - - =- - - - . - .
- f. '
t 1
1
! FRAIDWOOD CONSTRUCTION 10:48 THURSDAY, OCTCEER 16;
! LIMITED REPORT NRC ITEM STATUS SCHEDULER CAT 109 =
f !
i' OBS ITEM NUMBER SUBJECT STATUS CLOSING REPOR1
- - INTERLABORATCRY COMPARISON OF !
- ANALYSES OF PRIMARY RX COOLANT. i
! r l
160 456-100-86-037-04~ NRC OPEN ITEM TO TRACK CONCERNS' OPEN FILD WITH THE REEULTS OF THE !
. CONFIRMATORY MEASUREMENTS PROGRAM. 'l
- 1. !
t j '161 456-100-86-046-05 NRC DPEN ITEM TO REVIEW GENERAL OPEN j l EMERGENCY EAL FOR CONDITION 24 IN l BWSP 200-1A1 TO INSURE THAT THE i CORRECT CLASSIFICATION IS MADE.
162 456-150-84-07 PART 21 CN ENERGY AB50RBING PtEADY ;
} MATERIAL (EA!!) FABRICATED BY HEXCEL i DURING 1978-1979 HAD CRUSH ,
STRENGTHS BELOW ACCEPTAFLE VALUES. !
i l 163 456-155-82-01 55(E) 82-01 INADECUATE HVAC DUCT. READY l WELDING.
I .
l 164 456-155-82-09 55(E) 82-09 CN INTERFERENCE OF. READY MECHANICAL SNUBBER BRACKETS WITH l
PIPE MOVEMENT.
165 456-155-E2-10 55(E) 62-10 ON INALEQUATE READY STRUCIURAL STEEL INSPECTICNS. ,
i 166 456-155-83-01 55(E) 03-01 CN HVAC IhSTALLATICN READY- l
.NOT IN ACCORDANCE WITH S&L 1 SPECIFICATIONS. I i
167 456-155-83-03 55(E) 83-03 ON SUPPORT CCLUMNS FOR READY i S/G & RCPS NOT INSTALLED IN +
ACCORDANCE WITH S&L DRAWINGS. i i
168 456-155-83-08 55(E) 83-08 ON FABRICATICN OF MVAC READY t DUCT FITTING WITHOUT APPROVED ,
DESIGN DOCUMENTt" 0N.
160~ 456-155-84-07 55(E) 84-07 ON INADEQUATE CONCRETE READY EXPANSION ANCHOR (CEA) l INSTALLATIGN. ;
170 456-155-84-08 55(E) 84-08 DN INADEQUATE OPEN [
INSTAtt ATION 0F VENTILATION HOUSING j
& AIR RISERS I
F
. _ _ . _ _ _ _ _ . . . _ _ _ ._____..__...____ - _ _ _ _ _ ____._.. m. _ _ __.___ _ --..- ~ . _ . . . _ _ . . _ . _ __ _
f*' .
i ^
l- .
URAltWOOD CONSTRUCTION 10:48 THURSDAY, OCTOBER 16j LIMITED REPORT NRC ITEM STATUS l i i
~
---SCHEDULER CAT =109 l
l 01'S ITEM NUMBER SUBJECT STATUS CLOSING REFORT l
}
j 1 71 456-155-84-11 55(E) 84-11 ON FAILURE OF BOEING READY .
. S/G SNUBBER hlGd PRESSURE ROD l . SEALS.
l f
- 172 456-155-84-12 55(E) 84-12 DN IMPROPER REMOVAL READY OF ASME NPT NAMEPLATES. l 173 456-155-84-14 55(E) 84-14 CN DEFECTIVE BCEING READY S/G SNUBBERS. !
, 174 456-155-04-15 55(E) 84-15 ON INCONSISTENCIES IN READY
! THE GXN UELDING PROGRAM. #
I 175 456-155-84-17 55(E) 84-17 ON THE NEED FOR READY I l IMPROVED CEA INSTALLATION / i
{ - DOCUt1ENT ATION. {
f .
l 176 456-155-84-19 55(E) 84-19 ON ABILITY OF HEXEL READY t EAM 10 MEET CRUSH STRENGTH ,
- REQUIREMENTS.
