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SECURITIES AND EXCHANGE COMMISSION (Release No. 3 5 - 24694
)
Filings Under the Public Utility Holding Company Act of 1935
("Act")
August 12, 1988 Notice is hereby given that the following filing (s) has/have been made with the Commission pursuant to provisions of the Act and rules promulgated thereunder.
All interested persons are referred to the application (s) and/or declaration (s) for complete The statements of the proposed transaction (s) summarized below.
application (s) and/or declaration (s) and any amendment (s) thereto is/are available for public inspection through the Commission's
)
office of Public Reference.
Interested persons wishing to comment or request a hearing on the applicatAon(s) and/or declaration (s) should submit their views in writing by September 6, 1988 to the Secretary, Securities and 1:xchange Commission, Washington, D.C. 20549, and serve a copy on the relevant applicant (s) and/or declarant (s) at the address (es) specified below.
Proof of service (by affidavit in case of an attorney at law, by certificate) should be or, filed with the request.
Any request for hearing shall identify A
specifically the issues of fact or law that are disputed.
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person who so requests will'be notified of.any hearing, if l
ordered, and will receive p copy of any notice or order issued in i
the matter.
After said date,.the application (s) and/or s
declaration (s), as filed or as amended, may be granted and/or E
permitted to become effective.
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The Southern Company (70-7530)
The Southern Company (" Southern"), 64 Perimeter Center East, Atlanta, Georgia 30346, a registered holding company, and its i
electric utility subsidiaries, Alabama' Power Company ("APC"), 600 j
l North 18th Street, Birmingham, Alabama 35291, and Georgia Power j
Company ("GPC"), 333 Piedmont Avenue, N.E., Atlanta, Georgia I
' 3030s, have filed an application-declaration pursuant to Sections 1
6(a), 7, 9(a), 10, 12(b) and 13(b) of the Act and Rules 45 and i
I 86-95 thereunder.
Southern proposes to organize a new wholly owned Delaware subsidiary to be known as Southern Nuclear Operating Company, 4
- }
Inc., ("SONOPCOd), to consolidate the personnel of the Southern
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system companies involved in nuclear services into a single i
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organization.
SONOPCO's operating structure will be implemented in three phasec. Initially, key nuclear operations management I
In the second personnel will be shared between APC and GPC.
phase, which would begin upon approval by the Commission of the I
present application-declaration, SONOPCO will be organized as a service company that will provide APC and GPC with nuclear services, including plant operating services, fuel procurement services, administrative services and technical services, but will not own, finance or operate any nuc, lear or other utility In the third phase, SONOPCO will become responsible, on assets behalf of the owners and through contract with them, for the i
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a j 'e 3
fj operation and maintenance of all nuclear generating facilities owned by Southern electric system companies.
SONOPCO may apply to the Nuclear Regulatory Commission
("NRC") or its. successor for facility license or permits for the
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I Farley Nuclear Plant ("Farley"), owned and operated by APC, and 4
i for the Hatch Nuclear Planti (" Hatch") and Vogtle, Nuclear Plant
("Vogtle"), each of which is jointly owned by GPC, the Municipal i
Electric Authority of Georgia, Oglethorpe Power Corporation, and the City of Dalton, Georgia, and for which GPC is the present i
licensee and operator under an existing operating agreement.
F Nuclear services rendered by SONOPCO to nuclear plants not wholly owned by associates of the Southern system will be pursuant to service.or operating agreements that provide for billing at negotiated rates.
i Accounting, treasury, and other support services, as well as personnel, may be furnished to SONOPCO at cost by Southern Company Services, Inc., APC, and GPC.
S0kOPCO will render service to associated companies at cost, pursuant to Section 13 (b) of the Act.
The costs will be accounted for and billed to the owners of the subject facilities as prescribed by Rules 91 and 93 and the uniform system of accounts prescribed thereunder.
In the case of SONOPCO's services rendered for the Vogtle and Hatch units, these costs will be deterni,ned, accumulated, and
-allocated among the owners of Vogtle and Hatch in proportion to their ownership interests.
1
. p'
';4 SONOPCO will issue, and Southern vill purchase for cash all j
1' of the shares of SONOPCO's common stock for an aggregate consideration of up to $10 million.
Southern proposes to make open account advances to SONOPCO from time to time, which may be converted into capital contributions or shares of common stock of l
The rate of return on SONOPCO8s equity capital will not i
SONOPCO.
exceed the average of the most recent rates of return allowed by t
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i the Alabama Public Service Commission and the Georgia Public Service Commission on the equity capital of APC and GPC, l
respectively.
SoNOPCO also proposes to obtain funds from third party lenders.
The aggregate principal amount of advances to SONOPCO by Souchern or landers other than Southern will not i
exceed $50 million at any time outstanding.
Interest on open account advances by Southern will accrue at a rate not to exceed Unless the prime rate at a bank designated by Southern.
authorized by the Commission, loans by parties other than Southern will have maturities not to exceed ten years and will accrue interest at a rate not to exceed the lender's prime rate f
plus 2% for variable rate loans and the prime rate at the time of i
borrowing plus 34 for fixed rate loans.
Ioans by p _ ties other i
than Southern may be secured or unsecured and may be guaranteed by Southern, APC and/or GPC.
With respect to the initial capitalization of $10 million and.to open account advances from Southern, it is requested that the Commission reserve jurisdiction over amounts in excess of $5,ti~0,000 and 0
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$15,000,000, respectively, and over all advances from lenders 1
other than Southern.
Southern requests this financing authority through December 31, 1990.
For the Commission, by the Division of Investment Management, pursuant to delegated authority.
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Jonathan G. Katz Secretary 1
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By: Chirlcy E. Hollis Assistant Secretary 1
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aasep uglTE3 STATES
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NUCLEAR RESULATORY COMMISSION canon,,
k 101 MARIETTA STREET, NM.
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ATLANTA, GEORG4A 33323 i
AUG 11 1:ni8 Docket Nos. 50-321, 50-366 50-424, 50-425 License Nos. DPR-57, NPF-5 NPF-68 CPPR-109 l
Georgia Power Company ATTN: Mr. W. G. Hairston, III Senior Vice President -
Nuclear Operations l
P. O. Box 4545 j
Atlanta, GA 30302 i
. Gentlemen:
i
SUBJECT:
MEETING Sup04ARY - NUCLEAR OPERATIONS - TRANSITION ORGANIZATION l
This refers to the information meeting conducted in the NRC Region II Office on July 25, 1988.
This meeting was held at your request to discuss your current l
l transitional nuclear operations organization for the cceporate office, Vogtle facility and Hatch facility.
A list of attendees, a brief summary ard a copy of your handout are enclosed.
y It is our opinion that this meeting was beneficial and has kept us apprised j
of your nuclear operations organization.
In accordance with Section 2.790 of NRC's " Rules of Practice,". Part 2 l
Title 10, Code of Federal Regulations,'a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
Should you have any questions concerning this letter, we will be pleased to discuss them.
Sincerely,
-; _ h J. Nelson Grace Regional Administrator
Enclosures:
1.
Meeting. Summary 2.
List of Attendees
'3.
Georgia Power Company Presentation 2-cc w/encis:
(See page 2)
Georgia Power Company 2
AUG 11 1968 cc w/encls:
R. P. Mcdonald, Executive Vice President, Nuclear Operations P. D. Rice, Vice President, Project Director C. W. Hayes, Vogtle Quality Assurance Manager G. Bockhold, Jr., General Manager, Nuclear Operations L. Gucwa, Manager, Nuclear Safety and Licensing J. A. Bailey, Project Licensing Manager B. W. Churchill, Esq., Shaw, Pittman, Potts and Trowbridge D. Kirkland, III Counsel.
Office of the Consumer's Utility Council D. Feig, Georgians Against l
Nuclear Energy l
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ENCL.050RE 1 J
MEETING SUPMARY On July 25, 1988, representatives of Georgia Power Company (GPC) met with the NRC in the Region II office in Atlanta, Georgia to discuss the Corporate l
office, Vogtle facility, and Hatch facility nuclear. operations organization.
A list of meeting attendees is in Enclosure 2.
4 l
GPC gave a presentation which provided an organization status.
l An outline of GPC's presentation is given in Enclosure 3.
After approval by the Securities and Exchange Connission, a nuclear operating company consisting of the nuclear plants in the Southern Capany (Hatch, i
Farley, Vogtle) will be formed. The corporate office location will be decided once approval for the company is obtained.
A project organization has been i
established for each plant.
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3 ENCLOSURE 2 i
LIST OF ATTENDEES i
U. S. Nuclear Regulatory Commission - Region II L. A. Reyes, Director, Division of Reactor Projects (DRP)
V. L. Brownlee, Chief. Branch 3. DRP 4
H. C. Dance Chief. Section 18. DRP M. V. Sinkule Chief. Section 38, DRP j
D. M. Verrelli, Chief, Branch 1, DRP C. Patterson, Project Engineer, DRP f
NRC - Office of Nuclear Reactor Regulation j
- D. B. Matthews, Project Directorate II-3 Georgia Power Company W. G. Hairston, III, Senior Vice President', Nuclear Operations C. K. McCoy, Vice President, Nuclear Operations j
J. T. Beckham, Vice President Nuclear Operations i
T. J. McHenry, Manager, General Support t
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ENCLOSURE 3 DAMLEAR OPERATIONS - TRMSITION ORGANIZATIGN R. f*. MCDONALD EXEC VP - NUC OPS P. H. BRITT C. T. NGOK EXECUTIVE SECETARY SEN NGR Ma4LITY Ammmany N. S. HAIRSTON SR VP - NUC OPS T. J. NCE05tfu ASST TO EVP S SVP staC OPS SAFETY EVIEN BOAfe i
J. T. BECKHAM C. K. NCC0Y T. J. NCEsstfu VP - haar2 FAR DtATD4 VP - BaaCLEAR IVOSTLEI sem EERAL gapPeRT
- 3. L. MINTZ L. C. SEAZLEY N. E. Lose SENIOR SECRETARY EXECUTIVE SEINETAftY SECRETARY IV
(
L. T. SUCNAs J. P. MAE e J. J. manarTim NGR LIC S EMS - HATCH NOR LIC S EMS - WOSTLE IIER Tft0S S EER PEP
- 3. K. NCLEODu H. P. WALKER 4 S. C. ENALD pesR teti StFPORT IIGR NNT SUPPORT /DaacLEAR 100R RADIOLOGICAL SAFETY H. C. NIX S. 80CKHOLD N. B. HOSSYe BEN 349R - 9000 LEAR PLANT SEN 900R - NUCLEAR PLANT 8804 ADMIN SUPPORT l
07/21/se e Indicates a trenettlonal positten ulth incueInent serving in an acting capacly.
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Vogtle Electric Generating Plant 35110-C NUCLEAR OPERATIONS gemen na b
10 6
om Georgia Power 1,f,c
- m. ~a COMMON Unit VOld CHEMISTRY CONTROL OF THE REACTOR COOLANT SYSTEMVOID 1.O PURPOSE This procedure provides instructions for controlling the chemistry environment of the Reactor Coolant System (RCS).
2.0 DEFINITIONS 2.1 DOSE EQUIVALENT 10 DINE-131 (DEQ I-131)
Shall be that concentration of I-131 (microcurie / gram) which alone would produce the same thyroid dose as the cuantity and isotopic mixture of I-131, 1-132. I-133, 1-134 and 1-135 actually present.
The thyroid duse conversion factors used for this calculation shall be those listed in Table E-7 of NRC Regulatory Guide 1.109 Revision 1, October 1977.
2.2 E-BAR (E)
Average disintegration energy shall be the average (weighted in proportion to the concentration of each of the sum of the average radionuclide in the sample) beta and gamma,.e.ergies per disintegration (MEV/D) for the radionuclides other than radiciodines, with Icast half-lives greater than 14 minutes making up at 951 of the total non-radiciodine activity in the sample.
2.3 ZEOLITES Compounds of calcium, magnesium, aluminum and silica that, when incorporated into crud, can cause (1) a significant barrier to the heat tr.'nsfer, and (2) densification of crud, with the potential for increased concentration of lithium hydroxide at the clad surface.
2.4 MODE Operational modes refers to plant reactivity, thermal temperature conditions as power and average coolant stated in Table 1.2 of section 1 of the Technical 4
Specifications.
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PAGE No oCEDURE No.
HEVIStoN 2 of 44 VEGP 35110-c 10 f
a 3.0 PRECAUTIONS AND LIMITATIONS The following list of chemistry related Technical 3.1 Specifications and Limiting Condition for Operation (LCO) apply to the Reactor Coolant Syrrem:
3.1.1 3/4.4.7 Chemistry LCO 3.4.7 - The RCS chemistry shall be maintained i
within the limits specified below at all times.
Reactor Coolant System Chemistry Limits Steady State Limit Transient Limit Parameter Dissolved Oxygen *
$ 0.10 ppm 5 1.00 ppm l
Chloride 6 0.15 ppm 5 1.50 ppm Fluoride
$ 0.15 ppm s 1.50 ppm
- Limit not applicable with Tavg less than or equal to 250*F.
Action:
1)
Modes 1, 2, 3, and 4:
With any one or more chemistry parameters in a.
excess of its steady-state limit but withir.
Its transient limit, restore the parameter to within its steady-se. ace limit within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in at least HOT STANDBY within the ne::t J
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUIDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With any one or more chemis t ry ;'ar.ineters in excess of its transient limit, he in at leirt HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUIDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
I 2)
At All Other Times:
With the concentration of either chloride or fluoride in the RCS in excess of its steady-state limit for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or in excess of its transient limit reduce the pressurizer pressure to less than or equal to 500 psig, if applicable, and perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the RCS determine that the RCS remains acceptable for continued operation increasing the pressurizer pressure above prior te 500 psig or prior to proceeding to Mcc'e 4 The sample and analy, sis frequency is at leest once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> except disselved oxygen wher. Tovp is
< 250*F.
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DAGE No
- 'PhocEDURE No.
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-VEGP 35110-C 10 3 of 44 3.1. 2 --
3/4.4.8 Specific A ivig LCO 3. 4. 8.cific activity of~the reactor i
coolant shall Lc limited to:
Less than or equal to 1 microcurie per gram DEQ i
a.
1-131, and
^
b.
Less than or equal to 100/? microcuries per gram I
of,ross activity.
Applicability:
Modes 1, 2, 3, 4 and 5 4
Action:
l 1)
Modes 1, 2 and 3*:
With the specific activity of th'e reactor a.
coolant greater than 1 microcurie per gram DEQ 1-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the
.g t-limit line chown on Figure 1, be in at least HOT STANDBY with Tavg less than 500*r within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and 4
- With Tavg greater than or equal to 500'F.
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With the specific activiev of the reactor coolant greater than 100/E microcuries per gram of gross radioactivity, be in at least HOT STANDBY with Targ less than 500*F within j
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
2)
Modes 1, 3, 3, 4 and 5:
With the specific activity of the reactor coolant greater than 1 misrocurie per gram DEO I-131 or l
greater than 100/E microcuries per gram of gross radioactivity, perform the sampling and analysis requirements stated below until the specific activity of the reactor coolant is restored to within its ifmits.
i NOTE Special reports to the commission may be required as a result of exceeding RCS specific activity limits, refer to procedure 30020-C d-
" Chemistry Reports" and Tech Spec 6.8.1.2.b.
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PKoCEDUAE No REvissoN PAGE No l
VEGP-35110-C 10 4 of 44 l-Reactor. Coolant Specific Activity Sample and Analvsis Program
)
Modes in Vhich Sample And Type of Measurement Sample and Analysis Analysis And Analysis Frequency Required 1
- 1. Cross Radioactivity At least once per 1, 2, 3, 4 e
i Determination
- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
- 2. Isotopic Analysis Once per 14 days 1
for DEQ 1-131 concentration
- 3. Radiochemical for Once per 6 months ***
1 j
E Determination **
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Isotopic Analysis
- a. Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> li, 2#, 3#, 4#,
for Iodine including whenever the 5#
t I-131 I-133, and specific activity I-135 exceeds 1 uCi/ gram of DEQ 7-131 or 1
100/E uCi/ gram radioactivity and,
- b. One sample 1, 2, 3 between 2 and 6 4
i hours following a thermal power change 4
exceeding 15% of the rated thermal power within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period
- A gross. radioactivity. analysis shall consist cf the quantitative measurement of the total specific activity of the reactor coolant except for radionuclides with half-lives.less than 14 minutes ar.d all radioiodines.
The total specific activity shall be the sum of the degassed beta-gamma activity and the total of all identified gaseour. activitieu in the sar.ple within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the sample is taken and extrapolated hack to i
when the sample was taken.
Determination of the contributors to j
the gross rpt.cific activity shall be based upon those energy i
peaks identified virh a 95% confidence level.
The latest available datt may be used for pure beta-emitting radionuclides, l
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tgydON IPAGE No PMoCEDURE No
~ 35110-C 10 5 of 44 VECP
- A Radiochemical analysis' for E shall cer.sist of - the quantitative measurement.of the specific activity for each radionuclide except for radionuclides with half-lives less than 14 minutes and all radiciodines, which are identified in the reactor coolant.
The specific activities for these individuni f F for the radionuclides shall be used in the determination o reactor coolant cample.
Determinution of the contributors to E shall be based upon those energy _ peaks identifiable witt e 05%
confidence level.
- ' Sample to be taken after a minimum of 2 EFFD and 20 days of POWFR OPERATION bave elapsed since reactor was Inst subcritical for 48 hourn or longer i Until the specific activity of the RCS is restored within its limits.
3.1.3 3/4.9 Refueling Operations 3/4.9.1 Boror Concentration LCO 3.9.1 - The boron concentration of all filled i
portions of the reactor coolant system and the
)_,
refueling canal shall be maintained uniform and iI suf fi cient to ensure that the more restrictive of the following reactivity conditions is mets either:
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a.
A Feff of 0.95 or less, or l
b.
A boron concentration of greater than or equal to i
2000 ppm.
Applicability:
Mode 6
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Action:
4
'Jith the requirements of the above specification not
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satisfied.:immediately suspend all operations. involving CORE ALTERATIONS or positive reactivity chanFes and initiate and continue boration at greater than or equal i
to 30 gpm of a solution containing greate-than er equal to 7000 ppm boron or its equivalent until Keff is reduced to less than or equal to 0.95 er the boron concentration is restored to greater than or equal to j
2000 ppm, whichever is more restrictive.
L Surveillance Requirements i
-The boron concentration of the reactor c'eclant svstem 1
and refueling canal shall be determined by chemical analysis at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
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OcEDURE No.
REVISloN FAGE No VEGP 35110-C 10 6 of 44 3.2 All liquid and gas associated with the PCS and its directly connected support systems is p,ctentially radioactive and should be trea.ed as such at all tires.
Ensure gcod henith physics prcetices are exercised when handling liquid or gas associated with the primary systems.
3.3 The concept of time-distance-shielding should be folicwed to maintain dose as low as reasonably achievable (ALARA).
1.4 All reactor coolant contains some amount of dissolved i
radioactive gas.
Handling of reactor coolant liquids should be done in a well ventilated area.
3.5 Sample venreir containing radionetive or potentially radioactive liquid should be rightly sealed and properly labeled at all times unions actually performing analyses.
3.6 When all analyses for a given s.imple are complete, any remaining sample, liquid or gas. should be properly disposed of as soon as possible.
Do not leave unmarked or partially filled containers if liquid or gas in the
'. b hoods or sinks or on counter tops.
3.7 Evaporation or distillation of any radioactive liquid must be performed only in a laboratcry fume hood.
3.8 Radioisorolic analysis, for radioactive liquid and gas samples, sTould normally be perforined as soon am possible after sample collection to prevent ebr it,nn o; short half-life isotopes due to decay.
i NOTE 1
Certain samples may he held longer for decay of short lived iseropes in order to enhance detection of the longer lived isotopes.
3.9 If a significant discrepancy develoos in chemistry parameters between the reactor coolent liquid and the pressurizer liquid samples,(eg., greater than 40 ppm boron difference) request that operations in el io. r.,
the pressurizer spray to equalize the parameters.
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4 PRoCEotf2E No.
REvtsloN PAGE No 1].-
VEGP 35110-C 10 7 of 44 3.10 The prer.surizer gas space is normally vented to the VCT through the steam space sample line.
Th'r. relieves the "hard bubble" ther enuse.: RCS pressure contrel problems.
Refer to Procedure 35515-C, " Operation of The Nuclear Sampling System - Liquid" for additional instructions.
1 4.0 PROCEDURE 4.l CHEMISTRY OBJECTIVES 4.1.1 Montrer the integrity of the fuel cledding.
4.1.2 Minimize crud production ar.d activation th(tchy reducing the radiation exposure te personnel.
4.1.3 Maintain adequate controin through monitoring, 4
cnalysis, and chemical coaditioning to allcw continued operation within the limits totablished by technien!
specifientions and this procedure.
4.1.4 Monitoring of the chemical shim to assist epurationn or the reactivity control.
j 4.2 GENEP.AL FYSTEM DESCRIPTION The reneter coolant system (RCS) consists of four similvr heet transier Iceps connected in parallel to the reactor pressurn vessel.
Each loop contains a reactor ceolant punp, steam generator, and associated piping and valves.
In addition, the system includes 9 pressurizer, pressurizer relief and safety volves, interconnectirg piping, and instrumentation necessary for operational control.
All of the abcve componenen I
are located in the containment building.
i During operation, the RCS transfers the heat generated i
in the core to the nteam generators, where steam is produced to drive the turbine-gener. iter.
doraten demineralized water is circulated in the RCS at r.
i flowrate and temperature consistent with achieving t he reactor core thermal-hydraulic performance.
The water also acts as a neutron moderatec and reflectu-ar.d r.r a solvent for the neutron absorher used in chemicel shim control.
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ocEDuiI/ No tiEvisioN PAGE No l
VEGP 35110-C 10 8 of 44 The RCS pressure is controlled by the use of tbc pressurizer where water and steam are maintained at saturation conditions by electrical heaters and water sprays.
Steam can be formed (by the heaters) or condensed (by the pressurizer spray) to minimize l
pressure variations due to contraction and cypansion of the reactor coolant.
Spring-loaded safety valves snd power-operated relief valves connected to the pressurizer provide for steam discharge from the RCS.
Discharged steam is piped to the pressurizer relief tank (pressurizer relief discharge system), where the steam is condensed and cooled by mixing with water.
l Material of construction for the major components of the RCS are stainless steel and Irconel.
4.3 ACTION LEVELS Three action levels have been defined in accordance with EPRI Primarf Water Chemistry Guidelines for taking remedial action when monitored parameters are observed and confirmed to be outside normal operating values.
Normal operating values are consistent with long term system reliability.
Action Level 1 is implemented whenever an out of normal operating value is detected and confirmed.
Action Level 2 is implemented when abnormal conditions indicate significant damage could be done to the system in the short term, thereb, warrarting a prompt correction of these conditions.
Action Level ? is implemented when conditions indicate that it is inadvisable to continut operation of the plant.
I. 3.1' Action Lev ('
1 If a parameter exceeds the Action Level 1 value return the parameter to within the Action Level 1 value within
)
7 days or go to Action Level 2 ff the parameter has an Action Level 2 value.
l 4.3.2 Action Level 2 If a parameter exceeds the Action Level 2 value, return the parameter to within the Action Level 2 value within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the parameter has not been restored to within the Action Level 2 value within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, ar.
orderly unit shutdown should be initiated and the plant should be brought to a cold shutdown condition as quickly as permitted by other plant constraintr..
If chemistry is improved to within the requirements of Action Level 2 prior to plant shutdown, full power i
operation may be resumed.
l 6hNb U
7 s
' ' PROCEDURE No.
REVistoN PAGE No VECP 35110-C 10 9 of 44 4.3.3 Action Level 3 If a parameter exceeds the Action level 3 value, an orderly unit shutdown should be initiated immediately, with reduction of coolant temperature : e less that.
250*F as rapidly as other plant constraints perrit.
4'. 4 SAMPLE LOCATIONS Samples of the RCS are obtained viu the Primary Sampic Panel grab sample points.
Refer to Procedure 35515-C.
" Operation Of The Nuclear Sampling System".
4.5 SAMPLE FREQUENCY 4.5.1 Routine samples are obtained e.t the frequencies specified in Procedure 30025-C, " Periodic Analysis j
Scheduling Program".
4.5.?
Non-routine camples are ebtained at frequencies contained in guidelines in this procedure.
4.5.3 Technical Specification 3/4.4.8 requires sampling for DEO-I 131 between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> following a thermal power change exceeding 15% of rated thermal power within a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> period.
When notified of this power change by Operations Department, log the notifications, perform RCS DEQ-I 131 analysis and log appropriate DEQ-I 131 analysis information of Data Sheet 5 attached.
Route to foremar for review.
4.5.4 Technical Specification 3/4.11.2 requires sampling of the RCS for DEQ-I 131 and monitoring of the noble gas plant vent monitor, (and under conditions of primary to secondary leakage, the condenser air ejector noble gas i
monitor.) for effluent activity following each startup.
shutdown and greater than 151 thermal power change within a one hour period.
When notified by Operations i
4 Depcrtment, log the notifications, perform required RCS DEQ-I 131 and log appropriate DEQ-I 131, plant vent noble gas monitor readings and condenser air ejector noble gas monitor readings (if applicable) on Dnta Sheet 5 attached.
NOTE Uce the ten minute average reading of one hour preceding the event as the pre-event value.
Use the ten minute average reading taken when sampling :he RCS for DEQ-Il31 for the post-event value. -Other n
ten minute averages may he used 4
F upon Lab Supervisio,n_ approval.
L MM
- 3E"VistoN PAGE No.
PROCEDURE No-10 of 44 VEGP 35110-L 10 4.5.5 To determine if the change in activity monitored by the gaseous monitors indicate a positive change abeve the statical deviation of the background (such as when PERMS monitor hourlv average is reading at or near zero rather than a significant positive number).
Perform the following calculation on Data Sheet 5.
( N Bcpm X 0.62) (Yuci/cc/ cpm) = Z uci/cc B = Current background subtract reading in cre Y = Current gain factor setting in uci/cc/ cpm Z = Level of activity which current reading murt be above in uci/cc 4.5.5.1 If the pre-reading is less char. the statistical deviation calculated in 4.5.5 above (Z), multiply the statistical deviation (Z) by 3 and compare to the post reading taken to determine if it is a factor of 3 greater.
4.5.5.2 If the pre-reading is above the statistical deviation calculated in 4.5.5 above, this actual reading is 1
multiplied by a factor of 3 then compared to the post reading value taken to determine if the post reading is a factor of 3 greater.
2 4.6 SAMPLE DATA RECORDING 4.6.1 Log all analysis results on the appropriate attached Data fheet in accordance with procedure 31045-C, "Chemiatry Logkeeping, Filing And Records Storage".
4.6.2 If the lithium concentration falls outside of the control bands of Figure 7, take actions, as indicated on the figure, to ensure that the lithium concentratfor.
is returned to the appropriate concentr.v::e.
~
4.6.3 Immediately notify the Laboratory Forer.an of any out v.
specification conditions.
Immediately notify the Operations Shift Supervisor of confirmed technical specification violations.
4.7 CHEMISTRY CRITERIA and System chemistry parameters, specifications, corrective actions are set forth in Table 1 through Table 10.
4.8 SYSTEM MONITORS In-line radiation monitor, CVCS Letdown Poritor -
RE-48000, is located downstream of the letdown heat exchanger providing indication of abnorms1 activity levels in the reactor coolant system.
I--.
D44',
'f
~~
)
PAGE No PROCEDURE No
)
4.9 DATA CORRELATIONS 4.9.1 Relation of pH And Conductivity Based on physical chemistry fundamentals, a relation exists between the pH and conductivity of a pure solution of an acid or base.
In particular, for a given pH, the conductivity must always be equal te or greater than the value indicated in Figure 2.
In situations where the reported data (pH/ conductivity) data place a point within the " impossible region", the evaluator can confidently state that one or both results are incorrect.
4.9.2 Relation of pH To Lithium And Boron Concentration In the absence of rignificant concentrations of impurities in the primary coolant, a well-defined relation exists between the pH and conductivity and the 4
lithium and baron concentrations.
The dependener. c.f pH on lithium and boron concentration at 25'C is shown in Figure 3 and Figure 4.
Similar infotmation for the conductivity and the lithium and boren relation is given in Figure 5 and Figure 6.
Such information can:
4 be used to verify the consistency of the data.
If pH or conductivity deviates from the indicated values in Figures 3, 4, 5 and 6, one of two conclusions car be 3
reached.
One of the measured aarameters is in error.
a.
Review of trend graphs for each parameter can sometimes give a. rapid indication of which parameter is in error.
b.
Presuming the analytical results are correct, an unidentified species is present in the primary coolant.
For example, a neutral salt (NaC1) will increase solution conductivity, but the pH will remain in agreement with the e'.<pected value.
A strong base (NaOH) or a weak base (NH,,0H) will increase the pH and conductivity comp 3 red to SO ) will expected values.
A strong acid (H2 4
increase conductivity and decrease the pH compared to expected values.
4.10 USEFUL INFORMATION AND FORMULAS 4.10.1 RCS Volume (Including Pressurizer)
Hot 61,346 gallons Cold 93,222 gallons m...
i 0
'~
L-AGE No PROCEDUME NO.
Revision VEGP 35110-C 10 12 of 44 NOTE The above volumes are equivalent gallons of water at STP.
4.10.2 Purification Flow Normal (gal / min) 75 Maximum (gal / min) 120 4.10.3 Formulas Purification Half-Life (T1/2) a.
0.693 l
Tgj3 =
V Q
Where:
Q = Letdown Rate V = System Volume b.
D,econtamination Factor (DF) i DF = Initial Activity Final Activity Infinite Dilution - assumes pure water for feed c.
~(Sh)
CF = Ci x e l
Where:
CF = Final concentration Ci = Initial concentration Q = Bleed & feed rute T = Time elapsed V = System volume d.
Volume of Bleed and Feed to Change Concentration
- Cj C
VF = VS in Where:
VF = Volume of feed VS = Volume of system CF = Concentration of feed Ci = Initial concentration Cf = Fine.1 concentration
PMocEDumE No.
REvlsioN PAGE No.
VEGP 35110-C 10 13 of 44 4
NOTE If concentration of the feed is zero, this formula will not work, use Infinite Dilution formula above, Theoretical RCS Hydrogen Concentrati_on e.
Assumes VCT temperature between 100"F and 150*F.
I Formula incorporates conversion from mole fraction to ec/kg and includes Henry's Law Coefficient.
RCS H (cc/kg) = (1.13) (P )
2 7
Where:
in the VCT in Partial pressure of H2 P
=
7 psia.
For example if VCT is operating at 30 psig and 801 H 8 2
(30 psig + 14.7 atmospheric) x P
=
7 (0.8) 35.76 psia H2 P
=
y f.
Lithium Removal, Calcula*. ions of Time to have CVCS Cation Bed in service t
= [V/Q in Co/Ci] / 60 V
= RCS volume (gallons).
Q
= Lerdown flowrate (gallons / minute)
C,= Initial Li conc. (PPM).
C! = Desired Li cone. (PPM).
time to place cation bed in service (hours).
t a
p.
Grams of Li-OH to Add.
LiADDITION = 0.023 ( A Li x VRCS)
Li
= desired increase in Li (PPM)
V
= RCS volume (gallons)
RCS Li
= grams of Li-OH to Add.
ADDITION I
PAGE No PROCEDURE No.
LEvtstoN VFCP 35110-C 10 14 of 44 4.11 CHEFICAL ADDITION 4.11.1 Chemical additions to the RCS c e made using the i
Chemical Mixing Tank 1(2)-1208-T6-005 located on le"r1 A Elevation 195 of the Auxiliary Building.
i Refer to Procedure 30006-C, " Laboratory Safety Manual",
4.11.2 when handling chemicals fcr addition.
4.11.3 Notify Operations when chemical additions are to be made.
4.11.4 Request that operations isolete the Chemical Mixing Tank 1(2)-1208-T6-005.
When the Mixing Tank has been isolated, open drain 4.11.5 valve 1(2)-1208-U4-180 and vent valve 1(2)-1208-U4-179.
Drain all water from the Chemical Mixing Tank.
4.11.6 Close drain valve 1(2)-1208-U4-180 and open fill valve 1(2)-1208-U4-178.
4.11.7 Slowly add chemicals through fill valve, 1(2)-1208-U4-178.
NOTE The volume of the Chemical 1"ixing Tank is 5 gallons.
Do not overfill.
4.11.8 Close fill valve 1(2)-1208-U4-178 and request that Operations vent the Chemical Mixing Tank.
Close the vent valve, 1(2)-1208-U4-179, and request 4.11.0 that Operations open the isolation valves to thr:
Chemical Mixing Tank 1(2)-1208-T6-005 to add th.
Chemicals to the RCS.
FIGH ACTIVITY IN THE REACTOR COOLANT SYSTEM 4.12 RCS activity limits are listed in Table 1 and Table 5.
4.12.1 4.12.2 Symptoms of high activity include:
4.12.2.1 Alarm on the CVCS Letdown Menitor (RE-48000) 4.12.2.2 Abnormal rtdiation levels at sampling stations, i
-..._. = - --_.
~~
PAGE No.
PROCEDURE No Revision l.
VEGP 35110-C 10 15 of 44 I
4.12.2.3 Abnormal increase in any routine radiochemical analysis (i.e., greater than 25% increase in isotopic activity between equilibrium conditions).
1 4.12.3 Actions Keep Operations informed of all activiticc ciid resul'_s 4.12.3.1 so that recuired Technical Specification actions car tr
- taken, i'
4.12.3.2 If the CVCS Letdown Monitor alarms, perform an isotopic anclysis on the RCS to determine the validity of the alarm and to assist in core damage assessment.
Draw sufficient ran.ples to prevent unnecessary edditional sampling.
4.12.3.3 If sample results are normal, check monitor operation, including local radiation levels.
If the first indication of high activity is discovered i
i 4.12.3.4 during routine analysis, determine the cause and inform Operations.
NOTE Confirmation of the cause for high RCS activity is made by laboratory analysis.
4.12.3.5 If a fuel defect is suspected, perform:
a.
Dose Equivalent Iodine b.
1-131/I-133 Ratio NOTE If the Iodine Ratio is aaproximately ten (10) times the normal ratio of 0.05-0.07, fuel defects are indicated.
4.12.3.6 If the Dose Equivalent Iodine is greater than 1.0 uCi/gm, perforn surveillances in accordance with Technical Specifications 3/4.4.8.
Refer to Step 3.1.2.
of this procedure.
4.12.3.7 If high activity is determined to be frou. crud, check the following to determine the magnitude and source or cause of the problem.
m
m-I PAGE No.
m" PRoCE, Dune No REVistoN VECP 3'110-C 10 16 of 44 VCT cover g.:c (type of gas and overpressure both correct?)
b.
RCS chemistry (i.e., dir. solved oxygen, chemical contaminants, lithium concentration, hydrogen concentratiot.).
i CVCS demineralizer exhaustion.
c.
d.
Recent chemical addition.
Review oacrating conditions, RCS pump starts, e.
trips, taermal transients.
4.12.3.8 Corrective Actions Plant action should be in accordance with the a.
Technical Specifications.
b.
Cleanup can be accomplished by f rere..a ir.g purification flow, changing the CVCS demineralizers, purging the VCT, and/or bleeding and feeding the RCS.
REFl:R_NCES
,E 5.0 5.1 Chemistry Criteria and Specifications - