ML20214P190
| ML20214P190 | |
| Person / Time | |
|---|---|
| Site: | Perry, Byron, Braidwood, Clinton, 05000000 |
| Issue date: | 09/15/1986 |
| From: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Funches J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8609170347 | |
| Download: ML20214P190 (23) | |
Text
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pw SEP 151986 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 statu: for Perry 1, Clinton 1 Braidwood 1, and Byron 2.
This information is current as of September 10, 1986-.Should you or your staff have any further questions, please contact R. C. Knop for Perry and Clinton, W. S. Little for Braidwood, and W. L. Forney for Byron 2.
Ucr19 hat Stened by C.E. Corolics" 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, Perry SRI, Clinton SRI, Braidwood SRI, Byron J. Strasma
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Perry 1 Clinton 1 Braidwood 1 Byron 2
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LICENSING STATUS FOR PERRY 1 Perry 1 is a BWR/6, Mark III containment plant. The Cleveland Electric Illuminating Company (CEI) was issued a low power operating license (NPF-45) on March 18, 1986 authorizing fuel loading and plant operation up to 5% of rated thermal power. A Comission full power license briefing was conducted on September 5, 1986. Due to a court ordered stay, a Commission vote to authorize a full power license was not conducted. Region III issued a SALP report on June 27, 1986, and a meeting was held with CEI on July 15, 1986.
One license condition involving fire protection for cable tray supports remains to be completed.
In a letter to H. R. Denton, dated March 10, 1986, CEI certified that the plant's Technical Specifications conform with the as-built plant.
In a letter to the Commission dated August 15, 1986, the Governor of Ohio (Richard Celeste) stated that he has appointed a panel to study.the adequacy of the offsite emergency plan EPZ area in view of the Chernobyl accident; and that he has withdrawn the State's approval of the Perry offsite emergency plan pending completion of the commissioned study. The Governor also requested that the NRC delay issuing a full power license for Perry Unit 1 until the panels study is completed.
Hearings The ASLB hearings were initiated in May 1983, during which time the QA Construction issue was litigated. A favorable Partial Initial Decision was issued on December 2,1983, and was appealed by the intervenor (Sunflower Alliance). The Licensing Board's QA decision was affirmed by the Appeal Board (ALAB-802).
Hearings were completed on the emergency plans and TDI diesel generator reliability issues on April 12, 1985. Hearings on the remaining issue (hydrogen control for degraded core accidents) were concluded on May 3, 1985. The ASLB issued a concluding Partial Initial Decision (PID) on emergency planning, hydrogen control and diesel generators on September 3, 1985. This decision specifies several issues to be resolved by the applicant:
emergency planning - 4 items; TDI diesels - 1 item; and hydrogen control -
2 items. The four emergency plan items were satisfactorily resolved and were reported as such by the FEMA. Both intervenors (Ohio Citizens for Responsible Energy and Sunflower Alliance) have appealed the ASLB PID as well as several other prior decisions. A motion for a stay of the PID was denied by the Appeal Board on October 24, 1985. A motion to reopen the record and admit six new contentions involving fire protection requirements and single loop operation was filed by Intervenor 0CRE on December.12, 1985 and denied by the Appeal Board on February 27,1986. A motion to admit a new contention relative to the earthquake impact on the Perry seismic design was also filed by OCRE on February 3, 1986. The Appeal Board ordered that a preliminary hearing be held the week of May 15, 1986 to determine if OCRE's I
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LICENSING STATUS FOR PERRY 1 allegations on the earthquake should be admitted as a new issue for litigation. The Commission vacated the Appeal Board Order and denied the motion to reopen on April 18,1986(CLI-86-07). On July 25, 1986, the Appeal Board affirmed the concluding partial decision, as well as prior ASLB decisions on appeal, in ALAB-841.
2.206 Petition A Petition was filed by Susan Hiatt of the Ohio Citizens for Responsible Energy (0CRE) on February 3, 1986. This Petition requests that the NRC not permit fuel. loadir.g or any -facility operation pending inspection and testing of the facility, an examination of site seismicity, and hearings on OCRE's seismic design contention (if it is admitted by the Appeal Board).
