ML20072J530
| ML20072J530 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/28/1983 |
| From: | Bradley E PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.G.1, TASK-TM NUDOCS 8306300133 | |
| Download: ML20072J530 (5) | |
Text
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PHILADELPHIA El.ECTRIC COMPANY 2301 MARKET STREET P.O. BOX 8699 PHILADELPHI A. PA.19101
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CUG EN E J. BR ADLEY
.seocea,e es.seakc...s.k DO*4 ALD ELANKEN RUDOLPH A. CHILLEMI C. C. MI R K H A LL T. H. M AH ER CORNELL PAUL AUERBACH June 28, 1983 EDW ARO J. CULLEN. J R.
THOM AS H. MILLER. J R.
IR ENE A. McKENN A asses,a.T c...sak Mr.
A.
Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.
S.
Nuclear Regulatory Commission Washington, D.C.
20555
Subject:
Limerick Generating Station, Units 162 Revised Response to TMI Item I.G.1 Re ference :
PECO and NRC Conference Call dated June 27, 1983 File:
GOVT l-l (NRC)
Dear Mr. Schwencer:
The attached document is a draft revised response to TMI Item I.G.I, " Training during Low-Power Testing",
as a result of the referenced conference call.
The information contained on the draft revised response will be incorporated into the FSAR, exactly as it appears on the attachment, in the revision scheduled for August, 1983.
Sincerely.
I Euge e J.
Bradley 8
RJS/gra/68 j
Copy to:
See Attached Service List 8306300133 830628 PDR ADOCK 05000352 A
r cc: Judg3 Lawr:nco Br:nn3r (w/ enclosure)
Judge Richard F. Cole (w/ enclosure)
Judge Peter A. Morris (w/ enclosure)
Troy B. Conner, Jr., Esq.
(w/ enclosure)
Ann P. Hodadon.
(w/ enclosure)
Mr. Frank R. Romano (w/ enclosure)
Mr. Robert L. Anthony (w/ enclosure)
Mr. Marvin I. Lewis (w/ enclosure)
Judith A. Dorsey, Esq.
(w/ enclosure)
Charles W. Elliott, Esq.
(w/ enclosure)
Jacqueline I. Ruttenberg (w/ enclosure)
Thomas Y. Au, Esq.
(w/ enclosure)
Mr. Thomas Gerusky (w/ enclosure)
Director, Pennsylvania Emergency Management Agency (w/ enclosure)
Mr. Steven P. Hershey (w/ enclosure)
Donald S. Bronstein, Esq.
(w/ enclosure)
Mr. Joseph H. White, III (w/ enclosure)
David Wersan, Esq.
(w/ enclosure)
Robert J. Sugarmen, Esq.
(w/ enclosure)
Martha y. Bush, Esq.
(w/ enclosure)
Spence W. Perry, Esq.
(w/ enclosure)
Atomic Safety and Licensing Appeal Board (w/ enclosure)
Atomic Safety and Licensing Board Panel (w/ enclosure)
Docket and Service Section (w/ enclosure)
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DRAFT LGS,S-PLANTSAFETYhARAMETERDISPLAYCONSOLE
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I.D.2 Position Each applicant and licensee shall install a safety parameter display system (SPDS) that will display to operating personnel a minimum set of parameters which define the safety status of the This can be attained through continuous indication of plant.
direct and derived variables as necessary to assess plant safety status.
Response
The Limerick Design includes an Emergency Response Facility Data System (ERFDS).
This system is based on the General Electric Emergency Response Information System.
The SPDS at Limerick will be a part of this ERFDS.
The hardware design is essentially complete with installation scheduled to begin in April 1983.
The software effort is proceeding on schedule to support system checkout in August 1983.
It is expected that the system will be operat'ional by fuel load.
The parameters included in the SPDS disp' lay are based on the entry conditions for the Limerick symptom-based emergency procedures.
As changes and improvements are made to the reactor pressure vessel control and containment control procedures, the system can be modified to reflect these changes.
The SPDS parameters are a subset of the parameters available in the ERFDS data base, which is based on the Regulatory Guide 1.97 Rev. 2 BWR 1
l parameter list.
The system has been designed in accordance with l
the guidance provided in NUREG-0696.
t A safety analysis describing the basis on which the selected parameters are sufficient to assess the safety status of each identified function for a wide range of events will be available I
I by August 1983.
Prior to fuel load, the SPDS will be reviewed in conjunction with the other NUREG-0737 supplement initiatives.
As one of the final steps in integrating all of the control room modifications (i.e.,
l Regulatory Guide 1.97, SPDS, Emergency Operating Procedures),
an emergency procedure walk through is scheduled as part of the i
i control room review, o
I.G.1 TRAINING DURING LOW-POWER TESTING Position We require applicants for a new operating license to define and commit to a special low-power testing program approved by NRC to be conducted at power levels no greater than 5 percent for the
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Rev. 20, 05/83 1.13-18b
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purposes of providing meaningfu1 technical information beyond that obtai W in the normal startup test program and to provide supplemential" training.
Clarification Chapter 14 of the Final Safety Analysis Report describes the applicant's initial test program.
The objectives of the initial test program include both training and the acquisition of technical data.
This program has been determined by the staff to be acceptable as reported in Section 14 of this report.
- However, we require the applicant to perform additional testing and training beyond the requirements of the initial test program.
Response
The BWR Owner's Group Program for compliance with NUREG-0737 Requirement I.G.1 was transmitted to the NRC via letter (BWROG-8120) from D.B. Waters to E.G. Eisenhut.
The generic program described in' this document is divided into five sections:
I-Preoperational Testing; II-Cold Functional Testing; III-Hot Functional Testing; IV-Startup Testing; and V-Additional Training and Testing.
The initial test program for Limerick as described
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in FSAR Chapter 14 follows the testing described in the first
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four sections of the owner's Group Program.
DuRing this program, PECo expects to perform significant plant transients only once, 4
but with a maximum of licensed personnel in attendance.
The Limerick unit unique simulator provides an excellent mechanism l
for training people without affecting the real plant.
Repetition of startup tests solely for testing purposes will be done on this simulator.
Additional information is provided in the responset to M Ouestion 640.11.
II.B.1 REACTOR COOLANT SYSTEM VENTS Position Each applicant and licensee shall install reactor coolant system I
(RCS) and reactor vessel head high point vents remotely operated from the control room.
Although the purpose of the system is to vent noncondensible gases from the RCS which may inhibit core cooling during natural circulation, the vents must not lead to an unacceptable increase in the probability of a loss-of-coolant accident (LOCA) or a challenge to containment integrity.
Since these vents form a part of the reactor coolant pressure boundary, the design of the events shall conform to the requirements of Appendix A to 10 CFR Part 50, " General Design Criteria." The vent
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system shall be designed with sufficient redundancy that assures a low probability of inadvertent or irreversible actuation.
Each licensee shall provide the following information concerning the design and operation of the high point vent system:
(1)
Submit a description of the design, location, size, and power supply for the vent system along with results of analyses for loss-of-coolant accidents initiated by a break I
in the vent pipe.
The results of the analyses should demonstrate compliance with the acceptance criteria of 10 CFR 50.46.
(2)
Submit procedures and supporting analysis for operator use of the vents that also include the information available to the operator for initiating or terminating vent usage.
Clarification A.
General (1)
The important safety function enhanced by this venting capability is core cooling.
For events beyond the present design basis, this venting capability will.substantially increase the plant's ability to deal with large quantities k
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