ML20246C900
| ML20246C900 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Catawba |
| Issue date: | 07/05/1984 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20246C819 | List: |
| References | |
| FOIA-89-226 NUDOCS 8908250173 | |
| Download: ML20246C900 (9) | |
Text
u 4
JUL 051984 j
i MEMORANDUM FOR:
Harold R.-Denton, Director Office of Nuclear Reactor Regulation j
FROM:
James P. O'Reilly, Regional Administrator l
SUBJECT:
DUKE POWER COMPANY'S CATAWBA UNIT 1, DOCKET NO. 50-413, STATUS OF FACILITY COMPLETION l
i Based on the implementation of the prescribed NRC inspection program and other related inspection activities we have determined that construction and preopera-tional testing of Catawba Unit 1 Nuclear Station have been completed in accordance with the FSAR, other docketed commitments and regulatory requirements with the exceptions listed in this memorandum and in the enclosures.
Region II has requested and received from Duke Power Company (DPC) the status of completion letter dated June 11, 1984, and supplements dated July 2 and 3,1984. We noted the extensive reviews performed by DPC regarding the completion of construction,
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preoperat tonal testing and readiness for operation.
The letters are acceptable and consistent with our findings with the exceptions noted below.
Based on the satisfactory resolution of the items below, we recommend issuance of a fuel load and precritical testing license.
1.
Emergency Diesel Generators are undergoing an extensive disassembly and inspection program. DPC has applied for an Exemption to GDC 17.
Region II supports granting of this exemption up to the time of initial criticality since no fission product inventory or decay heat exists until this time.
1 Region 11 recommends a license condition to address post inspection testing i
verification by Region II.
(See Enclosure 3, Item G.7) 2.
Region II concludes that, due to the omission of certain vital areas pre-sently not identified in the security plan, 10 CFR 73 requirements have not been fully met.
In our view, an exemption is required; however, we do not recommend an exemption beyond initial criticality.
3.
Ice condenser testing and erection of steel removed during ice loading
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remain to be completed.
DPC commits to complete this work, prior to increasing reactor coolant temperature above 200'F which is consistent with technical specifications.
A license condition is recommended to require verification of ice condenser testing and associated steel erection by Region II prior to reactor coolant temperature exceeding 200'F.
(See ).
4.
Carbon filter loading and testing needs to be completed prior to placing the following systems in service in accordance with applicable technical specifications or as noted.
Auxiliary Building Filtered Ventilation Exhaust System (Mode 4 - TS a.
3.7.7); Region 11 does not recommend a license condition.
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JUL 0 5~ 984
-Harold R. Denten 2
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b.
Annulus Ventilation System (Mode 4 - TS 3.6.1.8); Region 11 does not recommend a_ license condition.
c.
Spent Fuel Ventilation Exhaust System (TS 3.9.11); DPC commits to testing prior to power escalation; Region II does not recommend a license condition.
d.
Containment Air Release and Addition System (Mode 4 - TS 3.6.1.9c); DPC commits to testing prior to initial criticality.
Region II does not recommend a license condition.
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DPC commits to testing Technical Support Ventilation System prior to e.
initial criticality.
Region II does not recommend a license condition.
l f.
Containment Purge and Incore Instrumentation Purge Exhaust (Mode 4 - TS 3.6.1.9a); Region II does not recommend a license condition.
5.
The Standby Shutdown Facility (SSF) is not fully operational in that the Spent Fuel Pool, the primary water source fer the SSF, will not be filled with water during initial fuel loading. An alternate water source from the Refueling Water Storage Tank will be'available and capable of being aligntd
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to the standby makeup pump.
Region II. recommends a license condition tt verify, the $$F has been returned to normal operation petor to initial criticality. (See Enclosure 3 Item G.6.)
Additionally, Region II has forwarded to NRR comments concerning draft Technical Specifications for the SSF in a let.ter dated July 5, 1984.
6.
