ML20203K858
| ML20203K858 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/08/1986 |
| From: | Brown R, Missig N GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20203K798 | List: |
| References | |
| LO-LP-39217, LO-LP-39217-00, NUDOCS 8608210383 | |
| Download: ML20203K858 (19) | |
Text
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1 Georgia Power POWE3 GEteERAflCN DEPARTME%f g'
VOGTLE ELECTRIC GENERATING PLANI yn.
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TITLE: ADMINISTRATIVECONTR0EM NUMBER-L -LP-39217-00 LICENSED OPERATOR TRAINING 0 PROGRAM: REVISION-AUTHOR: N. MISSIG DATE: 8/7/86 APPROVED: TMfM DATE: g/r//g INSTRUCTOR.GUIDELINEN
- 1. TRANSPARENCY PROJECTOR
- 2. WHITE BOARD WITH MARKERS O
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- 1. PURPOSE STATEMENT: l TO TEACH THE ADMINISTRATIVE CONTROLS ESTABLISHED AND REQUIRED BY TECHNICAL SPECIFICATIONS.
ll. LIST OF OBJECTIVES:
- 1. The student will be able to list the minimum shif t crew composition required by technical specifications.
- 2. The student will be able to differentiate between events requiring immediate, one hour and four hour reports to the NRC.
- 3. The student will be able to give the actions required for a safety limit violation.
- 4. The student will be able to list the requirements for entrance into a high or a high-high radiation area.
- 5. The student will be able to list the basic functions of the PRB End SRB. -
- 6. The student will be able to list the three requirements for making a temporary change to a procedure.
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REFERENCES:
TECHNICAL SPECIFICATIONS SECTION 6 ADMINISTRATIVE CONTROLS 10CFR50 r
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LO-LP-39217-00
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Ill. LESSON OUTLINE: NOTES I. INTRODUCTION A. Required by 10CFR50.36 B. Administrative controls that relate to:
- 1. Organization and management
- 2. Procedures
- 3. Record keeping
- 4. Review and audit
- 5. Reporting II. PRESENTATION A. Responsibility
- 1. Read Section 6.1 B. Organization LO-TP-39217-00-001
- 1. Details onsite and offsite organization LO-TP-39217-00-002
- 2. Read Section 6.2
- a. Minimum shift composition LO-TP-39217-00-003
. C. Plant Staff Qualifications
- 1. Read Section 6.3 D. Training
- 1. Read Section 6.4 E. Review and Audit I
Establishes two review boards 1.
- a. ' Onsite - upper plant staff
- b. Offsite - Atlanta staff
- 1) For Hatch and Vogtle !
l
- 2. Briefly review Section 6.5 s 4
. I LO-LP-39217-00 j i
- lli. LESSON OUTLINE: NOTES 1 F. Rcportable Event Action
- 1. Details reporting for specific events 1
- 2. Three different time requirements
- a. Immediate
- b. Within one hour
- c. Within four hours
- 3. Details writing License Event Reports (LER's)
- 4. Read through handout from 10CFR50 LO-H0-39217-00-001
- 5. Review the rast of Section 6.6 G. Safety Limit Violation
- 1. Ask what are safety limit violations
- 2. Read Section 6.7 H. Procedures and Programs
- 1. Defines what activities require procedures
- a. Read Section 6.8.1
. 2. Defines review and approval
- a. Read Section 6.8.2
- 3. Defines how changes are made
- a. Read Section 6.8.3
- 4. Progress - Section 6.8.4
- a. Primary Coolant sources outside cant.
- b. In-Plant Radiation Monitoring
- c. Secondary water chemistry
- d. Post accident sampling i
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LO-LP-39217-00 lil. LESSON OUTLINE: NOTES I. Reporting Requirements
- 1. Details normal reporting to NRC
- 2. Briefly review reports required. j J. Record Retention -
- 1. Required for 5 years
- a. Read Section 6.10.1
- 2. Required for life of facility i I
- a. Read Section 6.10.2 i K. Radiation Protection Program j i
- 1. Complies with 10CFR20 1
- 2. Read Section 6.11 !