By letter dated February 4, 1986, to the Commission, Donald L. Schlemmer, on behalf of the Western Reserve Alliance, requested that immediate action be taken with regard to the Perry plant, Units 1 and 2.
Specifically, Mr. Schlemmer requested that the Commission: -(1) suspend the construction of the Perry plants, (2) require an independent design and construction verification program to assess the integrity and implementation of the Perry quality assurance (QA) programs, and (3) review and require an audit of an application by Centerior Energy Corporation (CEC) seeking the approval of the Securities and Exchange Commission (SEC) to acquire all outstanding shares of Cleveland Electric Illuminating Company (CEI) and Toledo Edison and of mergers by which this will be effectuated.
Both Petitions were denied on March 18, 1986.
(DD-86-04)
Region III Inspections There is one open item requiring resolution prior to exceeding 5% power.
This item concerns the adequacy of the fire barrier wrappings of safety related electrical supports.
1.
Preoperational-and-Startup Testing All Preoperational Tests required before fuel load are complete. Perry 1 was issued a low power operating license on March 18, 1986, and the licensee commenced fuel load on March 21, 1986. On April 24, 1986 the licensee completed loading the 748 fuel assemblies loaded into the vessel. Some delays were experienced due to malfunctions in the fuel handling equipment and due to spurious signals experienced in the neutron monitoring system (a LER has been filed by the licensee on the neutron monitoring system problems).
Initial criticality occurred on June 6, 1986. The licensee has completed Non-Nuclear Heatup, and is currently performing Nuclear Heatup.
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5 LICENSING STATUS FOR PERRY 1 3-2.
Emergency Preparedness An Emergency Preparedness Implementation Appraisal (EPIA) v3s conducted in March 1985, and follow,up inspections were conducted in July, September, November 1985, and January 1986. All appraisal items have been closed.
One bulletin item, related to auditability problems in hign noise areas, remains to be resolved. The licensee has agreed to identify the hign noise areas during the next six months, cnd to take the nt.cessary, permanent corrective action (s) at the first refueling cutage.
In addition, a plant first aid facility must be completed before removing the con-struction crews' medical office.
A full participation exercise was conducted on April 15, 1966 $atisfying emergency preparedness licensing requirements. A sumr54ry report of the exercise (50-440/86-09 and 50-441/86-03) identifying exercise weaknesses i
needing corrective action., was issued by the regional inspection staff on April 30, 1986.
3..
Security The lest security inspection was conducted the week of May 5, 1986. This-inspection was for the startup phase.
One violation was identified and immediately corrected by the licensee. This violation is considered closed.
A management neeting was held at Region III on August 14, 1986 with the licensee to discuss a Level IV security violation, and an associated Level IV violation concerning reportability of the event. There are no known security issues which would preclude issuance of a. full pcwer operating license.
4.
Fire Protection in December 1985, Region III completed its pre-licensing inspection 3ctivi-ties. All pre-licensing issues have been resolved. A few minor hardware items are being processed by the licensee on an acceptable schedule. The licensee has been requested to evaluate the need to wrap safety related cable tray supports prior to exceeding 5% power.
5.
1986 0hiu Earthquake Review An earthquake occurred-on January 31, 1986, with an epicenter 10 miles south of the Perry site. The earthquake had a magnitude of approximately five on the Richter scale. An Augmented Inspection Team (AIT) was dispatched to the site on February 1,1986, to gather facts and to make a general assessment of the damage. This effort was subsequently supplemented with a team of Regional specialists during the week of February 3,1986. These team inspections identified no significant damage to the plant as a result of the earthquake.
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LICENSING STATUS FOR PERRY 1 In June 1986, the licensee completed the submission of all reports on the results of the confirmatory work items required in SSER No. 9 for full power licensing authorization. The staff has completed its review of the licensee's reports, and.has completed its own independent assess-ment of the earthquake, and its impact on the plant design. The staff's evaluation report, which is to be documented in SER Supplement 10, was advanced to the licensee by letter dated August 13, 1986, with copy to the intervenor. The staff concludes that all' outstanding and confirmatory issues related to the earthquake have been satisfactorily resolved to permit the full power licensing of Perry 1.
