ML20154H993

Forwards Updated Plant Licensing Status for Perry 1, Clinton 1,Braidwood 1 & Byron 2 as of 860228

ML20154H993
Person / Time
Site:	Perry, Byron, Braidwood, Clinton, 05000000
Issue date:	03/05/1986
From:	Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:	Funches J Office of Nuclear Reactor Regulation
References
NUDOCS 8603100430
Download: ML20154H993 (20)

Text

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'Dr*f B MAR 0 51986 MEMORANDUM FOR: Jesse L. Funches, Director, Planning and Program Analysis Staff, NRR FROM: Charles E. Norelius, Director, Division of Reactor Projects, RIII

SUBJECT:

NTOL PLANT LICENSING STATUS - REGION III Enclosed is the updated plant licensing status for Perry 1, Clinton 1, Braidwood 1, and Pyron 2. This information is current as of February 28, 1986.

Should you or your staff have any further questions please contact R. C. Knop, T. P. Gwynn, W. S. Little, and W. L. Forney respectively, for the plants above.

" Original signed bf E.G. Green:::m

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 ,.

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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 FES issued (NUREG-0854) April 1982 SER issued (NUREG-0853) February 1982 LastSERSupplement(SSER-5) January 1986 IP fuel load (licensing) date Late March 1986 Caseload Forecast Panel projected fuel load date First Quarter 1986 Clinton was approximately 99% complete on January 31, 1986. The majority of bulk construction is complete; all systems have been torned over to IP. There are approximately 25,000 open items on IP's master punch list; about 11,500 fuel load items. The applicants critical path analysis forecasts April 13, 1986 as the fuel load date. Region III believes this date is optimistic. Plant fire protection is the critical path item. Preop test activity remains behind schedule.

FSAR Review The staff's FSAR review is nearly complete. Six outstanding and four confirma-tory issues remain to be resolved. However, IP has recently submitted two amendments (35 and 36) that total over 5000 pages and reflect the results of an FSAR Certification Program. These amendments have to be reviewed by the staff prior to fuel load. In addition, IP is in the process of submitting system deferrals and preoperational test deferrals for staff review. A program similar to one submitted by Hope Creek to accelerate the start-up test program is under staff review.

Hearings As a result of the resolution of these contentions, hearings on the Clinton application have been terminated.

Emergency Preparedness (0nsite Plans)

The staff has completed its review of the applicant's onsite emergency response plans (through Revision 4, dated December 15,1984) for Clinton and finds an adequate planning basis for an acceptable state of emergency preparedness.

Revision 5, dated November 20, 1985, is being reviewed.

W - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _

LICENSING STATUS FOR CLINTON 1 Emergency Preparedness (Offsite Plans)

The radiological emergency response plans of the State and local governments are still under revision. 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 has already 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 are required and FEMA will provide supplemental findings in March 1986. I Physical Se'curity All Clinten Security Plans have been reviewed and approved. Security for onsite Special Nuclear Material (SNM) was considered adequate. Additional inspections are scheduled for March 1986. Full implementation date for the security program is unknown. Several past proposed implementation dates have been postponed by the applicant.

Audits A SQRT and PVORT audit was performed August 20-23, 1985. Based on the results of this audit, a PV0RT reaudit was required. Staff meetings were held in Bethesda on September 26 and October 21 with the applicant to discuss a PV0RT recovery program. The PVORT reaudit was performed November 18-21, 1985. Based on the SQRT and PV0RT audits an issue related to the use of test versus analysis for the qualification of the operability of valves has surfaced. The staff performed an additional audit on January 28 and 29, 1986 at the Sargent and Lundy Offices in Chicago, Ill. Preliminary results indicate more work is required to resolve this issue for both SQRT and PVORT.

Detailed Control Room Design Review (DCRDR)

The Clinton DCRDR Summary Report was docketed on September 20, 1985. A pre-

, implementation audit to review DCRDR results and planned control room improve-

> ments was performed October 28-November 1, 1985. The staff's safety evaluation determined the requirements of NUREG-0737 have been satisfied subject to com-pletion of certain actions by the applicant as identified in the safety evaluation.

HRC Inspections:

A number of normal inspection items remain to be completed. These are listed below with the appropriate percent completion as of February 1986. The staff believes adequate resources can be made available to complete them without adverse impact on the fuel load and plant startup schedule.