I L. High Radiation Area greater than 100 mrem / hour ,.
l
- 1. 10CFR20 requires locked doors
- 2. In lieu of 10CFR20 requirements
- a. Lists the three requirements for entry
. b. Read section 6.12.1
- 3. List added requirement for High-High(greater than 1000 mR/hr) l
- a. Locked doors or flashing lights ,
I
- b. As well as 6.12.1
- c. Read section 6.12.2 M. Process, Control Program
- 1. Solid Rad Wasta
- 2. Read section 6.13 6
a-
LO-LP-39217-00
- lli. LESSON OUTLINE: NOTES N. Offsite Dose Calculation Manual
- 1. Gaseous and Liquid Rad Waste
- 2. Read Section 6.14
- 0. Major changes to Liquid, Gaseous and Solid Rad Waste systems. ,
l
- 1. Read Section 6.15 i III.
SUMMARY
A. Review Objectives S
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{ 50.72 Title 10-Energy 5 50.72 Immediate notification require. (B) Any deviation from the plant's ments for operating nuclear power re- Technical Specifications authorized actors. pursuant to I 50.54(x) of this part.
(a) Genersi requirements.' (1) Each (ii) Any event or condition during nuclear power reactor licensee licensed operation that results in the condition under 150.21(b) or 5 50.22 of this part of the nuclear powerplant, including shall . notify the NRC Operr.tlons its principal safety barriers, being seri-Center via the Emergency Notification ously dest aded; or results in the nucle.
System of: ar power plant being:
(1) The declaration of any of the ( A) In an unanalyzed condition that Emergency Classes specified in the II. significantly compromises plant censee's approved Emergency Plan;s safety; or (B) In a condition that is outside the (11) Of those non Emergency events design basis of the plant; or specified in paragraph (b) of this sec. (C) In a condition not covered by the tion. plant's operating and emergency pro-(2) If the Emergency Notification cedures.
System is inoperative, the licensee (iii) Any natural phenomenon or ,
shall make the required notifications other external condition that poses an l via commercial telephone service. actual threat to the safety of the nu-other dedicated telephone system, or clear power plant or significantly ham-any other method which will ensure pers site personnel in the performance that a report is made as soon as practi- of duties necessary for the safe oper-cal to the NRC Operations Center.* ation of the plant.
(3) The licensee shall notify the (iv) Any event that results or should NRC immediately after notification of have resulted in Emergency Core the appropriate State or local agencies Cooling System (ECCS) disch1rge into -
and not later than one hour after the the reactor coolant system as a result time the licensee declares one of,the of a . valid signal.
Emergency Cla==ma. (v) Any event that results in a major (4) When making a report under loss of emergency assessment capabill-paragraph (aM3) of this section, the 11- ty. offsite response capability. or com-censee shall identify: munications capability (e.g., signifi-(1) The Emergency Class declared; or cant' portion of centrol room indica-(11) Either paragraph (bx1). "One- tion. Emergency Notification System.
Hour Report." or paragraph (bM2). or offsite notification system).
"Four-Hour Report." as the paragraph (vi) Any event that poses an actual of this section requiring notification of threat to the safety of the nuclear t,he Non-Emergency Event. power plant or significantly hampers (b) Non emergency events-(1) one- site personnel in the performance of hour reports. If not reported as a dec- duties necessary for the safe operation laration of an Emergency Class under of the nuclear power plant including paragraph (a) of this section, the li- fires, toxic gas releases, or radioactive consee shall notify the NRC as soon as releases.
practical and in all cases within one (2) Four-hour reports. If not report-hour of the occurrence of any of the ed under paragraphs (a) or (bx1) of following: this section, the licensee shall notify (IXA) The initiation of any nuclear the NRC as soon as practical and in all plant shutdown required by the cases, within four hours of the occur-plant's Technical Specifications. rence of any of the following:
1 (i) Any event, found while the reac-
'Other guerements for immediate notifi- tor is shut down, that, had it been
- callon of the NRC by licensed operauns nu- found while the reactor was in oper-83'*' power reactors are contained else- ation. would have resulted in the nu-a where in this chapter, in particular* clear power plant, including its princl-i
- i s.o.r.