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6.
Perry Offgas Charcoal Fire On June 20, 1986, the licensee declared an unusual event based upon a determination that a fire existed in the off-gas treatment system charcoal adsorbers. The fire is believed to have been started as a result of positioning space heaters in close proximity to the charcoal adsorber tanks during testing. The licensee initiated a nitrogen purge on the adsorber tanks shortly after discovering the contained fire and esta-blished continued monitoring of the intermal temperatures of the affected tanks. After temperature profiles indicated that the fire was cut the licensee terminated the unusual event on June 23, 1986. A reignition of the charcoal fire occurred on July 6,1986 as the licensee attempted to resume preoperational tests of the offgas refrigeration syste:n.
The licensee's recovery plan was approved by Region III for removal of the charcoal. A wet evacuation process was used to remove charcoal from those tanks where the fire occurred. The removal process was completed on July 29, 1986.
The staff is preparir.g reports on this event which will be documented in SER Supplement 10.
Allegations All allegations concerning Perry have been r1iued by the staff. No significant problems have been identified m IN basis of allegation inspection / reviews performed by the regio: a. P f to date.
0I Investigations The Office of Investigations has three investigations underway regarding Perry.
l These items will be pursued by 01 at a later date due to priority work being performed by 01 at other facilities, and are not expected to impact the full
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power licensing decision.
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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 and is in the final stages of the licensing review process. The plant is jointly owned by Illinois Power Company (IP), Soyland Power Cooperative, Inc.
and Western Illinois Power Company (WIPC0).
IP has-a majority ownership and is responsible for plant construction, licensing and operation. Major milestones associated with CPS are as follows:
Application for OL tendered December 1, 1979
.FESissued(NUREG-0854)
April 1982 SERissued(NUREG-0853)
February 1982 LastSERSupplement-(SSER-5)
January 1986 IP fuel load (licensing) date Late September 1986 Clinton construction'is essentially complete and all systems have been turned over to IP. There are approximately 1700 open items on IP's master punch list required to full power operation; about 230 of these items need to be resolved prior to the fuel load date. The applicant predicts that they will be ready for fuel load by late September 1986.
Preparing systems to support operation in mode 5 and readying the shift crew to control plant activities are the critical path items. Of approximately 39 technical specification (TS) systems (63 sub-systems) and 58 support systems, 42 subsystems have been declared TS operable and 77 of 97 total systems are ready to support mode 5 operation.
FSAR Review The staff's FSAR review is nearly complete. All remaining SER issues have been resolved and all but one are reported in Supplement 6 to the SER which was issued in July 1986. The remaining issues to be resolved are related to FSAR amendment and Technical Specification changes submitted by the applicant.
Hearings As a result of the resolution of all contentions, hearings on the Clinton application have been terminated.
NRR Management Assessment Meeting The NRR Management Assessment meeting to determine the applicant's readiness for issuance of a low power license was held on July 9 and 10,1986 at Clinton Power Station. NRR believes the applicant will be ready for issuance of a low power license when all the items to be completed prior to fuel load have been completed and found acceptable by the NRC staff.
. Emergency Preparedness (0nsite Plans)
The staff has completed its review of the applicant's onsite emergency response plans (through Revision 5, dated November 20,1984) for Clinton and finds an adequate planning basis for an acceptable state of emergency preparedness.
LICENSING STATUS FOR CLINTON 1 Emergency Preparedness (Offsite Plans)
The Clinton site specific Annex (Local Plan) to the Illinois Plan for Radiological Accidents-(State Plan) was submitted to FEMA for review on August 6, 1985.
FEMA completed a review of the State of Illinois emergency plan in connection with other operating nuclear power plants in Illinois, and determined that it is adequate.
Interim findings on the adequacy of the local plan were provided by FEMA on December 13, 1985. Additional revisions were submitted and FEMA provided supplemental findings on April 4, 1986 that the offsite plans are adequate.
Construction Appraisal Team (CAT) Inspection For background on this issue, please refer to the October 8, 1985, report.