Miscellaneous Fire Protection items which are incomplete are described in DPC letter of June 29, 1984.
RII. concurs with the proposed corrective action and recommends that items 1,
2, 5, and 6 of the letter be incorporated as a license condition for Region II verification prior to critica1 P v.
(See Enclosure 3 Item I).
- 7.
Precritical preoperational tests have been identified in the DPC letter of July 2, 1984.
RII finds that completing the remaining tests during the precritical heatup and testing is consistent in the overall scope of the fuel load license.
Region II recommends a license condition to address completion of hot function testing prior to initial criticality.
(See Item G.8) 8.
The surveillance test procedures remaining to be written have been identi-fied by DPC and will be completed prior to the mode required. Most of these are of a longer term requirement and testing was performed initially by a preoperational test.
Region 11 does not recommend a license condition.
9.
Shift staffing and operational experience requirements are being addressed by NRR.
Region II has been involved in earlier discussions between NRR and DPC on this subject and will perform verification of staffing as required.
i 10.
Verify the adequacy of the standby makeup pump flow rate.
This item was identified by Region 11 and was, transmitted to NRR for evaluation in a letter dated June 1, 1984 11.
The following Three Mile Island Tast Action Items require further action by NRR prior to full power operation:
1.C.1, II.B.1, II.E.4.2. and II.K.3.5.b.
Regarding allegations, the Region 11 staff has completed all major inspection activity related to open allegation files and at present concludes that the issues should be resolved satisfactorily and should not impact a fuel load
' license.
We have reviewed the licensee's preparation for implementation of the Quality Assurance Program for Operations, and have found that they meet the requirements i
of 10 CFR 50, Appendix B, as specified in the licensee's Quality Assurance Program (Chapter 17 of the FSAR), which was reviewed by the Office of Inspection and Enforcement.
I The licensee's projected fuel loading date is July 5,1984. Region II considers this fuel loading date to be reasonably accurate.
James P. O'Reilly
Enclosures:
1.
Items to be Completed Prior to Fuel Loading 2.
Items to be Completed Prior to Exceeding 200'F (Mode 4) 3.
Items to be Completed Prior to Initial Criticality 4.
Items to be Completed Prior to Exceeding 5% Rated Power cc w/ enc 15:
E. G. Case, NRR D. G. Eisenhut, NRR T. M. Novak, NRR E. G. Adensam, NRR K. N. Jabbour, NRR R. C. DeYoung, OIE H. L. Thompson, DHFS bec w/encls:
(See page 4) l i
Harold R. Dento*
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bec w/ enc 15:
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R. C.. Lewis J.'A. 01shinski J. P. Stohr H. C. Dance A. R. Herdt A. F. Gibson V. L. Brownlee J. J. Blake T. E. Conlon-F. Jape P. S. Skinner P. K. Van Doorn
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JUL 05 884
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4 ENCLOSURE 1 l
ITEMS TO BE COMPLETED PRIOR TO FUEL LOADING l
OF CATAWBA UNIT I (DOCKET NUMBER 50-413)
The licensee will perform to the satisfaction of the NRC Region II the following inspector followup items:
1.
Relocate containment atmosphere monitor sample lines to reduce poten-tial plateout and to provide representative. sampling.
2.
Complete testing of process and effluent monitors 1-EMF-31, 34, 35. 36, 37, 38, 39, 40, 41, 43A and B, 45A and B, 46A and B, 49.
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ENCLOSURE 2-ITEMS TO BE COMPLETED PRIOR TO EXCEEDING 200*F-(MODE 4)
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l' AT CATAWBA UNIT 1 (DOCKET NUMBER 50-413) l The licehsee will complete to the satisfaction of NRC Region !! the ice condenser testing and all associated steel erection removed during ice l
loading.
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JUL 05 864 i
ENCLOSURE 3 ITEMSTbBECOMPLETEDPRIORTOINITIALCRITICALITY OF CATAWBA UNIT 1 (DOCKET NUMBER 50-413)
A.
Satisfactorily resolve the issues identified in Region II status of facility i
completion letter to NRR dated July 5, 1984.
B.
The licensee will complete the following corrective action (s) pertaining to the appropriate Construction Deficiency Reports (50.55e Items):
1.
Correct steam generator water narrow range level measurement system errors.
2.
Replace Limitorque valve operator drain plugs with drilled hole type of plug.
3.
Re-evaluate equipment located inside the valve doghouse for higher temperature tolerance following a steam line break accident.
C.
Thelicenseewillcompletethefollowingcorrectiveaction(s)requireda[e result of the corresponding violations to the satisfaction of NRC Region II:
1.
Provide records to indicate acceptable testing for the preoperational test of the upper head injection.
2.
provide assurance to follow procedures for maintenance of safety-related equipment.
3.
Provide emergency condition analysis for stress and support design calculations.
4.
Resolve pipe support discrepancies.
5.
Assure ability to control repaired / salvaged items.
6.
Evaluate equipment for possible damage after turnover to operations and prior to full implementation of preventive maintenance (PM) program; complete review of Critical Structures, Systems and Components PM requirements.
D.
The licensee will complete the requirements of the following bulletins to the satisfaction of HRC P,egion 11:
1.
Pipe support base plate design using concrete expansion anchor bolts.
2.
Seismic analysis for as-built safety-related piping systems.
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s E.
The licensee will' complete the following corrective action (s) for the 7
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corresponding unresolved items to the satisfaction of NRC Region II:
1.
Provide additional study of calculations to confirm technical adequacy i
of evaluation for piping analysis support load increase.
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2.
Resolve main steam water hammer problem.
F.
The licensee will complete the following. corrective action required by the corresponding deviation to the satisfaction of NRC Region II:
i 1.
Comply with FSAR commitments for the performance of thermal expansion
- preoperational testing.
2.
Review and make necessary improvements in hydrogen gas piping system for reactor coolant pump drain tank.
G.
The licensee will perform to the satisfaction of NRC Region II, the following inspector followup items:
1.
Resolve discrepancy between the designed and actual capacity for the charging system reciprocating charging pump.
2.
Relocate 11 quid discharge valve IWL124.
j.
3.
Relocate reactor coolant monitor IEMF48.
4.
Resolve problems with liquid leakage, overflow, spillage, etc.
5.
Resolve OA program pertaining to lack of control for use of aerosols.
6.
Return the Standby Shutdown Facility to normal operating condition.
7.
Complete post inspection testing of the emergency diesel generators and supporting systems.
8.
Complete precritical hot functional testing.
H.
The following allegations, concerning the licensee will be satisfactorily resolved by NRC Region II:
Review licensee's action concerning alleged failure to maintain inter-pass temperature of stainless steel socket welds including resolution to unresolved items 84-31-01 and 84-31-02.
I.
Licensee will complete to the satisfaction of Region II the fire protection items 1, 2, 5 and 6 identified in DPC letter to NRR dated June 29, 1984.
J.
Provide an automatic indication in the Security Alarm Stations to indicate when alarm system is on standy power.
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JUL 051984 I
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ENCLOSURE 4 ITEMS TO BE COMPLETED PRIOR TO EXCEEDING 5?. RATED POWER AT CATAWBA UNIT 1 (DOCKET NUMBER 50-413)
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A.
The licensee will complete the requirements of the following bulletin to the satisfaction of NRC Region II:
l Failures of GE type HFA relays in use in class IE safety systems.
1-B.
The licensee will perform to the satisfaction of the HRC Region II, the following inspector followup items:
Resolve differences in procedure and FSAR description.s of power coefficient test.
C.
The licensee will complete to the satisfaction of NRC Region II, the following TMI Task Action Items:
1.
I.G.1, Training During Low Power Testing 2.
II.B.2, Plant Shielding 3.
II.B.3, Post Accident Sampling 4.
II.B.4, Training for Mitigating Core Damage e
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