, hosesos. 130.403.
Emersoney I 5e.30.
Classes pal safety barriers, being seriously de-and 6 73.71.
are addressed I in Appendia E of this part. graded or being in an unanalyzed co j ' Commercial telephone number of the dition that significantly compro j
MRC Operations Center is t 203) 951-0660. plant safety.
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&b Chapter I-Nuclear Reguietery Commission 9 50.73 (11) Any event or condition that re- this section in addition to making the suits in manual or automatic actuation required initial notification, each 11-of any Engineered Safety Feature censee, shall during the course of the (ESF). Including the Reactor Protec- event:
tion System (RPS). However, actu- (1) Immediately report (i) any fur-ation of an ESF including the RPS. ther degradation in the level of safety that resulta from and is part of the of the plant or cther worsening plant preplanned sequence during testing or conditions, including (hose that re-reactor operation need not be report- quire the declaration of any of the ed. Emergency Classes. If such r. declara-(ill) Any event or condition that tion has not been previously made. or alone could have prevented the fulfill- (11) any change from one Emergency ment of the safety function of struc- Class to another, or (111) a termination tures or systems that are needed to: of the Emergency Class.
( A) Shut down the reactor and main- (2) Immediately report (i) the results tain it in a safe shutdown condition, of ensuing evaluations or assessments (B) Remove residual heat. of plant conditicas. (ii) the effective-(C) Control the release of radioac- ness of response or protective meas-tive material, or ures taken, and (111) Information relat-(D) Mitigate the consequences of an ed to plant behavior that is not under-accident. stood.
(lvMA) Any airborne radioactive re- (3) Maintain an open, continuous lease that exceeds 2 times the applica- communication channel with the NRC ble concentrations of the limits spect- Operations Center upon request by fled in Appendix B. Table II of Part 20 the NRC.
of this chapter in unrestricted areas, when averaged over a time period of (4s m 3 pes. Aug. 29.1983: 48 {;R 400s2.
sept.12.19s31 -
one hour.
(B) Any liquid effluent release that E 50.73 1,leennee event report system.
exceeds 2 times the liniiting combined (a) Reportable events. (1) The holder Maximum Permissible Concentration of an operating license for a nuclear (MPC) (see Note 1 of Appendix B to Part 20 of this chapter) at the point of power plant (licensee) shall submit a entry into the receiving water (i.e., un. Licensee Event Report (LER) for any event of the type described in this restricted ares) for all radionuclides paragraph within 30 days after the i except tritium and dissolved noble discovery of the event. Unless other-gases, when averaged over a time wise specified in this section, the 11-period of one hour. (Immediate notif t. censee shall report an event regardless cations made under this paragraph also satisfy the requirements of para. of the plant mode or power level, and graphs (sM2) and (bM2) of 9 20.403 of structure. regardless of the significance of the Part 20 of this chapter.) system, or component that (v) Any event requiring the trans. Initiated the event.
port of a radioactively contaminated (2) The licensee shall report:
person to an offsite medical facility (IM A) The completion of any nuclear for treatment. plant shutdown required by the (vi) Any event or situation, related plant's Technical Specifications; or to the health and safety of the public (B) Any operation or condition pro-l or onsite personnel, or protection of hibited by the plant's Technical Spect-fications; or the environment. for which a news re.
lease is planned or notification to (C) Any deviation from the plant's other government agencies has been Technical Specifications authorized or will be made. Such an event may in- pursuant to i 50.54(x) of this part.
