ML20087L087
| ML20087L087 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/23/1984 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| ULNRC-773, NUDOCS 8403270016 | |
| Download: ML20087L087 (13) | |
Text
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r U N ION ELECTFilC COM PANY Isol GRATIOT STREET ST. Louis, MISSOURI O..OX 14.
poMALo w..cMNELL March 23, 1984
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4 Mr. Harold R. Denton, Director Office of Nuclear Regulatory Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ULNRC-773
Dear Mr. Denton:
DOCKET NO. 50-483 CALLAWAY PLANT, UNIT 1 REQUEST FOR ISSUANCE OF OPERATING LICENSE Union Electric Company wishes to advise you that the design, construction and preoperational testing of Callaway Plant, Unit l are essentially complete and that the unit may be ready for fuel load as early as April-23, 1984.
Our readiness for opera-tion is premised on the following:
A.
Conformance of the plant to the FSAR, design documents and regulatory commitments Except as noted herein, in.my judgment, Callaway Plant conforms to the facility description in the FSAR and other information filed on our docket.
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B.
Staff Operational Readiness The Union Electric Nuclear Function, which I head, is the corporate entity responsible for the design, con-struction, startup and operation of Callaway Plant.
The function is currently staffed with 670 permanent employees (exclusive of the security force).
The entire organization is dedicated full time to the operation and technical support of the plant.
Over 580 Nuclear Function personnel are currently employed at the Callaway Plant site.
Twenty-eight members of our operating staff (including management and training personnel) have been licensed by NRC as Senior Reactor Operators; fourteen are NRC-licensed Reactor Operators.- The operations staff has demonstrated their competence and reliability l
through participation in activities leading to plant
-startup.
They have assisted in preoperational test activities at Callaway and assumed overall responsibility 8403270016 840323 PDR ADOCK 05000403 PDR A
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Mr. Harold R. Denton Page 2 March 23, 1984 for plant testing in December, 1983 during the hot functional test program.
Each shift operating crew will meet the experience requirements presented to the NRC Commissioners by the Utility Group on February 24, 1984.
Qualified advisors will be utilized to assure on-shift " hot participation experience" as defined by the Utility Group.
I am convinced that we have prepared our personnel to handle the responsibility of operating callaway Plant.
C.
Hearing Reviews The Atomic Safety and Licensing Board presiding over the Callaway operating license proceeding issued favorable decisions in December, 1982, and October, 1983 on construction quality assurance and off-site emergency preparedness issues, respectively.
While the second of those decisions authorized you to issue the license when other Staff findings were ready, the Atomic Safety and Licensing Appeal Board completed its review of those decisions and affirmed them in September and December, 1983.
By memorandum dated March 16, 1984, the Commission elected not to review the Appeal Board decisions.
Consequently, the entire NRC hearing process on the Callaway license application is concluded.
D.
Remaining Work Activities and Open Items During the final weeks prior to fuel load, our efforts will be concentrated on completion of construction activities, final preoperational testing and closecut of licensing issues and inspection findings as follows:
1.
NRR licensing issues:
All outstanding and con-firmatory issues have been addressed and await final NRC staff action.
It is expected that all of these items will be closed or resolved in SER Supplement 3.
2.
Open NRC Region III Inspection Findings:
We expect to address all open items and items of noncompliance which are restraints to fuel load in order to permit final assessment and response by Region III personnel.
3.
Significant Deficiencies and Potential 50.55(e) items:
All items identified as known or potential
m..
t Mr. Harold R. Denton-Page 3 March 23, 1984' 50.55(e) problems will be reviewed to assure that any unresolved problems are not exacerbated by fuel load and low-power test activities.
4.
The Master Tracking System (MTS) in use at callaway identifies and tracks completion of outstanding work documents, hardware and dccumen-tation deficiencies, inspection issues and other findings requiring resolution prior to operation.
MTS entries are reviewed and classified so as to identify restraints to plant operational modes.
All outstanding MTS items classified as potential restraints to fuel load will be closed out or dispositioned prior to fuel load.
Exceptions will be specifically justified, reviewed with the Resident Inspectors, and, if appropriate, reviewed by the Callaway Nuclear Safety Review Board (:NGRB),
our off-site review committee.
Similarly, MTS items classified as restraints to operational Modes 5'through 1 will be closed out or disposi-tioned before entering the restrained mode.
5.