Physical Security All Clinton Security Plans have been reviewed and approved. Security for onsite Special Nuclear Material (SNM) was considered adequate. Complete lock-down and implementation of the security program was initiated June 16, 1986.
Preoperational inspection of the security program have been completed and the security organization'is considered adequate to support fuel load.
Independent Design Review (IDR)
For background on this issue, please refer to the October 8,1985 report.
In SSER 6, issued in July 1983, we state that all open items and corrective actions taken by the applicant have been satisfactorily resolved.
NRC' Inspections:
A number of normal inspection items remain to be completed. These are listed below with the appropriate percentage completion as of September 1, 1986.
The staff believes adequate resources can be made available to complete them without adverse impact on the fuel load and plant startup schedule except as noted below in item 10.
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OperationQAReview(90%)
(100%)
PreopTestWitnessing(60%)
l Fuel Load Procedures Emergency Procedures (10%)
Evaluate Test Results (90%)
Verify Test Results Reviewed by Applicant (95%)
Fire Protectio'n (85%)
Testing Pipe Supports & Restraints (50%)
Liquid & Solid Waste (95%)
Chemistry (and Radiochemistry (85%)
Security 100%)
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LICENSING STATUS FOR CLINTON 1 There are also a number of other open items. These are discussed below.
1.
Construction and Preoperational Testing There are several matters requiring resolution including violations,
. unresolved items, and open items. Regional effort is being expended to resolve these matters prior to licensing.
Approximately 92.5% of acceptance / pre-operational tests have been completed. Drywell and containment structural integrity tests and containment integrated leak. rate testing were-satisfactorily completed January 2, 1986. Subsequent to this time, a hole was discovered in the containment lir.er which raised questions concerning the test results and control ~of work on the containment liner. The applicant plans to perform a confirmatory ILRT after fuel load but prior to initial criticality.
2.
Fire Protection A joint audit by NRR and Region III was conducted September 9-13, 1985.
There were one violation and twenty-three open items.
Inspections are in progress to review adequacy of resolution of open items.
3.
Radiation Protection & Radwaste The most recent inspections were conducted July 7-11, 1986. Areas requiring further licensee attention include:. preoperational testing, radiation monitor calibrations, radwaste solidification system installation, certain TMI action plan items compliance documentation (NUREG-0737 Item II.F.1, Attachments 1, 2, and 3), and ANSI N510
. acceptance test compliance documentation. All fuel load items are completed. Remaining items will be reviewed after fuel load.
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 prior to license issuance. 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 1986. A full-scale exercise was held December 4, 1985. No violations of NRC requirements were identified during the exercise. A total of six items must be resolved prior to fuel load, three prior to criticality, one prior to exceeding five percent power, and four will be examined during the October 1986 exercise.
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LICENSING STATUS FOR CLINTON 1.
5.-
Chemistry, Radiochemistry, and Confirmatory Measurements The applicant has completed confirmatory measurements comparisons necessary for license issuance. Analyses for Strontium 89 and Strontium 90 should be completed by five percent power. The applicant has completed all items required to be resolved in the chemistry and radiochemistry areas l
prior to fuel load.
j 6.
Overinspection f
On September 4, 1986, Region III replied to the applicants notification that the Overinspection Program had been concluded. Region III's closeout of the Overinspection Program is completed. Region III accepted the results of the Overinspection Program.
7.
Allegations
.There are 16 allegation files that remain open and assigned to the staff.
Most of the allegations have been reviewed in some detail,.but additional 1
inspections are required to close them out. These issues are expected to be resolved prior to fuel load.
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; j
(7 licenses: 5 SR0s and 2 R0s). The Connission policy on experience levels for SR0s, R0s and STAS is expected to be satisfied.
- 10. Post Modification / Maintenance Testing During a recent Region III inspection, the following significant concerns were identified:
(1) Failure to adequately perform post-modification i
testing; (2) non-existent post-maintenance testing; (3) Failure to adequately review maintenance work request packages; and (4) Use of improper material in performing modification / maintenance work. The l
applicant is conducting audits of the 129 modification packages and all of the maintenance work requests to determine the extent of testing that may be required to reverify preoperational test results.
Region III will evaluate the results of the applicant's findings.