ciude an onsite fatality or inadvertent (11) Any event or condition that re-release of radioactively contaminated sulted in the condition of the nuclear materials. power plant, including its principal (c) Followsp noH/lcolion. With re- safety barriers, being seriously degrad-
. spect to the telephone notifications ed, or that resulted in the nuclear made under paragraphs (a) and (b) of power plant being:
as-eas o-na-se 455
4 l 50.73 Title 10-Energy (A) In an unanalyzed condition that (C) Control the release of radioac-significantly compromised plant tive material: or safety; (D) Mitigate the consequences of an (B) In a condition that was outalde accident.
the design basis of the plant; or (villH A) Any airborne radioactivity (C) In a enndition not covered by the release that exceeded 2 times the ap-plant's operating F.nd emergency pro- plicable concentrations of the limits
- cedures. specified in Appendix B. Table II of (111) Any natural phenomenon or Part 20 of this chapter in unrestricted l other external condition that posed an areas, when averaged over a time actual threat to the safety of the nu- period of one hour.
clear power plant or significantly ham- (B) Any liquid effluent release that pered site personnel in the perform- exceeded 2 times the limiting com.
ance of duties necessary for the safe bined Maximum Permissible Concen-operation of the nuclear power plant. tration (MPC)(see Note 1 of Appendix (lv) Any event or condition that re- B to Part 20 of this chapter) at the sulted in manual or automatic actu. point of entry into the receiving water ation of any Engineered Safety Fea. (i.e., unrestricted area) for all radionu-ture (ESP), including the Reactor Pro- clides except tritiu m and dissolved tection System (RPS). However, actu. noble gases, whea averaged over a ation of an ESF, including the RPS, time period of one hour.
that resulted from and was part of the (ix) Reports submitted to the Com-preplanned sequence during testing or mission in accordance with paragraph reactor operation need not be report- (aH2Hvill) of this section also meet the ed. effluent release reporting .. require.
(v) Any event or condition that ments of paragraph 20.40$(hM5) of -
alone could have prevented the fulfill- Part 20 of this chapter.
ment of the safety function of struc- (x) Any event that posed an actual tures or systems that are needed to: threat to the safety of the nuclear (A) Shut down the reactor and main- power plant or significantly hampered tain it in a safe shutdown condition: site personnel in the performance of (B) Remove residual hest; duties necessary for the safe operation !
(C) Control the release of radioac- of the nuclear power plant including tive material; or fires, toxic gas releases, or radioactive i (D) Mitigste the consequences of an release.
accident. (b) Contents. The Licensee Event (vi) Events covered in paragraph Report shall contain:
(aH2XV) of this section may include (1) A brief abstract describing the one or more procedural errors, equip- major occurrences during the event, ment failures, and/or discovery of including all component or syst.em fall-design, analysis, fabrication, construe. ures that contributed to the event and tion, and/or procedural Inadequacies, significant corrective action taken or ,
However, individual component fall- planned to prevent recurrence.
ures need not be reported pursuant to (2HI) A clear, specific, narrative de- l this paragraph if redundant equip- scription of what occurred so that 1 ment in the same system was operable knowledgeable readers conversant and kvailable to perform the required with the design of commercial nuclear l safety function. power plants, but not familiar with (vil) Any event where a single cause the details of a particular plant can or condition caused at least one inde- understand the complete event.
pendent train or channel to become in- (ii) The narrative description must ;
operable in multiple systems or two in. Include the following specific informa- I dependent trains or channels to tion as appropriate for the particular l become inoperable in a single system event: I designed to: (A) Plant operating conditions (A) Shut down the reactor and main- before the event. 1 thin it in a safe shutdown condition; (B) Status of structures, compo- l (B) Remove residual heat; nents, or systems that were inoperable j
- 456 1 i j
)
E _ ___ ._ __ a
Chapter l-Noclear Reguletory Commission 9 50.73 at the start of the event and that con. nature of the event) or a procedural tributed to the event. error:
(C) Dates and approximate times of (ff) Whether the error was contrary i occurrences. to an approved procedure. was a direct t
I (D) The cause of each component or result of an error in r.n approved pro-
- system failure or personnel error, if cedure, or was associated with an ac-known.
