ML20132F587
| ML20132F587 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/29/1985 |
| From: | Bailey J GEORGIA POWER CO. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| GN-668, NUDOCS 8508020319 | |
| Download: ML20132F587 (4) | |
Text
f~ -
I Georgia Power Company Routs 2. Box 299A Waynesboro, Georgia 30830 Telephone 404 554 9961 404 724 8114 Southern Company Services. Inc.
Post Office Box 2625 Birmingham, Alabama 35202 Telechcme 205 870-6^11 Vogtle Proj.ect July 29, 1985 Director of Nuclear Reactor Regulation File: X7BC35 Attention:
Ms. Elinor G. Adensam, Chief Log:
GN-668 Licensing Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 REF.: BAILEY TO DENTON, GN-609, DATED 5/10/85 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND C?PR-1209 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 SER OPEN ITEM-12: SIMULATOR RESPONSE TEST
Dear Mr. Denton:
As a result of a telephone conversation with your staff on July 17, 1985, the attached changes will be made to the VEGP FSAR.
These changes supercede those contained in the referenced letter and will appear in FSAR Amendment 18.
If your staff requires any additional information, please do not hesitate to contact me.
Sincerely, e
d.
J. A. Bailey Project Licensing Manager JAB /caa Attachment xc:
D. O. Foster G. Bockhold, Jr R. A. Thomas T. Johnson (W/o Att.)
J. E. Joiner, Esquire D. C. Teper (W/o Att.)
B. W. Churchill, Esquire L. Fowler M. A. Miller W. C. Ramsey B. Jones, Esquire (W/o Att.)
Vogtle Project File L. T. Gucwa 0053V B508020319 850729 l
1 PDR ADOCK 05000424 i
E PM
r A/ Lac.I,~-si o r-11 VEGP-FSAR-1 1.9.148 REGULATORY GUIDE 1.148, MARCH 1981, FUNCTIONAL SPECIFICATION FOR ACTIVE VALVE ASSEMBLIES IN SYSTEMS IMPORTANT TO SAFETY IN NUCLEAR POWER PLANTS 1.9.148.1 Regulatory Guide 1.148 Position This guide delineates a procedure acceptable to the NRC for implementing regulations with respect to the detailed specification of information pertinent to defining operating requirements for active valve assemblies in light-water-cooled nuclear power plants.
1.9.148.2 VEGP Position 15 Conformance is addressed in table 3.9.B.3-10.
1.9.149 REGULATORY GUIDE 1.149, APRIL 1981, NUCLEAR POWER PLANT SIMULATORS FOR USE IN OPERATOR TRAINING
\\
1.9.149.1 Regulatory Guide 1.149 Position This regulatory guide describes a method acceptable to the NRC for specifying the functional requirements of a nuclear power plant simulator to be used for operator training.
1.9.149.2 VEGP Position
'^n ferwxceptwi4h -r: gc rd t o C ::t-ion 5. 4 ( 3 ) of ANCI/ANS 3.
GPC will conduct periodic simulator perf ce testing in r e to plant changes which training.
Since digital softwa s not dri change, retesting of verified simulator response ot be conducted.
Through the use of startup test operator o
" tions supported by plant transi arts and plant change noti
- he VEGP will be modified and tested to match plant
, nse.
simu subscction 13.2.1 for edditionel discussion.
c.on fo r rn. See s ubsecd ien 13 '11 for aMiMM disc "5 5'on-Amend. 9 8/84 1.9-112 Amend. 15 3/85
4"
\\
i VEGP-FSAR-13 The cold license training program will also water reactors.
contain a program of 10 reactor startups on a research/ test type rer.ctor to gain actual "at the controls" experience.
Personnel g
with prior Navy nuclear experience as an engineering watch
{
officer, engineering watch supervisor, reactor operator, or other equivalent positions or those who have prior commercial 10 nuclear plant licensed operator experience or those who have prior test reactor experience shall be exempted from 10 reactor startup requirements.
A combination of the preceding will g
items satisfy the experience requirements of NUREG-0737,
/
The details of the simulator program are contained in I.A.2.1.
tables 13.2.1-1 through 13.2.1-5.
se ra se rt to 131.1,.7 4
- k-
~"4d="ra f "a"
^:
"""P cir u *^r fill cc 4 r- "i*h Re atory Guide 1.149.
Since digital software does n drift ould be retesting of previously verified respons or ch e,
redundan r unnecessary.
Performance testing w be conducted for any har e or software modifications ma to the simulator as a result of nt changes that affect t*
ning.
The simulator will be ted continuously w e it is in use.
Operators and instrue s will ident' any incorrect simulator s.
Th e discrepancies shall be responses or inconsisten h
documented at the time of di ery, investi4ated by the W
simulator maintenance crew, n
orrected as appropriate.
The N-continuous feedback syst utilizi experienced operators and instructors will ade ely exercise test the simulator.
More immediate fo w through on identif discrepancies will be possible in mparison to conducting ann performance testing.
continuous, ongoing simulator i ovement program eu of annual exceeds requirements and will be conducted in perfo nce testing.
Documentation of discrepancy id ification, investigation, and resolution will be re. 4ned annn--ne,ea nn enen,---
a are me ~s.
.Amn1 en, 7r 13.2.1.3 Qualification and Requalification Program The qualification and requalification program for licensed is described in the operators and the training department following paragraphs.
i I
1 h.
l, 13.2.1.3.1 Licensed Operator Qualification
\\
J l
Reactor operator and senior reactor operator training programs include the qualification requirements contained in NUREG-0737, l
and are described in tables 13.2.1-1 through item I.A.2.1, 13.2.1-5.
g j-Amend. 10 9/84 13.2.1-5 Amend. 16 4/85
g Insert to 13.2.1.2 The VEGP simulator-will conform to the guidance given in each of the regulatory positions in' Regulatory Guide 1.149.
Conformance to regulatory position C.4 will be met by implementing paragraph 5.4 of ANSI /ANS-3.5-1981 in the fo11owing manner:
1.-
Comparison of the steady state operating values of critical and
-noncritical parameters between the VEGP Unit 1 control room and the simulator at various power levels.
2.
Maneuvering of the simulator.through the following plant evolutions listed in paragraph 3.1.1 of the standard.-
(a). Plant startup - cold to hot standby. The starting conditions shall be refueling conditions of temperature, and pressure (b) Nuclear startup from hot standby to rated power (c) Turbine startup and generator synchronization (d) Reactor trip followed by recovery to rated power (e) Operations at hot standby (f)' Load changes (manual and automatic control)
(g) Plant shutdown from rated power to hot standby to cooldown to cold (refueling) conditions (h) Startup, shutdown and power operations with less than full reactor coolant flow is not permitted by the VEGP operating license and therefore will not be conducted.
3.
Core physics testing will be comprised of an evaluation of simulation of:
(a) Estimated critical position computation (b) Estimated critical concentration computation (c) Shutdown margin computation (d) Estimating criticality by the I/M plotting' method 4..
Operations surveillance procedure testing will be comprised of those control room operations which are required to conduct the operability tests of the following systems:
(a) Diesel generators
.(b) Auxiliary feedwater (c) High lead safety injection (d). Safety injection (e) Residual heat. removal (f) Nuclear service cooling water-5.
Simulator malfunction conditions'shall be evaluated by experienced staff members for best estimate response or compared to actual plant data or other best estimate data.
~
6.
When a limited change is made, a specific performance test on the-affected systems and components shall be performed.
Factory acceptance testing of the VEGP simulator has already.been j'
i
-completed. The performance. test described above;will be completed prior-to August 1,1988 and not less than every four years thereafter.
l
.