I~ i j 177 456-155-85-05 55(E) 85-05 ON POTENTIAL VIOLATION GPEN
- 0F E.Q. DUE TO HELB ASSOCIATED WITH -
S/G'BLCWDOWN AND AUX STEAM.
l 178 456-155-86-02 55(E) 86-02 DN REJECTABLE WELD READY
.NDICA110NS ON LOOP-1 S/G AND [
PRESSURIZER UELD SEAMS.
t f
1 w_...-~_ _.. . _ _ -_- _ - _
BRAID'400D GPERATING 11:29 THURSDAY, OCTOBER 16,
, LIMITED REPORT NRC ITEM STATUS SCHEDULER CAT =i"'
i OBS ITEM NUMBER SUBJECT STATUS CLO3ING REPORT 14 456-101-81-01 IE BULLETIN 81-01 CN SURVEILLANCE READY 4
0F KECHANICAL SNUBBERS.
17 456-101-84-03 IE BULLETIN 84-03 ON A REFUELING OFEN CAVITY EATER SEAL FAILURE.
18 456-101-85-01 IE BULLETIN 85-01 DN STEAM BINDING GPEN OF AUXILIARY FEED WATER PUMPS 19 456-104-85-22 GL 85-22: POTENTIAL FOR LOSS OF OPEN POST-LCCA RECIRCULATION CABABILITY DUE TO INSULATION DEBRIS BLOCKAGE 20 456-122-86-00011 REMOTE SHUTDC'4 N CAPABILITY DPEN 4 21- 456-122-86-00029 AUX BLDG VENTILATION TESTING OPEN REQUIREMENTS 4
i i
h i
es.
FRAIDWOOD CONSTRUCTICN 10.43 THURS!AY, OCT0FER 16, LIMITED REPORT NRC ITEM STATUS
SCHEDULER C AT=121- 3 D--@_i_c_h_p_ay__b_e _co_d_e)_d after 5% power CES ITEM NUMfER SU5JEC1 STATUS CLCSING REPORT 179 456-100-82-03-05 bRC UNRESOLVED ITEM CN PCSSIPLE OFEN CONFLICT REG. GUIEE 1.29.
180 456-100-84-09-08 NRC OPEN ITEM ON OVERUSE OF OPEN FCR VERBAL AFFROVAL WITHOUT DOCUMENTED WRITTEN AFFROVAL.
181 456-100-84-13-03 -NRC CFEN ITEM DN USE CF VAPCR READY INHIBITOR OPTI0hs OTFER THAN GAS PURCES.
182 456-100-84-23-05 NRC OPEN ITEM ON LACK CF FINAL READY REVIEW AND AFFR0 VAL GF INSTALLATICN RECORDS FCR SENSING LINES.
183 456-100-85-004-01 NRC UNRESCLVED ITEM ON LEAKING CFEN TENDONS.
184 456-100-85-015-05 NRC CFEN ITEM CN EVALUATION OF FAST READY IR 86-039 h
INSPECTIONS TO INCLUDE CASES WnERE CALIb9ATED 100LS LERE NOT LCGSED.
185 456-100-85-027-03 NRC UNRESOLVED ITEM CN TIMELINESS READY REFCRTABILITY GF 55E REFORT 85-06 CN 3/G PRIPE.
186 456-103-95-037-01 NRC IDENTIFIED GSEP EXERCISE READY CEA(NESS, NO CALL TO NRC GPS CENTER LAS MADE BY TSC CR CONTRCL R00.1.
187 456-t00-85-037-02 NRC IDENTIFlED G5EP EXERCISE CPEN CEAKNESS, FROTECTIVE ACTION DECISION MA<IbG FROCESS INADEQUACY.
188 456-100-85-048-02 NRC UNRESOLVED ITEM REGARDING THE OFEN LACK CF TESTING GN MCLDED CASE PREAKERS.
189 456-100-85-054-02 NEC CFEs ITEM-TWE NRC INSFECICR OFEN REVIEWED FCAP OfSERVATIONS IN THE ELEC1RICAL AREA FOR TECHNICAL METHC00 LOGY AND CCMPLETENESS.
~190 456-100-96-002-01 hRC OFEN ITEM TO TRACX IHE CPEN SELECTION CF AN AREA AND CCNSTRUCTION OF i TLD CALIBRATION <
FACILITY.
r-BRAIDWOOD - CONSTRUCTION 10:48 THURSDAY, DC10BER 16; LIMITED REPCRT NRC ITEM STATUS SCHEDULER CAT =121 GBS ITEM NUMBER SUBJECT STATUS CLOSING REFORT
. 191 456-100-86-00'2-03 NRC OPEN ITEM TO TRACK THE CONST., OPEN STAFFING, AND STOCKING OF .THE RESPIRATOR ISSUANCE, STORAGE, AND CLEANING FACILITY.
192 456-100-86-002-05 NRC EPEN ITEM TO TRACK THE OPEN CONSTRUCTION CF FACILITIES AND STOCKING OF EQUIPMENT TO SUPPORT-THE RADIATION FROIECTION PROGRAM.
193. 456-100-86-016-02 NRC OPEN ITEM TO TRACK C'ONCERNS OPEN HELD WITH THE MANNER IN WHICH 10 CFR 50.59 REVIEWS ARE CURRENTLY BEING PREPARED.
194 456-100-86-021-35 NRC OPEN ITEM CN THE DISTRUBUTION OPEN Of THE FRAIDEDCD PUBLIC INFORMATION BROCHURE BY APRIL 1987.
l 195 456-150-83-02 H2 RECDP.BINED VITON SEALS READY IR 86-039 ROCXWELL INTERNATIONAL.
196 456-150-85-03 PIPING SUPPLIED BELOW MINIMAL READY WALL THICKNESS GUYON ALLOYS INC.
)
l 197- 456-155-84-05 55(E) 84-05 CN INCONSISTENCIES READY
- j. IN DOCUMENTATION OF STRUCTURAL l . STEEL INS'ALLATION TRAVELERS (SSIT) t l
l t
5 i
l l
L
Table 4.3 Braidwood Station Stop Work Action Initiated by Commonwealth Edison Company No. Year Organization Description
- 1. 1977 System Control Factory assembly on cable pans and hangers
- 2. 1979 System control Factory welds on Ianels
- 3. 1981 L. K. Comstock Cable pulling activities
- 4. 1981 Phillips, Getschow Instrument support design activities
- 5. 1981 Inryco Post tensioning material
- 6. 1982 Phillips, Getschow Mechanical equipment installation
- 7. 1982 L. K. Comstock Weld rod control
- 8. 1982 G. K. Newberg Structural steel installation
- 9. 1982 Phillips, Getschow Component supports
- 10. 1983 Pullman Sheet Metal- HVAC installation activities
- 11. 1984 Project Management Receipt of safety-related material
- 12. 1984 Pullman Sheet Metal Duct installation activities
- 13. 1984 L. K. Comstock Power cable pulls l 14. 1984 Pullman Sheet Metal HVAC equipment installation
! 15. 1984 G. K. Newberg FCAW and SMAW documentation
- 16. 1984 continental Field Machining Machining of diesel generators
- 17. 1984 L. K. Comstock Electrical butt splices l 18. 1984 L. K. Comstock. AVO system l
- 19. 1984 Phillips, Getschow Whip restraint installation
- 20. 1984 L. K. Comstock Hanger fabrication
- 21. 1984 L. K. Comstcok Inspector Reinspection Phillips, Getschow Program Pittsburgh Testing Laboratory
- 22. 1985 Phillips, Getschow Instrument Retrofit Verification j Program I
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