J

LICENSING STATUS FOR CLINTON 1

• Operation QA Review (70%)

Preop Procedures Review (95%)

(70%)

• Preop Test Fuel Load hitnessing(50%)

Procedures Emergency Procedures (0%)

Evaluate Test Results (25%)

Verify Test Results Reviewed by Applicant (28%)

Fire Protection (50%)

Testing Pipe Supports & Restraints (50%)

Radiation Protection (95%)

Liquid & Solid Waste (95%)

Gaseous Waste (95%)

Radiochemistry (30%)

Environmental Monitoring (30%)

Security (40%)

Emergency Preparedness (90%)

There are also a number of other open items. These are:

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 62% of acceptance / pre-operational tests have been completed.

Drywell and containment structural integrity tests and containment inte-grated leak rate testing were satisfactorily 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 containment liner. This issue is being pursued with the applicant.

2. Fire Protection A joint audit by NRR and Region III was conducted September 9-13, 1985.

There was one violation and twenty-three open items. A reinspection was completed in January 1986. Additional inspections are scheduled; the Appendix R inspection is scheduled to begin March 31, 1986.

3. Radiation Protection & Radwaste The most recent inspection was conducted January 27-31 and February 18-21, 1986. Areas requiring further licensee attention include: procedure revisions, gaseous radwaste system preoperational testing, radiation monitor calibrations, radwaste solidification system installation, certain TMI action plan items' compliance documentation (NUREG-0737 Items.II. L.3 and II.F.1, Attachments 1, 2, and 3), and ANSI N510 acceptance test compliance documentation.

LICENSING STATUS FOR CLINTON 1 4. Security The implementation status for the Personnel Screening Program to allow unescorted access to vital areas is the current most significant open item in the area of security. Problems encountered in planned implemen-tation of the security program in October and November 1985 also warrant site management oversight. The security computer system's capability to meet the security plan commitments cannot be adequately determined until the security access control / alarm monitoring program is fully implemented by the applicant.

5. Emergency Planning The pre-operational EP inspection 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. An exercise was held December 4, 1985.

6. Radiochemistry and Environmental Monitoring In order to demonstrate readiness in Radiochemistry and Environmental Monitoring (REMP) for an NT0L, the applicant must perform a confirmatory measurements program, demonstrate the competence of the chemical staff and technicians by completing formal and on-the-job training and accurately analyzing radiological and nonradiological-spiked samples, implement a QA/QC program in the laboratory and counting room, complete facilities for laboratories and counting room, calibrate counting equipment and fully implement the REMP. These activities are currently being implemented.

The current inspection will be completed the first week in March 1986.

7. Overinspection On November 15, 1985, the applicant requested Region III's concurrence in terminating the Record Verification Program; RIII denied the request on December 12, 1985; on January 22, 1986, the applicant submitted a letter wherein it is stated that the Records Verification Program will be suspended on February 3, 1986 at the applicant's risk. An inspection was conducted the week of January 27, 1986.

On January 16, 1986 the applicant notified Region III that the Electrical Cable Tray Hanger Reinspection was completed.

8. Allegations There are 13 allegation files that remain open. 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 prior to fuel

! load.

i 1

LICENSING STATUS FOR CLINTON 1 9. 01 Investigations There are six outstanding investigations.

10. 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). The final group of examinations was completed in January 1986 and licenses were issued in February 1986,(10 licenses: 3 SR0's and 7 R0's). The licensee has requested additional examinations which have not yet been scheduled due to manpower limitations. The Commission policy on experience levels for SR0s, R0s and STAS is expected to be satisfied.

PLANT - CLINTON PM - BYRON SIEGEL (X29474)

TECHNICAL SPECIFICATIONS:

PROOF AND REVIEW: Complete FINAL: MARCH 1986 FSAR SSER SCHEDULE OPEN ISSUES RESPONSIBLE ORG. CATEGORY INPUT ISSUED COMMENTS

1. Equipment Qualification EB/ DBL 2 02/15/86 03/31/86 All EQ audits have been com-completed. Staff waiting for applicant to submit in-formation on open issues.

Related to SQRT and PV0RT staff still has not resolved concern of test versus analyses to qualify oper-ability of valves. Staff and applicant are trying to resolve this issue.

