ML20203K844

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Rev 0 to Training Lesson Plan LO-LP-39216-00, Design Features Section 5
ML20203K844
Person / Time
Site: Vogtle  Southern Nuclear icon.png
Issue date: 08/08/1986
From: Brown R, Fordham D
GEORGIA POWER CO.
To:
Shared Package
ML20203K798 List:
References
LO-LP-39216, LO-LP-39216-00, NUDOCS 8608210376
Download: ML20203K844 (11)
v • d • e


Text

T Georgia Power 6 POWE2 GENERATION CEPARTMENT VOGTLE ELECTRIC GENERATING PLANT ,,, pg,?, f TRAININGLESSONPyN"~>'[','Ciikl, g kfk f TITLE: DESIGNFEATURESSECTION3 gi b' 5'NNh LO-LP-39216-00 PROGRAM: LICENSED OPERATOR TRAINING 0 REVISION:

AUTHOR: D. FORDHAM 8/8/86 DATE:

APPROVED: T[ DATE: f/f//g' INSTRUCTORGUIDELINES8 WHITE BOARD WITH MARKERS

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LO-LP-39216-00

l. PURPOSE STATEMENT:

TO TEACH THE USE AND APPLICABILITY OF THE DESIGN FEATURES, SECTION 5 0F TECHNICAL SPECIFICATIONS II. LIST OF OBJECTIVES:

1. The student will be able to list the definition of Exclusion Area and Low Population Zone from 10CFR100.
2. The student will be able to list the design pressure and temperature of containment.
3. The student will be able to list the design features of the fuel including number of assemblies, rods per assembly, active fuel length, total weight and maximum enrichments.
4. The student will be able to list the design features for control rods including percentage composition and cladding material.
5. The student will be able to list the design pressure and temperatures for the.RCS and pressurizer.
6. The student will be able to list the design features of the spent fuel storage racks including K when flooded with unborated water, center to center distance, drainage and capacit,ggy, and the K,gg for new fuel storage assuming aqueous foam moderation.

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__ LO-LP-39216-00

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REFERENCES:

TECHNICAL SPECIFICATIONS SECTION 5 DESIGN FEATURES 10CFR100 et _

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LO-LP-39216-00 lil. LESSON OUTLINE: NOTES I. INTRODUCTION A. Design Features

1. Those features that cannot be changed
a. Would have significant effect on safety
2. Not covered in previous tech specs.
3. Materials of construction or geometric arrangements II. PRESENTATION ,

A. Site

1. Exclusion Area - Figure 5.1-1
a. Required for 10CFR100
b. Person standing at outer periphery
1) Less than 25 Rem W.B.
2) Less than 30D Rem' Thyroid from iodine
3) For two hours after accident
2. Low Population Zone

. a. Also required by 10CFR100

b. Person at outer boundary
1) Less than 25 Rem W.B.
2) Less than 300 Rea to thyroid from iodine
3) For entire passage of cloud B. Containment
1. Steel lined reinforced concrete structure
2. Cylindrical shape and done roof l

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y LO-LP-39216-00 lil. LESSON OUTLINE: NOTES

3. Dimensions
a. Inside diameter - 140 feet
b. Inside height - 226 feet
c. Minimum thickness
1) Walls - 3 ft. 9 in.
2) Roof - 3 ft. 9 in.
3) Basement - 8 ft. 3 in.
4) Instrumentation cavity - 8 ft.
5) Steel liner - 1/4 inch 0 3
d. Net free volume 2.75 x 10 ft
4. Design Parsmaters
a. Pressure - 52 psig
b. Temperature - 400*F -

C. Reactor Core

1. Fuel Assemblies

, a. 193 fuel assemblies

1) Each with 264 fuel rods (17 x 17) - 25
2) Clad with Zirc 4
3) Active fuel length 144 inches
4) Maximum weight 1766 grams Uranium
5) Initial fuel load enrichment maximum of 3.2 W% U-235
6) Refuel fuel load enrichment maximum of 3.5 W% U-235.