This matter may influence the applicant's date for fuel loading.
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PLANT - CLINTON PM - BYRON SIEGEL (X29474)
TECHNICAL SPECIFICATIONS:
PR0OF AND REVIEW: Complete FINAL: MAY 1986 SER SSER SCHEDULE OPEN ISSUES RESPONSIBLE ORG.
CATEGORY INPUT ISSUED COMMENTS 1.
Equipment Qualification EB/ DBL 2
07/30/86 All EQ audits have been com-08/30/86
.09/21/86 pleted and issues resolved.
Awaiting staff's SSER input for seismic part of review.
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I PLANT - CLINTON I
i PM. BYRON SIEGEL (X29474) 1 TECHNICAL-SPECIFICATIONS:
i PROOF AND REVIEW: Complete j
FINAL: MARCH 1986 A
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FSAR SSER SCHEDULE OPEN ISSUES RESPONSIBLE ORG.
CATEGORY INPUT ISSUED C0pmENTS e
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I LICENSING STATUS OF BRAIDWOOD 1 L
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Braidwood l is approximately 97% complete and the applicant's current fuel load
'date is September 30, 1986. The FES was issued in June 1984. The SER was issued in November 1983. The-letter from the ACRS supporting' issuance of'an
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OL was issued on February 11, 1985. The ASLB hearings commenced on October 29, 1985.
Integrated hot functional testing began March 9,1986 and
-was completed on April 21, 1986.
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FSAR Review I
The application for the Byron and Braidwood Stations was submitted and accepted i
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; i
i therefore, the st'aff'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 nine outstanding and four confinnatory items still under review.
F Hearings j[
The Braidwood application is contested; the OL hearing is ongoing.
Initial hearings on the emergency preparedness contention were conducted on October 29, i
1985; hearings were completed for this contention on March 12, 1986. The l
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 i
the construction.of Braidwood Station. Directed Certification to the Appeal j
Board of this Order was requested by the applicant and supported by the.NRC j
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 1
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, opposed by'the intervenor. On April 23, 1986, the Commission dismissed the quality assurance contention. An additional 4
issue was accepted by the ASLB on July 23, 1985 concerning harassment, intimida-tion, retaliation and other discrimination. Hearings on this issue were held May 6-9, 1986, and were resumed on May 27, 1986; hearings will proceed continously Monday through Friday until completion. The ASLB decision is scheduled for i
September 1986, however, it may slip due to the length of the hearings.
i The applicant submitted a Motion for Authorization of Fuel Loading and l
Precritical Testing to the ASLB on August 18, 1986.
1 Construction Appraisal Team (CAT) Inspection a
i A CAT Inspection was conducted by the Office of Inspection and Enforcement j-during December 10-20, 1984 and January 7-18, 1985. The Inspection Report (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 j
identified a number of hardware deficiencies and program weaknesses as
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potential enforcement action items. These included vendor tanks and heat exchangers with deficient welds, vendor radiographs not meeting required weld 1
j or film quality requirements, failure to identify the required weld sizes for 4
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LICENSING STATUS OF BRAIDWOOD 2-pipe supports and restraints, installation o_f unqualified switchboard wire and bolts of. indeterminate material, failure to identify deficient seismic pipe support and. restraint installations, and failure to provide adequate l
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.e ec r cal separation criteria in quality control procedures. The potential enforcement actions were issued as violations by the Region in April 1985.
- The resolution of all deficiencies is being followed up by the Region.
Independent Design Review (IDR)
On April 24, 1985, the applicant submitted its plans for ensuring that all 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 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.- Open items will be followed by Region III as part of.the routine inspection program.