2. Suppression Pool Hydro- PSB/ DBL 3 02/28/86 03/31/86 Awaiting SER from reviewer.

dynamic Loads

3. Humphrey Containment Issues PSB/ DBL 3 02/28/86 03/31/86 Awaiting SER from reviewer.

4. Remote Shutdown, Com- EICS/ DBL 3 02/28/86 03/31/86 Awaiting SER from reviewer.

pliance GDC19

5. Control Systems Failures EICS/ DBL 3 03/15/86 03/31/86 Staff has to review issue.

From HELB

6. ATWS Recirculation Pump EICS/ DBL 3 02/28/86 03/31/86 Awaiting SER from reviewer.

Trip

7. IST EB/ DBL 3 02/28/86 03/31/86 Issue under review by staff.

I PLANT - CLINTON PM - BYRON SIEGEL (X29474)

TECHNICAL SPECIFICATIONS:

PROOF AND REVIEW: Complete FINAL: MARCH 1986 SSER SCHEDULE FSAR RESPONSIBLE ORG. CATEGORY INPUT ISSUED COMMENTS OPEN ISSUES 3 02/28/86 03/31/86 Awaiting SER from PSB

8. Jet Impingement and Pipe PSB/ DBL Rupture Analysis 3 02/28/86 03/31/86 Awaiting SER from EPB

9. Offsite Emergency EPB/IE Preparedness Programs

10. Meteorological Measure- EPB/IE 3 02/28/86 03/31/86 Awaiting SER from EPB ments Program

.: s .' .

LICENSING STATUS OF BRAIDWOOD 1 Braidwood 1 is approximately 90% 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 OL was issued on February 11, 1985. The ASLB hearings commenced on October 29, 1985.

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.

Although there are a number of outstanding (9) and confirmatory (6) items under review, the principal items of concern are: (1) emergency preparedness plans and facilities, and (2) fire protection program.

Hearings The Braidwood application is contested; the OL hearing is divided into three sessions commencing on October 29, 1985, March 11, 1986, and May 6, 1986, respectively. Initial hearings on the emergency preparedness contention were conducted on October 29, 1985; hearings are expected to be completed for this contention on March 11, 1986. 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 has 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 and is pending before the Commission for a decision. The NRC staff filed responses to Commission questions concerning this request on December 19, 1985. An additional issue was accepted by the ASLB on July 23, 1985 concerning harassment, intimidation, retaliation and other discrimination. The hearing on the QA contention is scheduled to begin May 6, 1986. The applicant submitted a motion for sumary disposition for several of the QA contention subparts which the staff supported by affidavits filed February 14, 1986. The ASLB has not made a decision on this 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 (50-456/84-44; 50-457/84-40) was issued February 20, 1985. Although construc-I

e LICENSING STATUS OF BRAIDWOOD 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 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. The potential enforcement actions were issued as violations by the R:gion in April 1985. The resolution of all deficiencies is being followed up by the Region.

Independent Design Verification Program (IDVP)

On Apr l1 24,1985, the applicant submitted its plans for ensuring that all appliuole 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.

Region III Inspections There are approximately 300 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 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 (percent completion for each area is included):

Mechanical Components (84%)

Instrumentation (80%)

Containment Structural Integrity Test (0%)

Preop QA Program (80%)

Operations QA Program (0%)

Operation Staffing Inspection (10%)

Comparison of As-Built Plant to FSAR Description (20%)

Safety Committee Inspection (0%)

Inspection of Operating Staff Training (0%)

Plant Procedures (0%)

Operating Procedures (30%)

Maintenance Procedures (0%)

Emergency Procedures (5%)

Fuel Receipt and Stora Fire Protection (20%) ge (80%)

l I

l.,.*.

LICENSING STATUS OF BRAIDWOOD

• Preop Test Program Records (0%)

Preop Test Program Implementation (65%)

Preop Test Procedure Review (48%)

Preop Test Witnessing (54%)

Preop Test Results Review (22%)

Technical Specifications Review (10%)

Radiological Environmental Monitoring (0%)

Security (10%)

• - RadiationProtection(70%)

Radwaste (10%)

Radiological and Chemical Confirmator

• Material Control and Accounting (5%) y Measurements (0%)

Emergency Preparedness (5%)

Security and Safeguards All security plans have been reviewed and approved. Two inspections have been conducted to date. The licensee will be required to have their security plan fully implemented prior to fuel load. It is too early to determine whether significant security problems exist which may impact on fuel load.

Radiation Protection and Radwaste The most recent inspection was conducted August 19-23, 1985. There are presently 5 open items. It is too early to determine whether significant problems exist which may impact on fuel load. The next inspection in this area is scheduled for March 1986.