Design features and programs as well as construc-tion items having safety significance which may not be complete by fuel load include the following:
a.
Installation of modified under-voltage trip attachments for the reactor trip bypass breakers and completion of the qualification program for reactor trip breaker shunt coils (Ref:
ULNRC-763, 3/12/84);
b.
Completion of all portions of the IEEE-323/
NUREG-0588 environmental qualification programs (Ref:
SLNRC 84-0009, 1/27/84 and SLNRC 84-0034, 2/23/84);
.c.
Completion of all portions of the IEEE-344 seismic qualification programs (Ref:
SLNRC 84-0040, 3/16/84);
~
.d.
Operational readiness of the Reactor Vessel Level Indicating System (Ref:
SLNRC 83-0019, 4/15/83);
e.
Completion of all phases of the Emergency Response Facilities Information Systems (Ref:
SLNRC 83-0019, 4/15/83);
p.
J Mr. Harold R. Denton Page 4 March 23,.1984 f.-
Operational readiness of.the Post-Accident Sampling System (Ref:
SLNRC 84-0015, 2/1/84);
g.-
Fire Protection Audit Open Items (SLNRC 84-0037, 2/24/84).
6.
The preoperational test program for the Callaway Plant is essentially complete.
Testing deficiencies are tracked by MTS.
At this writing, the only preoperational test deferred until after fuel load is the-CRDM Cooling Test (CS-03GN02).
A portion of another test which involves acceptance of the halon system-for the north cable penetration room (CS-04KC02) will not be completed prior to fuel load.
Certain other testing deficiencies, such as a valve that leaked during hot functional testing, will require retest after fuel load when plant conditions permit.
7.
SNUPPS Licensing Submittals:
A number of documents have been submitted to your office by SNUPPS Staff which must be formally incorporated into the Callaway Docket.
Attachment'I lists these submittals which are hereby incorporated into the Callaway application.
To the best of my knowledge, the foregoing paragraphs address all remaining activities-which bear on your issuance of the Callaway Plant Operating License.
In summary, following our completion or disposition of the remaining activities noted, I believe that Callaway Plant and our Nuclear Function organization will be ready to commence fuel load.
We respectfully request issuance of the operating' license so that this activity may proceed as planned.
Very truly yours, Donald F.
Schnell
.DFS/bjp
' Attachment
L.
STATE OF MISSOURI )
)
Donald F. Schnell, of lawful age, being first duly sworn upon oath says that he.is Vice President-Nuclear and an officer of Union Electric Company; that he has read the foregoing document and knows the content thereof; that he has executed the same for and on behalf of said company with full power and authority to do so; and that the facts therein stated are true and correct to the best of his knowledge, information and belief.
By u
Donald F.
Schnell Vice President Nuclear SUBSCRIBED and sworn to before me this d342 day of 198M
/
d%RBANS PfAVFSr NOTARY PUBUC, STATE of MISSoum WY COMMISSION EXPlRES APRIL 22,im ST. LOUIS COUNTY f
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~cc Glenn L. Koester Vice President Operations y
Kansas Gas & Electric-
.P.O. Box 208
. Wichita,. Kansas 67201
-Donald T. McPhee Vice President Kansas City Power and Light Company 1330' Baltimore Avende 4
Kansas City, Missouri 64141 Gerald-Charnoff, Esq.
Shaw, -Pittman, Potts & Trowbridge
'1800 M. Street, N.W..
Washington, D.C.
20036
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Nicholas A. Petrick
' Executive Director SNUPPS 5' Choke Cherry Road Rockville, Maryland 20850-John H. Neisler Callaway Resident Office U.S. Nuclear Regulatory Commission RRil Steedman, Missouri 65077 Bill Forney Division of Projects and' Resident' Programs, Chief, Section lA U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen-Ellyn,: Illinois.60137 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
- Mr. James G. Keppler 1 Region'l Administrator a
U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137
s ATTACHMENT I to ULNRC-773 The following lists all transmittals from SNUPPS to Mr. Harold R. Denton which are to be incorporated into the Callaway Plant Unit 1 operating license application:
SNUPPS LETTER NUMBER SLNRC DATE SUBJECT 14 10/02/79 SNUPPS FSAR 80-34.