Region III Inspections There are approximately 194 matters which require resolution by the applicant prior to fuel load. These include open items, violations, 10 CFR 50.55(e) reportable deficiencies, allegations, unresolved items, generic letters IE Circulars, IE Bulletins, and 10 CFR 21 reports. There are also-a number of normal inspection modules that remain to be completed in the following areas (percentcompletionforeachareaisincluded):
Mechanical Components (93%)
Instrumentation (89%)
Preop QA Program (80%)
Operations QA Program (0%)
Operation Staffing Inspection (10%)
Comparison of As-Built Plant to FSAR Description (50%)
Safety Committee Inspection (0%)
Inspection of Operating Staff Training-(0%)
OperatingProcedures(40%)
Emergency Procedures (80%)
Fire Protection (10%)
Preop Test Program Records (0%)
Preop Test Program Implementation (80%)
Preop Test Procedure Review (80%)
PreopTestWitnessing(95%)
Preop Test Results Review (30%)
Radiological Environmental Monitoring (80%)
Security (25%)
RadiationProtection(95%)
Radwaste (30%)
SER Review and Followup (0%)
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LICENSING STATUS OF BRAIDWOOD Radiological and Chemical Confirmatory Measurements (20%)
Material Control and Accounting (0%)
Emergency Preparedness (80%)
Startup and Initial Fuel Loading Procedure Reviews (5%)
OL Applicant TMI Inspection Requirements (5%)
Security and Safeguards The licensee delayed implementation of full security from August 1,1986 to
' August 9, 1986. The licensee's internal audit of their security system during the week of August 18-22, 1986, disclosed significant concerns in the area of security computer reliability and guard force effectiveness, both of which could impact the issuance of a fuel load license. The licensee requested that Region III give consideration to delaying their inspection until the week of September 2,1986, so that the licensee could resolve their self-identified problem areas.
Region III's inspection during the week of September 2, 1986, disclosed significant deficiencies in the area of protected and vital area access controls, security computer reliability, and security system power supply, that must be resolved prior to fuel load.
Inspection will continue the week of September 15-19, 1986.
Radiation Protection and Radwaste The most recent inspection was conducted August 18-28, 1986. There are presently seven open items. None of the open items will affect the fuel load date.
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. Sixt'een of seventeen Senior Reactor Operators, and six of six Reactor Operators passed. The second group of operator examinations was completed in August 1986. Twelve of seventeen Senior Reactor Operators, and seven of eight Reactor Operators passed.
Allegations There are fifteen open allegation files which require Region III action. These issues are expected to be resolved prior to fuel load.
01 Investigations The Office of Investigations has four (three applicant plus one vendor case) open investigation files. These items will be pursued and should not affect fuel load.
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t LICENSING STATUS OF BRAIDWOOD 4 Fire Protection The NRR Site Audit and the Region III Appendix R Team inspection were conducted-
- during during the week of August -18,1986. One special inspection was conducted to' assess the ap911 cant's conformance to fire protection' requirements for receipt and storage of new fuel-onsite.
i 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
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October 15, 1985; the final BCAP report was issued on November 14, 1985, by Coninonwealth 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.
The Emergency Preparedness Implementation Appraisal was conducted on May 29 -
June 13, 1986. The associated report, issued July 22, 1986, contained 38 Open Items, the majority of which had -fuel. load as the due date for completion of corrective actions. These items include: completion of several emergency i
facilities;. readiness of equipment utilized by emergency response personnel; it and completion of initial and remedial training by various types of emergency response personnel (inclu~ ding SEs, SF, and SCREs). The licensee's fonnal response.on each Open Item and Improvement Item was received in late August, and the week of September 15 was agreed upon as being timely for the first followup inspection on fuel load Open Items.- However, since-the licensee's response for a number of fuel load items indicated corrective _ action j
completion dates of " fuel load" or "by September 30," multiple followup inspections are inevitable before all fuel load items can be closed.
4 The SER supplement which covers Chapter 13.3 (Emergency Planning) was issued in March 1986. Region III has submitted a second SER supplement which is undergoing staff review. On April 30, 1986, FEMA issued an interim finding that offsite emergency planning for the Braidwood Station provided " reasonable assurance that the health and safety of the public can be protected."'
The applicant successfully conducted an exercise of its emergency plan on November 6, 1985. The FEMA evaluation of State and local offsite plan implementation, issued April 3,1986, was prepared separately from the staff's evaluation'of the applicant's performance. No deficiencies were identified by FEMA.
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Plant: Braidwood Station, Unit 1 PM:
J. A. St:v:ns (x 27702)
Technical Specifications:
Proof and Review: Completed Final (Appendix A Version): September 23, 1986 FSAR SSER Schedule OPEN ISSUES Responsible Org.
Category Input Issued Comments 1.
Pump and valve operability EB 3
9/15/86 9/30/86 Applicant to submit
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response by 9/1/86.
2.
Seismic and dynamic quali-EB 3
9/15/86 9/30/86 Applicant to submit fication of equipment additional information by 8/25/86.
3.
Environmental qualification EICSB 3
9/15/86 9/30/86 Applicant to respond to of electrical and mechanical IE 86-02 & IE 86-03 by equipment 8/20/86 and IE 84-90 by 9/1/86.
4.
Organizational Structure F0B 3
9/15/86 9/30/86 Applicant to complete Shift Experience Program by 8/29/86.
5.
Emergency preparedness EPB 3
9/15/86 9/30/86 Applicant has responded to plans and facilities open items in EP Implemen-tation Appraisal Report on 8/21/86.
6.
Procedures generation F0B 2
9/15/86 9/30/86 Contractor's review package (PGP)
. schedule must be accelerated.
7.
Control room human factors EICSB 3
9/15/86 9/30/86 PDA for site-specific review items'under review; survey for environmental. systems to be submitted prior to criticality (10/31/86).
8.
Conformance of ESF filter PSB 3
9/15/86 9/30/86 Applicant to provide addi-'
tional information on devia-tions from RG 1.52 & 1.140 by 8/25/86.
9.
Fire Protection Program PSB 3
9/15/86 9/30/86
' Complete NRR Site Audit 8/29/86 and RIII' Appendix R Team Inspection by 8/22/86.
' Plant: Braidwood Station, Unit 1 PM:
J. A. Stevens (x 27702)
Technical Specifications:
Proof and Review:
Completed a
Final (Appendix A Version): September 23, 1986 FSAR SSER Schedule Confirmatory Issues Responsible Org.
Category Input Issued Comments 1.
Applicant compliance with the PD 5 3
9/15/86 9/30/86 Applicant to submit Commission's regulations by 9/1/86.
2.
Preservice inspection EB 2
9/15/86 9/30/86 Applicant to submit program results of UT exams 1
for cast S. S. by 9/1/86.
3.
Electrical distribution RIII 3
9/15/86 9/30/86 RIII to issue system voltage verification inspection report by t
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4.
Inservice testing of pumps RSB 3
9/15/86 9/30/86.
9/15/86.
Applicant to submit i
and valves differences from Byron l
by 8/20/86.
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Plant: Braidwood Station, Unit 1 PM:
J. A. Stevens (x 27702)
Technical Specifications:
Proof and Review: Completed Final-(Appendix A Version): September 23, 1986 FSAR SSER Schedule License Conditions Responsible Org.
Category Input Issued Comments 1.
Inservice inspection program EB 3
Applicant will submit ISI program 12 months prior to ist refueling outage.
2.
Natural circulation testing SOSI 3
Issue must be resolved prior to startup following 1st refueling outage..
3.
Masonry walls EB 3
9/15/86 9/30/86 Applicant will submit crack survey results by 8/25/86.
4.
Fire Protection Program PSB 3
Standard L. C.
Plant: Braidwood Station, Unit 1 PM:
J. A. Stevens (x 27702)
Technical Specifications:
Proof and Review: Completed Final (Appendix A Version): September 23, 1986 SSER Schedule Other Issues Responsible Org.
Category Input Issued Comments 1.
Jet Impingement EB/PSB 3
8/29/86 9/30/86 Submittal dated 7/2/86 under review.
2.
Antitrust Review PRAB 3
FR Notice issued 8/15/86.
3.
Technical Specifications F0B 3
Issue Final Draft by 8/22/86.
4.
Environmental Protection Plan EB 3
9/15/86 9/30/86 Submittal dated 3/3/86 under review 5.
Post-Accident Control Room PSB 3
9/15/86 9/30/86 Submittal dated 4/1/86 Habitability Analysis under review.
6.
Variance for Interim Operation PSB 3
9/15/86 9/30/86 Applicant to submit for Aux. Bldg. Vent. System variance request by 8/22/86.
7.
Startup Test Program F08 3
9/15/86 9/30/86 Applicant to submit additional information by 9/1/86.
8.
Integrated Leak Rate Tests EB 3
9/15/86 9/30/86 Applicant to submit ILRT (type A) test results by 8/20/86.
i-LICENSING STATUS OF BYRON 2 Byron 2 is approximately' 95% complete and the applicant's current fuel load date is October 15, 1986; however, this may be optimistic since licensee projections are late November,1986. Byron 2 is essentially identical to Byron I 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 licens_ing of Byron 1 applies to P
Byron 2.
Only very few unit-specific items, such as staffing and pre-service
-inspection, need to be completed.
i Hearings The hearings that were completed prior to licensing of Byron 1 applied to Byron
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- 2. There are no further hearings anticipated prior to licensing Byron.2.
Review and evaluation of emergency plans are complete. All outstanding emergency preparedness related SER items have been resolved.
I Construction Appraisal Team (CAT) Inspection l
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 i
meeting construction requirements was identified. A Notice of Violation containing three items was issued to the applicant on December 12, 1985. The 4
response received on January 24, 1986 and April 9, 1986 have been reviewed by the Region and IE, and the Region is monitoring the applicant's corrective actions.
t Independent Construction-Verification i
A R-I NDE van inspection was conducted October 28 to November 8, 1985,
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providing independent verification of construction activities and materials i
through records review and nondestructive examinations. The inspection report was issued December 18, 1985; no major concerns in the NDE area were
' dentified.
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Independent Design Review
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On April 24, 1985, the applicant submitted its plans for ensuring that all l
applicable corrective actions resulting from the Byron 1 IDI, Byron 1 IDR, and
[
the Clinton 1 IDR 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 report was issued on April 2, 1986 and concluded that corrective actions were being implemented although three items still required follow-up i
of completion. These will be followed by Region III as part of the routine inspection program.
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LICENSING STATUS OF BYRON 2 Region III Inspections There are approximately 95 matters which require resolution by the applicant prior to fuel load. These include open items, violations, 10 CFR 50.55(e).
reportable deficiencies, allegations, unresolved items, IE Bulletins and 10 CFR 21 reports.
'There are also a number of normal inspection modules that remain to be completed in the following areas (percent completion for.each area is included):
Review of as-builts (90)
Electrical components and cable (100)
Instrumentation (100)
Structural integrity) test (CILRT) (50)
Preop QA program (70 Comparison of as' built plant to FSAR (20)-
Preoptestprogramrecords(0)
Plant procedures (50)
Operatingprocedures(50)
Emergency procedures (0)
Fire protection (20)
Preoptestprogramimplementation(50)
Preoptestwitnessing(90)(5)
Preop test results review Technical Specifications review (20)
Radiological Environmental monitoring (30)
Security (10)
Radiationprotection(40)
Radwaste (35)
Radiological and chemical confirmatory measurements (70)
SERreviewandfollowup(70)
Operator Licensing The first group of operator examinations were administered in July 1986.
Exams were completed during the week of August 25; results are being evaluated.
Preoperational Testing As a result of the applicant's Byron 1 Lessons Learned Program and an NRC inspection conducted in early December of the applicant's Preoperational Testing Program, Region III plans no further inspection of the Preop Test Program. The inspection basis for this decision is documented in Inspection Report 455/85045. Region III will conduct normal inspections of preoperational tests and test results. Preoperational testing of the Emergency Core Cooling System (ECCS) at full flow was completed February 25, 1986. Hot functional testing is complete.
Integrated Leak Rate Testing is complete.
LICENSING STATUS OF BYRON 2 Security The June 1986 security preoperational inspection disclosed no significant concerns that could impact on fuel load. There are 14 open items which must be closed prior to fuel load. The next security preoperational inspection is scheduled for the week of September 29, 1986.
Initial security lockdown for Unit 2 occurred on September 1, 1986.
Allegations There are five allegations open at Byron applicable to Unit 2.
They are expected to be closed in the next few months. There are no issues which would impact fuel load.
Investigations There are no open 01 cases involving Byron 2.