Operator Licensing Confirmation that the senior reactor operators have obtained the requisite experience on shift is required. The first group of operator examinations is currently scheduled for April 1986. The second group is scheduled for July 1986.

Allegations There are sixteen 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 six open investigation files. These items will be pursued and should not affect fuel load.

LICENSING STATUS OF BRAIDWOOD Fire Protection The NRR Site Audit and the Region III Appendix R Team inspection are scheduled to be conducted by June 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.

Emergency Preparedness, The Region III pre-appraisal visit was conducted on September 24, 1985. Based on the applicant's current schedule for completing training for all persons assigned positions in the onsite emergency organization and, to a lesser extent, the installation status of the system for collecting coolant and containment air samples, a two week period beginning in late May has been tentatively scheduled for the Emergency Preparedness implementation Appraisal.

The offsite emergency plan is under review by FEMA; interim findings were issued by FEMA on November 20, 1985. FEMA estimates that the final version of the offsite emergency plans will be submitted by March 1986 and a supplemental finding will be provided to the NRC by late May 1986. Region III has completed the draft SER supplement which covers Chapter 13.3 (Emergency Planning).

The applicant successfully conducted an exercise of its emergency plan on November 6, 1985. The FEMA evaluation of State and local offsite plan implementation is being prepared separately from the staff's evaluation of the applicant's performance.

LICENSING STATUS OF BYRON 2 Byron 2 is approximately 83% complete and the applicant's current fuel load date is October 15, 1986; however, this may be optimistic. 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. Only very few unit-specific items, such as staffing and pre-service inspection, need to be completed.

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.

Independent Construction Verification An IE CAT inspection was perfomed 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 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. On April 24, 1985, the applicant submitted its plans for ensuring that all applicable cor-rective actions resulting from the Byron 1 101, 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.

Region III Inspections There are approximately 82 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):

. Reviewofas-builts(50)

LICENSING STATUS OF BYRON 2 .

HVAC(80)

. Electrical components and cable (74)

Instrumentation (67)

. Structural integrity)

Preop QA program (50 test (0)

. Comparison of as-built plant to FSAR (90)

. Preop test program records (0)

. Plant procedures (50)

. Operating procedures (50)

. Maintenance procedures (30)

. Emergency procedures (0)

. Fuel receipt and storage (20)

. Fireprotection(20)

. Preoptestprogramimplementation(50)

. Preop test witnessing (10)

. Preop test rasults review (5)

. Technical Specifications review (20)

. Radiological Environmental monitoring (0)

. Security (0)

. Radiationprotection(40)

Radwaste(25)

Radiological and chemical confirmatory measurements (50)

. Material control and accounting (0)

. SER review and followup (0)

Operator Licensing The first group of operator examinations is currently scheduled for July 1986.

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 procedure development area. 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.

Security The security plans reviewed and approved during the licensing of Byron 1 also apply to Byron 2. Minimum review will be necessary. The SER supplement will indicate this fact.

Allegations There are six allegations open at Byron. They are expected to be closed in the next few months. There are no issues which would impact fuel load.

LICENSING STATUS FOR PERRY 1 Perry 1 is a BWR/6, Mark III containment designed plant in the final stages of the licensing review process. The Cleveland Electric Illuminating Company I (CEI) tendered an application for an Operating License (0L) on January 31, 1981.

The FES was issued in August 1982. The SER was issued in May 1982 with the latest supplement (No. 8) issued in January 1986. CEI is working to a fuel load date of early March, 1986. They are awaiting the completion of the staff's '

assessment of the earthquake impact on the Perry design (which occurred on l January 31,1986). l FSAR Review The staff's FSAR review is essentially complete. All outstanding SER items have been resolved and documented in SSER No. 8 issued in January 1986. A separate SER supplement will be issued prior to licensing addressing the impact of the January 31, 1986 earthquake on the Perry plant seismic design. Licensing of Perry 1 has been delayed pending completion of the staff's assessment of this event.

The Technical Specifications were issued to the applicant for certification on November 19, 1985. Additional changes including deletion of fire protection ,

were issued for certification by CEI.  !

