ML20117M365

Forwards for Review,Rev to Paragraph 132.1.2 in FSAR Re Simulator Performance Testing,Per 850508 Meeting on Draft SER Open Item 92

ML20117M365
Person / Time
Site:	Vogtle
Issue date:	05/10/1985
From:	Bailey J GEORGIA POWER CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
GN-609, NUDOCS 8505170020
Download: ML20117M365 (3)

Text

r Georgia Power Company

&- Rout) 2, Box 299A Waynesboro. Georgia 30830 Telephone 404 554 9961 404 724-8114 Southern Company Services, Inc.

Post Office Box 2625 Birmingham, Alabama 35202 Telephone 205 8704011 Vogtle Project May 10, 1985 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Ms. Elinor G. Adensam, Chief Log: GN-609 Licensing Branch #4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 REQUEST FOR ADDITIONAL INFORMATION: DSER OPEN ITEM 92

Dear Mr. Denton:

Enclosed for your staff's review is a revision .to paragraph 13.2.1.2 in the VEGP FSAR. This revision is a result of our meeting with your staff on May 8, 1985 and will appear in FSAR Amendment 17.

If your staff requires any additional information, please do not hesitate to contact me.

Sincerely, V. A. Bailey Project Licensing Manager JAB /sm Enclosure xct D. O. Foster L. T. Gucwa R. A. Thomas G. Bockhold, Jr.

J. E. Joiner, Esquire T. Johnson B. W. Churchill, Esquire D. C. Teper M. A. Miller L. Fowler B. Jones, Esquire (w/o enclosure) Vogtle Project File 0205m

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1 l() VEGP-FSAR-13 water reactors. The cold license training program will also contain a program of 10 reactor startups on a research/ test type reactor to gain actual "at the controls" experience. Personnel 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 nuclear plant licensed operator experience or those who have 10 prior test reactor experience shall be exempted from 10 reactor startup requirements. A combination of the preceding will O satisfy the experience requirements of NUREG-0737, items I.'A.2.1. The details of the simulator program are contained in tables 13.2.1-1 through 13.2.1-5.

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• k- ""4d=""a Since digital sodtware does n drift "4"a" 4" Re atory Guide 1.149.

or ch e, retesting of previously verified respons ould be 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 instruc s will ident y any incorrect simulator responses or inconsisten s. Th e discrepancies shall be ery, investi@ated by the 16-documented at the time of di O simulator maintenance crew, continuous feedback syst n

utilizi orrected as appropriate. The 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. T continuous, ongoing simulator i ovement program exceeds requirements and will be conducted in eu of annual perfo nce testing. Documentation of discrepancy id ification, investigation, and resolution will be re ned a pave nf ek. e4mn12ene porfnemsnr. Anan--nes*4mn 13.2.1.3 Qualification and Requalification Program O The qualification and requalification program for licensed operators and the training department is described in the following paragraphs.

( '; 13.2.1.3.1 Licensed Operator Qualification Reactor operator and senior reactor operator training programs include the qualification requirements contained in NUREG-0737, item I.A.2.1, and are described in tables 13.2.1-1 through 13.2.1-5.

Amend. 10 9/84 13.2.1-5 Amend. 16 4/85

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' Insert to 13.2.1.2

@t 2, 'br The VEGP simulator will conform to the guidance give Regulatory Guide 1.149. Performance testing of the simulator specifi a a paragraph 5.4 of ANSI /ANS-3.5-1981 will be accomplished in the following manner:

Comparison of the s'teady. state' operating values.of_ critical and-

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noncritical parameters between the VECP 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 S~ '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

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'(f) Load changes'(manual and automatic control)

- (g) Plantishutdown 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 F (d) ' Safety injection (e) Residual heat removal (f) Nuclear service cooling water

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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.

When a' limited change is made, a specific performance test on the

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affected systems and components shall be performed.

~ Factory acceptance testing of the VEGP simulator has already been completed. The performance test described above will be completed prior to August 1,1988.and not -less than every four years thereaf ter.

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