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LO-LP-39216-00 lli. LESSON OUTLINE: NOTES

2. Control Rod Assemblies
a. 53 full length assemblies
b. 142 inches of absorber material
1) 95.5% Natural Hafnium
2) 4.5% Zirconium
3) Clad with stainless steel D. Reactor Coolant System
1. Maintained with code requirements
a. FSAR Chapter 2
2. Design Pressure 2485 psig
3. Design Temperature
a. RCS 650*F .. _
b. Pressurizer 680*F" -

3

4. Volume - steam and water 12, 240 1100 ft
a. At T, , 588.5'F

. E. Meteorological Tower Location

1. Figure 5.1-1 F. Fuel Storage
1. Criticality
a. Spent fuel racks
1) K,fg less than or equal to .95
2) Flooded with unborated water
3) 10.6 inch center to center distance between spent fuel assemblies 6

y LO-LP-39216-00 111. LESSON OUTLINE: NOTES

b. New fuel stored dry
1) K,gg less than or equal to .98
2) Assume aqueous foam moderation
2. Drainage
a. Designed to prevent inadvertent draining below 194' 1 "
3. Capacity
a. Maximum of 288 spent fuel assemblies G. Component Cyclic or Transient Limits (Table 5.7-1)
1. Reactor Coolant System
a. Heatup cycles at less than 100*F/ hour or cooldown at less than 100*F/ hour
1) 200 - .
b. Pressurizer cooldown cycles less than or equal to 200*F/ hour
1) 200
c. Loss of load without immediate reactor or turbine trip
1) 80
d. Loss of offsite AC power
1) 40
a. Partial loss of flow - one loop lJ-
1) 80~ ,
f. ' Reactor trip cycles
1) 400 I

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a LO-LP-39216-00 )

ill. LESSON OUTLINE: NOTES l

g. Inadvertent auxiliary spray actuation cycles
1) 10
h. Leak tests - 2485 psig
1) 50 - 1
1. Hydrostatic pressure tests - 3107 psig
1) 5
2. Secondary
a. Steam line break greater than 6 inches
1) I
b. Hydrostatic pressure tests - 1461 psig
1) 5 III. SUP0fARY A. Site
1. Exclusion Area
2. Low Population Zone

. B. Containment

1. Configuration
2. Design Pressure and Temperature C. Reactor Core
1. Fuel Assemblies
2. Control Rod Assemblies

~

D. Reactor Coolant System

1. Design Pressure and Temperature
2. Volume 8

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LO-LP-39216-00 lil. LESSON OUTLINE: NOTES E. Meteorological Tower Location F. Fuel Storage

1. Criticality
2. Drainage -
3. Capacity G. Component Cyclic or Transient Limits 4

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Y 9 50.73 a

Chapter l Neeleer Regoletery Commisslannature of the event) or a proc ntrary error:

at the start of the event i es ofand to an that (ii) Whether con. procedure,cowas a direct approved the error was tributed to the event.(C) Datesresult and of approximate an error in ant m approved pro-occurrences, t or (D) The cause of each componenf cedure, or was associated with an ac-tiv system failure or personnel error, i an approved procedure; i tics of h ism, known.

(E)ef The f (iii) Any unusual character swork location (e.g., h and fectf ailure of eachmode.

failed 'mec component,ian the that directly contributed to the error; known. d tifica- and lved (F) The Energy Industry I encomponent (iv) The type of personnel function iden-invotility.li-tion System (i.e.. contractor personnel, unonllcensed ti!!er and system name tifica- censed of eachoperator, compo-nent or system utilityoperator, lly ini- other referred utility p (1) The Energy Industry IdenIEEE Std(K) Automatically and manua tion System is defined in: Recommend- tlated safety system responses. manufacturer and mode i 803-1933 (May 16.1983) (L) The of I ed Fractices for Uniquenumber IdentificationPlants (or other identification)each and Related com Fac l pies and Definitions,803-1983 has been ft con-ceap-event. (3) An assessment of the sa of e ythe (2) IEEE Std and implications proved for incorporation by referen sequences by the Director of the Federal Regis- <

ter. A notice of any changes made event. to This ansessment that could have per.

must include the material incorporated from componentaformedby referencewill thethat samebefunctionpublished in the P as the com-and systems failed '

1stan. Copies may be obtainedthe 345 East 47th during the event.

ponents Institute of ti e Electrical and E tronics Engineers. (4) A description of any correc v Street. New York, NY 10017. A actions copy isplanned as a result of the available for inspection and copying for a fee Room.1717 Document at the Commission's H 8treet NW.,

event, Publicincluding those to reduce the i ilar in the future.