Hearings The ASLB hearings were initiated in May 1983, during which time the QA Con- ,

struction issue was litigated. A favorable initial Board decision was issued  !

on December 2, 1983, and was appealed by the intervenor (Sunflower Alliance). l 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 .e opplicant: emergency planning - 4 items; TDI diesels - 1 item; and hydrogen control - 2 items. 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 OCRE on December 12, 1985. A motion to admit a new contention relative to the earth-quake impact on the Perry seismic design was also filed by OCRE.

2.206 Petition A Petition was filed by Susan Hiatt of the Ohio Citizens for Responsible Energy (OCRE) on February 3, 1986. This Petition requests that the NRC not permit fuel loading 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).

LICENSING STATUS FOR PERRY 1 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.

The staff is currently reviewing these petitions.

Construction Appraisal Team (CAT) Inspection A CAT inspection was conducted by the Office of Inspection and Enforcement on August 22-September 2 and September 12-23, 1983 at Perry Units 1 and 2. The Inspection Report (50-440/83-31; 50-441/83-30) issued on November 7, 1983 noted no pervasive failure to meet construction requirements but did identify nine potential enforcement actions. A Notice of Violation containing three viola-tions was issued to the applicant. These matters have been reviewed by the Region and subsequently closed.

Integrated Design Inspection (IDI)

The NRC's Office of Inspection and Enforcement conducted an IDI at Perry and related facilities during the period of August 6 to October 12, 1984. The inspection report (50-440/84-29) was issued December 12, 1984. The applicant responded to the inspection report on January 24, 1985. IE letter dated February 25, 1985 comments on the applicant's January 24 response and a followup inspection team visit to the Perry Architect Engineer was conducted during the week of February 25, 1985. IE's followup inspection report dated March 26, 1985 indicated that 13 open items remain to be settled, primarily in the electrical design area. A further audit was conducted in May 1985, during which these remaining 13 open items were closed, with some followup required in the electrical system area by the regional staff to verify implementation. The IDI inspection is considered to be closed with all items satisfactorily resolved.

Region III Inspections There are about six matters requiring resolution by the applicant. These include: open items, violations, construction deficiency reports (10 CFR 50.55(e)), and responses to circulars and bulletins.

There are also a number of normal :nspection items that remain to be completed (percent completion for each item is included):

witnessing of preop tests (96%)*

l.ICENSING STATUS FOR PERRY 1

• evaluation of test results (94%)*

• verification that test results are reviewed by the licensee (98%)*

• These inspection items will remain open beyond fuel load due to deferred test.

There are a number of other open inspection items. These are:

1. Construction and Preoperational Testing Preoperational test phase is approximately 95% complete. The overall status of the test program is listed below. NOTE: Included in the status below are tests which the applicant has identified as not required prior to fuel load.

Test Results Test Results No. Approved Verified Tests CEI By NRC Preoperational Tests 106 102 85*

Acceptance Tests 118 115 83*

The region held a management meeting on June 3, 1985 with the licensee to discuss precoerational test program deficiencies in the area of test pro-cedure adequacy, test conduct and commitment implementation. The licensee committed to extensive corrective actions which Region III has followed and evaluated. Although these corrective actions were slower than expected in manifesting themselves in actual program conduct, more recent inspections show that they appear to have been effective. Therefore, problems with the preoperational test program are no longer of major concern.

• The NRC review of pre-fuel load rea.uired test results is complete.

2. Radiation Protection and Radwaste No significant RP or RW problems that might impact on the licensing process are being carried as regional open items. Several matters including use of silicone sealant on ventilation duct work and licensee requests for deviation from NUREG 0737 items are being considered by NRR.

3. Emergency Preparedness An Emergency Preparedness Implementation Appraisal (EPIA) was conducted in March 1985, and follow-up inspections were conducted in July, September, and November 1985. All appraisal items were closed, except for two items required to be completed before criticality. In addition, one bulletin item remains to be resolved prior to criticality, and a plant first aid facility must be completed before removing the construction crew medical office.

I l LICENSING STATUS FOR PERRY 1 l l A full participation exercise which is required to be conducted within one year and prior to exceeding 5% power was conducted in November 1984. A l partial participation exercise was conducted in November 1985. An exemption l request has been submitted to the Commission in the event the plant is

! ready to exceed 5% power before the next full participation exercise, l which is scheduled for April 1986.

i By letter dated February 4, 1986, FEMA has confirmed that two Board

( conditions have been completed satisfactorily. This confirmation will be provided in a future supplement to the SER prior to authorization to exceed 5% of rated power.