(E) The failure mode, mechanism. an tivity or task that was not covered by approved procedure; and effect of each failed component, if (iff) Any unusual characteristics of
( known. the work location (e.g. heat. noise)
(F) The Energy Industry Identifica- that directly contributed to the error; tion System component function iden- and i tifier and system name of each compo- (fu) The type of personnel involved nent or system referred to in the IAR. (i.e.. contractor personnel, utility ll-(1) The Energy Industry Identifica- censed operator, utility nonlicensed tion System is defined in: IEEE Std operator, other utility personnel).
803-1983 (May 18,1983) Recommend- (K) Automatically and manually ini-ed Practices for Unique Identification (lated safety system responses.
Plants and Related Facilities-Princi- (L) The manufacturer and model pies and Definitions.
(2) I d M Std 803-1983 has been ap- number (or other identification) of each component that failed during the proved for incorporation by reference event, by the Director of the Federal Regis. (3) An assessment of the safety con-ter. A notice of any changes made to sequences and implications of the the material incorporated by reference will be published in the FuosaAL Reo- event. the This assessment must include availability of other systems or _
IsTsa. Copies may be obtained from components that could have per-the Institute of Electrical and Elec- formed the same function as the com-tronics Engineers. 345 East 47th ponents and systems that failed Street. New York. NY 10017. A copy is during the event.
available for inspection and copying (4) A description of any corrective for a fee at the Commission's Public actions planned as a result of the Document Room 1717 H Street. NW.. event, including those to reduce the Washington. D.C. and at the Office of probability of similar events occurring the Federal Register.1100 L 8t. NW.. In the future.
Washington. D.C. (5) Reference to any previous similar (0) For failures of components with events at the same plant that are multiple functions, include a list of known to the licensee.
systems or secondary functions that (6) The name and telephone number were also affected, of a person within the licensee's orga-(H) For failure that rendered a train niration who is knowledgeable about of a safety system inoperable, an esti- the event and can provide additional mate of the ethosed time from the dis- Information concerning the event and covery of the failure until the train the plant's characteristics.
was returned to servies. (c) Supplemental information. The (I) The method of discovery of each Commission may require the licensee component or system failure or proce- to submit specific additional informa-dural error. Lion beyond that required by para-(J)(1) Operator actions that affected graph (b) of this section if the Com-the course of the event. including op- mission finds that supplemental mate-erster errors, procedural deficiencies, rial is necessary for complete under-or both, that contributed to the event. standing of an unusually complex or (2) For each personnel error, the li- significant event. These requests for consee shall discuss: supplemental information will be (1) Whether the error was a cogni- made in writing and the licensee shall tive error (e.g., failure to recognise the submit the requested information as a actual plant condition. failure to real- supplement to the initial LER.
Ise which systems should be function- (d) submission of reports. Licensee ing, failure to recognise the true Event Reports must be prepared on 457
-~ , _ _ _ _ - _ . , - , _ , , ,__,.m_ ..__,_-_.n,-- - _
$ 50Jg Title 10-Energy Form NRC 366 and submitted within unless the Commission shall give its 30 days of discovery of a reportable consent in writing.