07/29/80-Masonry Walls 81-02 01/20/81 Transcript of FSAR Review Meeting 81-13 02/27/81 Review of FSAR Chapter 8 81-16 03/20/81 Electrical Instrumentation and Control Drawings 81-34 05/26/81 NRC Request for Additional Information-Preservice Inspection Program Plan 81-35 05/27/81 Emergency Procedures and Training for Station Blackout Events 81-38 06/01/81 Emergency Response Facilities 39 06/03/81 Auxiliary Feedwater System 81-41 06/04/81 Electrical, Instrumentation and Control Drawings 81-42 06/04/81 Letter Retransmittal (SLNRC 81-38) 81-44 06/08/81 Reliability Analysis of the SNUPPS Auxiliary Feedwater System 81-47 06/19/81 Emergency' Response Facilities r
i 81-48 06/22/81 control of Heavy Loads i '
'81-49 06/22/81 Description of ESF Status Panel 81-51 06/26/81 Human Factor Evaluation of the SNUPPS Control Room i
81 07/01/81
_ICSB Meeting
'81-62 08/10/81 Seismic Analysis
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,81-63
'08/10/81 Description of ESF Status Panel I
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SNUPPS LETTER NUMBER SLNRC DATE SUBJECT 81 08/12/81 Human Factor Evaluation of the SNUPPS Control Room 81-66 08/31/81 Improved Load Following Package 1
81-67 08/14/81-ICSB Positions 81-68 08/14/81 ICSB Review 81-69 08/14/81 NRC Request for Additional Information - Materials Engineering 81 08/20/81 NSSS Setpoint Methodology n
81-71 08/17/81 NRC Request for Additional Information-Materials Engineering
. 81-73 08/20/81 Meeting with Power Systems Branch 81-75 08/27/81 Seismic Analysis 81-76 08/31/81 CPB (Reactor Fuel) Review 81-82 09/01/81 ICSB Review 81-83 09/01/81 RSB Review 81-89 09/05/81 Pump and Valve Test Program 81 09/05/81 MEB Review 81-92L 09/09/81 CPB Review 81-96 09/09/91' RSB Review 81-97' 09/11/81 Event V Program 81-98 09/11/81 Turbine Missile Analysis 81-100:
09/11/81 PSB Review 81-101 09/14/81 RSB Iteview 81-103 09/16/81 NRC Request for Information-Materials Engineering
'81-105 09/17/81 RSB Review 81-107 09/18/81 Pump and Valve Test Program
.81-108 09/18/81 SER Open Issues
SNUPPS LETTER NUMBER SLNRC DATE SUBJECT 81-109 09/22/81 PSB Review 81-111 09/22/81 ICSB Review 81-113 09/24/81 Revision Seven to SNUPPS FSAR 81-115 10/02/81 ICSB Review 81-117 10/02/81 PSB Review 81-120-10/30/81 CPB Review 81-123 11/16/81 ICSB Review 81-124 11/17/81 SER Outstanding Issue-Cable Tray Seismic Analysis81-126 11/17/81 Natural Circulation Cooldown 81-127 12/11/81 Pump and Valve Test Program 82-01 01/07/82 SNUPPS ECCS Analysis 82-04 01/19/82 NUREG-0737, Item I.D.1 82-05 01/19/82 Shunt Coils for Reactor Trip Breakers 82-06 02/04/82 NRC Request for Information-Seismic Qualification of Equipment 82-08' 02/09/82 Seismic Qualification of Equipment 82-09 02/12/82 Safe Shutdown with a Postulated Fire in the Control Room 82-10' 02/23/82 Revision Eight to SNUPPS FSAR 82-16 03/16/82 NUREG-0737, Item I.D.1 82-19 04/02/82 Long Term Operability of Deep Draft Pumps 82 04/12/82 NUREG-0737, Item I.D.1 82-23 04/29/82 NUREG-0737, Item II.D.1 82-25 05/14/82 Long Term Operability of Deep Draft Pumps 82-28 05/25/82 Fillet Weld Requirements
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' SNUPPS LETTER HUMBER SLNRC DATE SUBJECT
' 82-30' 07/01/82 NUREG-0737, Item II.D.1 82-33
- 08/04/82 Control of Heavy Loads 82-40' 10/20/82 NUREG-0737, Item II.D.1 82-41 10/18/82 Seismic. Analysis 82-46 11/03/82 Fire Protection Review 4
8 2-47 12/03/82.
Regulatory Guide 1.121, Application for Withholding Proprietary Information from Public Disclosure
. 82-49 12/15/82 Revised Submittal of Snubber Technical Specification 82-50' 12/22/82 SNUPPS QA Program for Design and Construction
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82-59
- 12/22/82 Raquest for Information re: SRP Section 7.4, Remote Shutdown Capability 83-02 01/07/83 NUREG-0737,' Item II.D.1 83-07 02/04/83 NUREG-0737, Item II.B.3 83-15 03/10/83-Environmental Qualification of Safety Related Equipment 83-22 04/26/83 containment Recirculation Sump Testing 4
83-24 05/09/83 Power' System Branch Review 83-25 05/09/83 Fillet Weld Requirements 83-27
. 05/13/83 Power System Branch Review 83 05/27/83 Environmental Qualification of Safety Related Equipment
- 83-35 06/30/83 SNUPPS Program Plan for the DCRDR 83-36 07/08/83 SNUPPS Technical Specifications 83-42 07/28/83 Environmental Qualification of Safety-Related Electrical Equipment 83-45 08/30/83 Alternate Pipe Break Criteria 4
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SNUPPS LETTER NUMBER SLNRC DATE SUBCECT 83-47 08/31/83 ICSB Review: Proposed Technical Specification 83 09/07/83 SNUPPS Technical Specifications 83-54 10/27/83 Instrumentation and Control Systems Branch Review 83-55 10/27/83 Instrumentation and Control Systems Branch Review 83-61 11/23/83 Environmental Qualification of Equipment 83-62 11/28/83 SNUPPS Program Plan for the DCRDR 83-63 11/30/83 NUREG-0737, Item I.D.1 84-03 01/13/84 SPDS Safety Analysis l
84-04 01/16/84 containment Purge Valve Operability 84-05 01/18/84 NRC Request for Information re Preservice Inspection (PSI) Relief Request 84-08 01/27/84 Control of Heavy Loads 84-09 01/27/84 Environmental Qualification Justification for Interim Operations 84 01/31/84 Power System Branch Review 84-11 01/31/84 Power System Branch Review 1
84-13 02/01/84 Environmental Qualification of Safety-Related Electrical Equipment 84-14 02/01/84 Fire Protection Review 84-15 02/01/84 SNUPPS License Conditions 84-16 02/02/84 Safe Shutdown Following Loss of Instrument Bus 84-17 02/02/84 Steam Generator Tube Plugging Requirements 84-18 02/02/84 Revision 13 to SNUPPS FSAR 84-19 02/02/84 DCRDR Summary Report i
r B s, SNUPPS
- LETTER NUMBER SLNRC DATE SUBJECT 21 02/02/84 Environmental Qualification of Equipment 84-22 02/02/84-Diesel Generator Rocker Arm Lube Oil Temperature-
- 23 02/02/84 Seismic Qualification of Equipment 84-24 02/02/84 Power System Branch Review 84-25 02/07/84 Environmental Qualification of Safety-Related Electrical Equipment 84-26 02/07/84 NRC Request for Information re Preservice Inspection (PSI) Relief Request
' 84627 02/08/84 NRC Request for Information re Preservice Inspection Programs 84-29 02/09/84 SNUPPS Technical Specifications 84 02/13/84 NRC Request for Information re PSI 84-32 02/14/84 Preservice Inspection Program for RCS Piping Welds 84-54
-02/17/84 Reactor Cavity Shielding
' 84-34 02/23/84.
E.Q. Justifications for Interim Operation 84-35 02/23/84 I&CS Branch Review 84-36 02/24/84 Preservice/ Inspection Relief Request-Callaway Plant
- 84-37 02/24/84 Fire Protection Review 84-38 02/27/84 Slave Relay Testing Technical Specification Requirements
.84-39 03/05/84
.E.<Q. Justifications for Interim
. Operation 84 03/06/84 Justifications for Interim Operation
- Seismic Qualification
- 84-41
' 03/14/84 Fire Protection Review 42-03/14/84 Revision 14 to SNUPPS FSAR i
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-LETTER NUMBER.
SLNRC DATE SUBJECT 84-43 03/15/84 Containment Isolation Dependability 84-44 03/16/84 S/G Tube Rupture Event 84-45 03/16/84 Equipment Qualification 84-46 03/20/84 SNUPPS Tech Specs 84 03/21/84 E.Q. of Mechanical Equipment 84-48 03/21/84 NRC Audit of SNUPPS Control Room Design Reviews, Week of 2/27/8 4 4
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