! 4.. Security l The last security inspection was conducted the week of December 2, 1985, l

which closed all remaining modules. No violations were identified and all

! previous violations have been satisfactorily addressed and are considered I closed. There are no known security issues which would preclude issuance i

of a license.

5. Fire Protection l In December 1985, Region III completed its pre-licensing inspection activi-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.

6. Earthquake Damage Review An earthquake occurred on January 31, 1986, at an epicenter 10 miles l

south of the Perry site. the earthquake had a magnitude of approximately l

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 i damage to the plant as a result of the earthquake.

On February 12, 1986, CEI provided an assessment of the earthquake and it's impact on the plant. That report concluded that the impact of the earthquake would not alter any of the design or licensing basis. That report with its conclusions is currently being evaluated by NRR for any design basis impact.

Allegations There are currently seven allegation files on Perry being pursued by the staff, and are expected to be closed in the next few weeks.

One of the allegation files consists of 48 allegations received as part of the February 4, 1986, 2.206 petition from Western Reserve Alliance (WRA).

An initial inspection was conducted during the week of February 16 and February 23, 1986.

LICENSING STATUS FOR PERRY 1 All of these allegations, including WRA 2.206 allegations, have been reviewed in some detail and no significant problems have been identified, which would preclude issuance of a low power license.

01 Investigations The Office of Investigations has three investigations underway regarding Perry.

These items are being pursued and are not expected to impact fuel load.

Operating Shift Experience By letter dated February 6, 1985, the applicant updated experience tables (initially provided in March 1984) reflecting nuclear power plant experience for operating shift positions at Perry. The tables reflect current and projected staffing experience levels at the time of Perry 1 fuel load.

At this time, no impact on licensing and availability of qualified operators is expected. Additional operator examinations were conducted during the week of December 9, 1985. Fifteen additional licenses were issued.

1

NAME OF FACILITY DATE MAILED .

REPORT NUMBERS gPRPDISTRIBUTION ,

NUMBER OF REPORTS TO BE REPRODUCED LETTER W/ CONCURRENCES W/ REPORT LETTER W/0 CONCURRENCES W/ REPORT REPORT ONLY NINBER OF THANK YOU LETTERS TO BE REPRODUCED LETTERW/CONCURRENCESW/RESPONSEFkOMLICENSEE LETTER W/0 CONCURRENCES W/ RESPONSE FROM LICENSEE LETTER ONLY W/0 CONCURRENCE COPIES WITH CONCURRENCES DMB/ DOCUMENT CONTROL DESK (RIDS)

REGION III FILES DPRP DIVISION FILES ~

RESIDENT INSPECTOR

• MIS /L. SUCHARSKI .

DEP DRMSP KEPPLER/ DAVIS COPIES WITHOUT CONCURRENCES P. ANDERSON K. GRAESSER T. MURRAY L. BECK J. CUDAC J. PARKYN R. CALLEN D. HOFntAN T. QUAKA M. CHERRY D. HINTZ R. QUERIO

_ D. CHEVEZ T. HOUVENACLE R. QUILLAN

_ R. COSARO N. KALIVIANKIS V. SCHLOSSER T. DAITILLO J. KODNER J. SCHOTT C. DIEDERICH H. KOHN D. SCOTT K. DREY LeBOUEF, LAMB, L. SHAMBLIN J. DUTTY LEIBY & MACRAE W. SHAMLA H. EVANS W. MARSHALL M. SINCLAIR D. FARRAR D. MARTIN C. SORENSEN J. FERMAN E. MARTIN J. SPENCER R. FLUECCE M. MILLER B. STAMIRIS S. CADLER D. MINECK B. STEPHENSON J. CALLOWAY R. MONTROSS H. VOICHT OVER--*

J. VENNEMANN E. WATZL W. WEBER D. WELLS D. WILT G. WRIGHT

• J. WALDRON M. VETTERHANN

s. YORK K. BORCSTADT W. SMITH EIS COORDINATOR, USEPA (D. C. COOK REPORTS ONLY)

J. FLYNN ,

CARE (CITIZENS AGAINST A RADI0 ACTIVE ENV.)

T. APPLEGATE .

G. HUMMEL J. WILLIAMS R. HOLY 0AK -

D. VANDEVALLE C. BECHHOEFER J. HARBOUR F.COWAN R. DECKER W. PATON S. MILTENBERGER J. ZACH e

n

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