Washington, D.C. andevents at the (5) Reference Office at the ofthe to any previous same plant that Federal sm are Registe Washington D.C. ith ber (G) For failures of components w known (6) Theto the namelicensee.

and telephone num multiple funcuens, include of a person a list who within the licensee's ofsystems is knowledgeable about or om.#sy fu orgs-were also affected, t ain nisation the a r event and can The provide addition of(H) For failure a safety system that renderedan inoperable, the esu-plant's characterlsucs. i (c) Supplemenest informat on.

mate of the elapsed time from the Commission maydis-covery require the licensee of the failure f h to submit specific additional informs-was returned (I)The to service.

method of discovery o eac tion beyond that required by para-component or systeum faGure or graph proce- (b) of this section if the Cc,m-dural error, td mission finds that supplemental mate-(JXI) Operator acuens that affec e rial is necessary for complete under-the course of the event, including op-erster errors, yn.,.a.! deficiencies,or standing information of anboth, unusually will that be contributed complex y.._

supplemental (2) For each ni- made in writing and the licensee censee shall discuss:

(i) Whether the error was a cog supplement to the initial LER. Licensee tive error (e.g. failure to recognise (d) theSubmission of reports.

actual plant condiuon. failure Event Reports must be prepared to real-Ise whichon systems I the true ing, failure to recognise 457

6

{ 50.73 Title 10-Energy Form NRC 366 and submitted within unless the Commission shall give its 30 days of discovery of a reportable consent in writina.

event or situation to the U.S. Nuclear (b) An application for transfer of a Regulatory Commission. Document Ilcense shall include as much of the in-Control Desk. Washington. D.C. 20555. formation describea in ii 50.33 and The licensee shall also submit an addi- 50.34 of this part with respect to the tional copy to the appropriate NRC identity and technical and financial Regional Office listed in Appendix A qualifications of the proposed trans-to Part 73 of this chapter. feree as would be required by those (e) Report legibility. The reports and sections if the spplication were for an copies that licensees are required to initial license, and, if the license to be submit to the Commission under the issued is a class 103 license. the infor-provisions of this section must be of mation required by 6 50.33a. The Com-sufficient quality to permit legible re- mission may require additionst infor.

roduction and micrographic process- mation such as data respecting pro-(f') Exemptions. Upon written re- posed safeguards assinst hazards from radioactive materials and the appli-quest from a licensee including ade- cant's qualifications to protect against quate of the NRC justification staff, theor at the Executive NRC initiation such har.ards. The application shall in-Director for Operations may, by a clude also a statement of the purposes l letter to the licensee, grant exemp. for which the transfer of the license is tions to the reporting requirements requested, the nature of the transac-under this section. tion necessitating or making desirable (g) Reportable occurrences The re- the transfer of the license. and an quirements' contained in this section agreement to limit access to Restricted replace all existing requirements for 11- Data pursuant to i 50.37. The Commis-censees to report " Reportable Occur- sion may require any person wfio sub-rences" as defined in individual plant mits an application for license pursu-Technical Specifications. ant to the provisions of this section to (48 FR 33468. July St.19631 file a written consent from the exist-ing licensee or a certilled copy of an US/IAEA SAFaoVARDs AoRasassNT order or judgment of a court of Compe-tent jurisdiction attesting to the per-8 54.78 Installetten information and ver. son's riaht (subject to the licensing re-iflestion. quirements of the Act and these regu-Each holder of a construction permit lations) to possession of the facility in-shall. If requested by the Commission. volved.

submit installation information. (c) After appropriate notice to inter-permit verification thereof by the In- ested persons, including the existing 11-ternational Atomic Energy Agency, censee, and observance of such proce-and take such other action as may be dures as may be required by the Act or necessary to implement the US/IAEA regulations or orders of the Commis-Safeguards Agreement, in the manner sion. the Commission will approve an set forth in llTS.4 and 78.11 through appilcation for the transfer of a 11-75.14 of this chapter. cense, if the Commission determines:

(45 FR SM11. July 31.19001 (1) That the proposed transferee is qualified to be the holder of the 11-TRANSFans or LICapess-CRsDIToRs* Cense; and RioMonasNasa or LacsNses (2) That transfer of the license is otherwise consistent with applicable O 50.80 'fremster of Ilsemess. provisions of law. regulations, and (a) No license for a production or orders issued by the Commission pur-utilisation facility, or any right there- suant thereto~

under, shall be transferred, assigned.

. or in any manner disposed of, either (42 U.s.c. 2132-2138. 2239) 7 voluntarily or involuntarily, directly (se FR este. Oct. 10.1961. as amended at 35 or indirectly, through transfer of con- FR 19eet. Dec. 29.1970: 3s FR 3954. Feb. 9.

trol of the license to any person. 19731 458 ,

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