ML20212J187
| ML20212J187 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood, Clinton, 05000000 |
| Issue date: | 01/16/1987 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Funches J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8701280104 | |
| Download: ML20212J187 (10) | |
Text
pe JAN 16 1987 MEMORANDUM FOR: Jesse L. Funches, Director, Planning'and Program Analysis Staff, NRR FROM: Charles E. Norelius, Director, Division of Reactor Projects, RIII
SUBJECT:
NT0L PLANT LICENSING STATUS -' REGION III Enclosed is the updated plant licensing status for Clinton 1,
-Braidwood 1, and Byron 2. This information is current as of January 16, 1987. Should you or your staff have any further questions, please contact R. C. Knop for Clinton, W. S. Little for Braidwood, and W. L. Forney.
for Byron 2.
AC STCygo yy g* E NORElnjs Charles E. Norelius, Director Division of Reactor Projects
Enclosure:
Updated Plant Licensing Status ,
cc w/ enclosure:
J. G. Keppler, RIII J. A. Hind, RIII C. J. Paperiello, RIII SRI, Clinton l
SRI, Braidwood l SRI, Byron J. Strasma
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LICENSING STATUS FOR CLINTON 1 Clinton Power Station (CPS) Unit 1 is a BWR/6 plant with a Mark III containment.
The Illinois Power Company was issued a low power operating license (NPF-55) on September 29, 1986 authorizing fuel loading and plant operation up to 5%
rated thermal power. The plant is jointly owned by Illinois Power Company (IP),
Soyland Power Cooperative, Inc. and Western Illinois Power Company (WIPCO). IP has a majority ownership and is responsible for plant construction, licensing and operation. Completed and projected major milestones associated with achieving a full power operating license are as follows:
Fuel loading completed October 21, 1986 C Vessel head-set (not tensioned) November 8, 1986 C Initial criticality January 22, 1987 Commission briefing February 14, 1987 Full power license February 23, 1987 Emergency Preparedness All onsite and offsite emergency preparedness licensing requirements have been completed satisfactorily.
A full participation emergency preparedness exercise was held on January 13, 1987. Since the exercise occurred prior to issuance of the full power license a schedular exemption from Appendix E will probably not be required.
NRC Inspections:
RIII conducted an augmented inspection of licensee performance during fuel loading. A number of fuel handling errors occurred during fuel loading. In addition, there have been numerous licensee event reports, many involving personnel errors. Those items were discussed during meetings on October 22 and December 1, 1986 with the licensee.
- 1. Construction and Preoperational Testing All preoperational tests required before fuel load are complete. Testing on deferred systems is in progress and approximately 78% of the tests have been completed.
Drywell and containment structural integrity tests and containment integrated leak rate testing were completed January 2,1986. Subsequent to this time, a hole was discovered in the containment liner which raised questions concerning the test results and control of work on the contain-ment liner. The applicant has successfully performed a confirmatory ILRT.
LICENSING STATUS FOR CLINTON 1 2. Fire Protection A joint audit by NRR and Region III was conducted September 9-13, 1985.
All items required to be resolved prior to fuel load were completed.
- 3. Radiation Protection & Radwaste The most recent inspections were conducted November 4-7, 1986. Areas requiring further licensee attention include: preoperational testing, radiation mon-itor calibrations, radwaste solidification system installation, and TMI action plan item compliance documentation (NUREG-0737 Item II.F.1, Attachment 1)
- 4. Emergency Planning An Emergency Preparedness Implementation Appraisal (EPIA) was conducted November 12-21, 1985, and a number of items were identified which will require correction. Most of those items are related to equipment not yet installed, training of onsite response personnel, and final revision of procedures. A follow-up inspection to the EPIA was conducted in March 1985.
A full-scale exercise was held January 13, 1987.
- 5. Chemistry, Radiochemistry, and Confirmatory Measurements The licensee completed certain confirmatory measurements comparisons necessary for low power license issuance. Analyses for Strontium 89 and Strontium 90 will be completed prior to operation above five percent of rated power.
- 6. Physical Security All Clinton Security Plans have been reviewed and approved. Security for onsite Special Nuclear Material (SNM) was found to be adequate. Complete lock-down and implementation of the security program was initiated June 16, 1986 and the security program is considered adequate to support plant operations. The most recent security inspection was conducted between December 1-10, 1986.
- 7. Allegations There are 12 allegation files that remain open and assigned to the staff.
Most of the allegations have been reviewed in some detail, but additional inspections are required to close them out. These issues are expected to be resolved to the point of determination of safety significance prior to operation above 5% of rated power.
LICENSING STATUS FOR CLINTON 1 8. 01 Investigations There are seven outstanding investigations.
- 9. Operator Licensing Licenses for operators were issued in July (17 licenses: 14 SR0s and 3 R0s) and December 5, 1985 (22 licenses: 14 SR0s and 8 R0s), in February 1986, (10 licenses: 3 SR0s and 7 R0s), and in April 1986; (7 licenses: 5 SR0s and 2 R0s). The Commission policy on experience levels for SR0s, R0s and STAS has been satisfied.
- 10. Enforcement The staff is reviewing three issues. One involves a case in which the Secretary, Department of Labor found that an electrical foreman at Clinton had been discriminated against for engaging-in a protected activity; this case is presently being reviewed by IE/0GC. The second involves a case of inadequate design review and construction of the service water intake structure with regard to maximum flood levels at the site. An enforcement conference was held on this issue with IP in the Region III office on August 29, 1986. The third issue involves a case of inadequate post maintenance / modification testing involving:
(1) failure to adequately perform post-modification testing; (2) inadequate post-maintenance testing; (3) failure to adequately review maintenance work request packages; and (4) use of improper material in performing modification / maintenance work. The licensee conducted audits of the 129 modification packages and all of the maintenance work requests to determine the extent of testing that was required to revalidate precperational test results. Region III evaluated the results of the licensee's findings, and found that corrective actions were adequate for fuel load. An enforcement conference was held on December 18, 1986.
LICENSING STATUS OF BYRON 2 Byron 2 was issued a low power license on November 6, 1986, and achieved initial criticality January 9,1987. The plant is scheduled to be ready for full power licensing by January 22, 1987. Byron 2 is essentially identical to Byron 1 which received its full-power license on February 14, 1985. The FES, issued April 1982, and the SER, issued February 1982, apply to both units.
FSAR Review The FSAR review that was completed to support licensing of Byron 1 applies to Byron 2. All unit-specific items, such as pre-service inspection and safe shutdown analysis, were addressed in Supplement No. 7 to the SER, which was issued to support fuel load.
Hearings The hearings that were completed prior to licensing of Byron 1 applied to Byron
- 2. There are no further hearings anticipated prior to licensing Byron 2.
Emergency Preparedness Review and evaluation of emergency plans are complete. All outstanding emergency preparedness related SER items have been resolved.
Construction Appraisal Team (CAT) Inspection An IE CAT inspection was performed from August 19 to September 20, 1985. The inspection report was issued on November 13, 1985. No pervasive breakdown in meeting construction requirements was identified. A Notice of Violation containing three items was issued to the applicant on December 12, 1985. The responses received on January 24, 1986 and April 9, 1986 have been reviewed by the Region and IE, and the Region has verified that the applicant's corrective actions were completed.
Independent Construction Verification A R-I NDE van inspection was conducted October 28 to November 8, 1985, providing independent verification of construction activities and materials through records review and nondestructive examinations. The inspection report was issued December 18, 1985; no major concerns in the NDE area were identified.
I Independent Design Review On April 24, 1985, the applicant submitted its plans for ensuring that all applicable corrective actions resulting from the Byron 1 IDI, Byron 1 IDR, and the Clinton 1 IDVP are incorporated into the Byron 2 design. The NRC has completed its review of this information. An inspection of the implementation of corrective actions was completed the week of November 18, 1985. The inspection reoort was issued on April 2, 1986 and concluded that corrective actions were being implemented. Three items requiring follow-up have been verified to be complete.
LICENSING STATUS OF BYRON 2 Region III Inspections There are approximately 24 matters which require resolution by the applicant prior to full power. These include open items, violations, 10 CFR 50.55(e) reportable deficiencies, allegations, unresolved items, and IE Bulletins.
The 2514 inspection program is in progress. All startup test procedure reviews are complete, and fuel load activities were witnessed. The remaining inspections to be completed prior to issuance of a full power license are precritical data reviews, and witnessing selected low power tests.
Operator Licensing All Byron 1 licensed personnel were issued Byron 2 licenses based upon exams in September 1986 given to a sample group.
Preoperational Testing Potential inadequacies in containment ventilation system flow were identified in preop test results. This requires resolution prior to exceeding 5% power.
Security A security preoperational inspection was conducted on September 22 -
October 7, 1986. No significant concerns were identified. Security lockdown was completed in September, and the security program is functioning smoothly.
Allegations
- There is one allegation file open at Byron' applicable to Unit 2. There are no technical issues which would impact full power.
Investigations There are no open 01 cases involving Byron 2.
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LICENSING STATUS OF BRAIDWOOD 1 A license authorizing fuel loading and precritical testing for Braidwood Unit 1 was issued on October 17, 1986. Fuel loading began on October 25, 1986, and was completed on November 3,1986. The FES was issued in June 1984. The SER was issued in November 1983, and SSERs 1 and 2 were issued in September and October, 1986, respectively. The letter from the ACRS supporting issuance of an OL was issued on February 11, 1985. The ASLB hearings commenced on October 29, 1985, and were completed on November 26, 1986. The hearing record was closed on December 17, 1986. A final ASLB decision is not expected until March 1987.
FSAR Review The application for the Byron and Braidwood Stations was submitted and accepted for review under the Commission's standardization policy statement of March 5, 1973. This application was for two duplicate units at each of two sites; therefore, the staff's review of the duplicate design portions of these four units was conducted simultaneously and documented in the Byron SER. The staff's review of the Braidwood site-specific portion of the Byron /Braidwood FSAR is essentially complete. There are four outstanding and four confirmatory items still under review.
Hearings
, The Braidwood application is contested; the OL evidentiary hearing was completed on November 26, 1986. The hearing was closed on December 17, 1986.
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 the construction of 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 of the Appeal Board denial of the grant of directed certification. This request was supported by the staff and opposed by the intervenor. On April 23, 1986, the Commission dismissed the quality assurance contention. An additional contention was accepted by the ASLB on July 23, 1985 concerning harassment, intimidation, retaliation and other discrimination. The hearing on this contention has been completed and spanned 97 hearing days between May 6, 1986 and November 26, 1986.
On August 18, 1986, the applicant filed a request persuant to 10 CFR 50.57(c) for authorization of fuel load and precritical testing. The staff submitted a response supporting the request; the intervenors opposed the request. On September 18, 1986, the ASLB issued an Order granting the applicant's motion.
Construction Appraisal Team (CAT) Inspection A CAT Inspection was conducted by the Office of Inspection and Enforcement during December 10-20, 1984 and January 7-18, 1985. The Inspection Report
! LICENSING STATUS OF BRAIDWOOD e (50-456/84-44; 50-457/84-40) was issued February 20, 1985. 'Although construc-tion was generally found to be in accordance with requirements, the team identified a number of hardware deficiencies and program weaknesses as potential enforcement action items. 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 i bolts of indeterminate material, failure to identify deficient seismic pipe j support and restraint installations, and failure to provide adequate
- electrical separation criteria in quality control procedures. The potential
]-
enforcement actions were issued as violations by the Region in April 1985.
- Seven of the nine violations have been closed by the Region.
[ Independent Design Review (IDR)
$ On April 24, 1985, the applicant submitted its plans for ensuring that all-T- applicable corrective actions resulting from the Byron 1 IDI and IDR, and the
. Clinton 1 IDR are incorporated into the Braidwood design. The NRC review of i this information has been completed; an NRC inspection was conducted on .
November 18-22, 1985 to verify the proper implementation of these corrective actions. The inspection report was issued on April 2, 1986. All open items
- -have been closed by the Fegion. ,
Region III Inspections
$ There are approximately 63 and 60 matters which require resolution by the applicant prior to initial criticality and 5% power, respectively. These include open. items, violations, 10 CFR 50.55(e) reportable deficiencies, LERs, i allegations, unresolved items, generic letters, IE Circulars, IE Bulletins, and
- 10 CFR 21 reports. There are also a number of normal inspection modules that l remain to be completed in the following areas (percent completion for each area i
4 is included):
- Operations QA Program Safety Comsnittee Inspection(74%) (50%)
Fire Protection (75%)
Preop Test-Procedure Review (95%)
Preop Test Results Review (90%)
, Radiation Protection (95%)
Radwaste (30%)
SER Review and Followup (75%)
i Radiological and Chemical Confirmatory Measurements (90%)
{ Emergency Preparedness (95%)
Startup Test Procedure Review (50%)
Startup Test Results (0%)
I Startup Test Witnessing (0%)
Overall Startup Test Program (80%)
Low Power Test Procedure Review (0%)
i
- Power Ascension Test Procedure Review (0%)
Precritical Data Review (0%)
Initial Criticality Witnessing (0%)
1
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r LICENSING STATUS OF BRAIDWOOD Security and Safeguards The preoperational inspection of the security program has been completed. The licensee has satisfied the minimum requirements of their security plans required to support fuel load.
Radiation Protection and Radwaste The most recent inspection was conducted October 6-8, 1986. There are presently four open items.
Operator Licensing Confirmation that the senior reactor operators have obtained the requisite experience on shift is required. The first group of operator examinations was completed in April 1986. Sixteen of seventeen Senior Reactor Operators, and six of six Reactor Operators passed. The second group of operation examinations was completed in August 1986. Twelve of seventeen Senior Reactor Operators and-seven of eight Reactor Operators passed. The third group of operator examina-tions were conducted during the weeks of November 10 and November 17, 1986.
Fourteen Senior Reactor Operator and five Reactor Operator licenses were issued.
The SR0 and R0 pass rates were 88% and 71%, respectively, for the third group.
Allegations There are seven open allegation files which require Region III action.
OI Investigations The Office of Investigations has four (three applicant plus one vendor) open investigation files.
Fire Protection The NRR Site Audit and the Region III Appendix R Team inspection were conducted during the week of August 18, 1986. One special inspection was conducted to assess the applicant's conformance to fire protection requirements for receipt and storage of new fuel onsite.
Braidwood Construction Assessment Program (BCAP)
For background information on this issue, please refer to the November 15, 1985 report. The final presentation to the NRC concerning BCAP was conducted on October 15, 1985; the final BCAP report was issued on November 14, 1985, by Commonwealth Edison Company for NRC review. The NRC review of the final BCAP report is documented in Inspection Report Nos. 456/86003; 457/86003 dated June 9, 1986.
Emergency Preparedness All onsite and offsite emergency preparedness licensing requirements have been completed satisfactorily. Several items must be resolved prior to initial criticality, and will be examined in the first quarter of 1987.
T LICENSING STATUS OF BRAIDWOOD By letter dated August 22, 1986, the licensee requested an exemption from the requirement to conduct an emergency preparedness exercise, involving the full scale participation of the State of Illinois and all three counties within the 10-mile EPZ, within one year of exceeding 5% power. The licensee has been informed that the 1987 exercise must also involve participation by the State of Indiana to satisfy the requirements of 10 CFR 50, Appendix E, IV.F.1.
FEMA has determined that the State of Indiana's involvement in the 1985 exercise was minimal, and inadequate to satisfy FEMA's exercise evaluation criteria associated with the aforementioned Appendix E requirement. The licensee's first exercise was conducted in November 1985, and the next exercise was proposed for mid-March 1987. This exemption request is currently under review.
The licensee has indicated that the State of Indiana will participate in the 1987 exercise in order to satisfy the regulatory requirements.