event or situation to the U.S. Nuclear (b) An application for transfer of a Regulatory Commission. Document lleense shall include as much of the in-Control Desk. Washington, D.C. 20555. formation described in il 50.33 and The licensee shall also submit an addi- 50.34 of this part with respect to the tional copy to the appropriate NHC 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 application 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 I 50.33a. The Com-sufficient quality to permit legible re- mission may require additional infor-production and micrographic process- ,
posed safeguards against hazards from (f) Kremptions. Upon written re- radioactive materials and the appil-quest from a licensee including ade- cant's qualifications to protect against quate justification or at the initiation such hazards. The application shall in-of the NRC staff, the NRC Executive clude also a statement of the purposes Director for Operations mav. by a 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-Lion necessitating or making desirable under this section. the transfer of the license, and an (g) Reports 6de occurrences. The re-quirements contetn2 in this section agreement to limit access to Restricted replace all exlNng requirements for 11- Data pursuant to i 50.37. The C6mmis- --
censees to reprt " Reportable Occur- sion may require any person who 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 33868. July 26.19831 file a written consent from the exist-ing licensee or a certilled copy of an US/IAEA SAFsGUARDs AonssassNT order or judgment of a court of compe-tent jurisdiction attesting to the per-5 54.78 Installation infor nation and ver- son's right (subject to the licensing re-III'843*"- 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 'nay be required by the Act or necessary to implement the US/IhEA regulations or orders of the Commis-Safeguards Agreement,in the manner sion. the Commission will approve an set forth in 56 78.8 and 78.11 through application for the transfer of a 11-78.14 of this chapter. cense,if the Commission determines:
(45 FR SM11. July 31.19 eel (1) That the proposed transferee is qualified to be the holder of the 11-TaANsFsas oF LICapss5-CR DIToRs* cense; and RIMuammsu or Lacsussa (2) That transfer of the license is otherwise consistent with applicable 9 50.00 't'reaster et h provislo'is 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. 2132-2135. 2239) voluntarily or involuntarily, directly (26 FR 9544. Oct.10.1961. ns amended at 35
' or indirectly, through transfer of con- FR 19661. Dec. 29,1970: 3s FR 3954. Feb. 9.
trol of the license to any person. 19731 458 l
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- L c- TP - .$92*3-co. oc.2 TABLE 6.2-1 MINIMUM SHIFT CREW COMPOSITION TWO UNITS WITH A COMMON CONTROL ROOM
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UNIT 1 IN MODES 1. 2. 3. OR 4 UNIT 2IN MODE:
1, 2. 3, OR 4 5OR0 DEFUELED
-. POSITION OS 1 1 1 SMO 1 1 1
- RO 3 3 2 NLO 3 3 2 STA' 1 1 1 UMT1IN 0000E 5 OR 0 UIET 2 W 8000E:
POSIT 1001 1,2,3. OR 4 '5OR0 DEFUELED OS 1 1 1 i SRO 3 0 0 RO 3 2 1 NLO 3 3 1 STA' 1 0 0 UlWT1 DWUELED UNIT 2IN 8000E:
POSITION 1,2. 3. OR 4 5OR0 DEFUELED 08 1 1 0 SRO 1 0 0 RO 2 , 1 0 NLO 2 1 0 STA' 1 0 0
- THE STA IS NOT REQUIRED ON SHIFT IF THE QUAURCATIONS 0F THE OPERATIONS SUPWMSOR ARE UPGRADED TO FULFE.L THE REQUIRDIENTS OF THE STA POSIT 100L vocTLE-uutt i 6h' - . - _ - _ _ _ _ _ . - - -
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( FUEL HANDLING SYSTEMS AND OPERATIONS I The fuel handling course for the Operations Department Shift Licensed Operators will cover the equipment necessary for fuel receipt, storage, core alterations, and shipment offsite along with all the associated operations and administrative requirements necessary to support all refueling operations. Generally this will include a discussion of the operation of all related fuel handling equipment and their interlocks combined with the requirements of the VEGP technical specifications and all associated VEGP Operations Department procedures. The goal being an operator that understands the refueling process, how refueling is physically accomplished and what precautions / limitations apply. Attached is a summary of the Fuel Handling Systems and Operations course.
I. FUEL STORAGE FACILITIES A. FUNCTION, LOCATION, AND DESIGN FEATURES OF THE NEW AND SPENT FUEL STORAGE AREAS B. DISCUSSION OF REQUIRED SUPPORT SYSTEMS FOR FUEL STORAGE C. DISCUSSION OF TECHNICAL SPECIFICATIONS FOR THE SPENT FUEL POOL
- 1. FUEL HANDLING EQUIPMENT D. DISCUSSION OF THE LOCATION, FUNCTION, AND DESIGN FEATURES OF THE:
- 1. SPENT FUEL CASK CRANE
- 2. SPENT FUEL POOL BRIDGE CRANE
- 3. REFUELING MACHINE
- 4. NEW FUEL ELEVATOR
- 5. UPENDERS
- 6. " FUEL TRANSFER CART
- 7. NEW FUEL HANDLING TOOL
- 8. SPENT FUEL HANDLING TOOL
I. ,
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'I E. OPERATIONAL CAPABILITIES OF THE FOLLOWING EQUIPMENT INCLUDING ALL INTERLOCKS:
- 1. SPENT FUEL CASK CRANE
- 2. SPENT FUEL POOL BRIDGE CRANE
- 3. NEW FUEL ELEVATOR
- 4. UPENDERS
- 5. FUEL TRANSFER CART
- 6. REFUELING MACHINE F. DISCUSSION OF ALL TECHNICAL SPECIFICATIONS RELATED TO THE EQUIPMENT LISTED ABOVE II. FUEL CYCLE A. DISCUSSION OF ALL THE STAGES OF THE FUEL CYCLE FROM INITIAL RECEIPT THROUGH SHIPMENT OF SPENT FUEL OFFSITE FOR LONG TERM STORAGE _
III. FUEL HANDLING OPERATIONS A. DISCUSSION OF THE CONDUCT OF REFUELING OPERATIONS B. PRECAUTIONS AND LIMITATIONS FOR HANDLING NEW AND PARTIALLY SPENT FUEL ASSEMBLIES C. DISCUSSION OF THE PROPER OPERATION OF THE:
- 1. FUEL TRANSFER SYSTEM
- 2. SPENT FUEL POOL BRIDGE CRANE i
- 3. NEW FUEL ELEVATOR
- 4. NEW FUEL HANDLING TOOL
- 5. SPENT FUEL HANDLING TOOL
- 6. REFUELING MACHINE D. DISCUSSION OF THE CORRECT METHOD OF NEW FUEL RECEIPT E. UNLOADING, INSPECTION, AND STORAGE OF NEW FUEL
4 F. DISCUSSION OF THE REFUELING PROCEDURE ,
1 G. REFUELING CAVITY WATER LEVEL SURVEILLANCE 1
H. DISCUSSION OF FUEL HANDLING UNUSUAL EVENTS INCLUDING PROPER OPERATOR ACTIONS TO BE TAKEN I. DISCUSSION OF ALL REFUELING RELATED TECHNICAL SPECIFICATIONS INCLUDING ALL ACTIONS REQUIRED TO BE TAKEN WITHIN ONE HOUR.
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MITIGATING CORE DAMAGE VEGP Mitigating Core Damage training ensures that all licensed operators are trained in the use of installed plant systems used to control or mitigate an accident that involves severe core damage.The following topics are covered:
1.MITIOATING CORE DAMAGE INTRO (LO-LP-36001-OO-C) 2.MCD CORE COOLING MECHANICS (LO-LP-36101-OO-C) 3.MCD INCORE INSTRUMENTATION (LO-LP-36102-OO-C)
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4.MCD EXCORE INSTRUMENTATION (LO-LP-36103-Od-C) 5.MCD VITAL INSTRUMENTATION (LO-LP-36104-OO-C) 6.MCD REACTOR CHEMISTRY (LO-LP-36105-OO-C) 7.MCD RADIATION MONITORING (LO-LP-36106-OO-C) 8.MCD GAS GENERATION (LO-LP-36107-OO-C)
Each lesson contains a student handout and transparencies. Mitigating Core Damage is at least 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in duration and is normally covered concurently with the control Room Operations phase of training. Portions of Emergency Procedure training covering Transients and Accident analysis are related to MCD training and serve to reinforce its concepts. However no credit for this training is applied to Mitigating Core Damage. Attached is an example of the Mitigating Core Damage training materials.
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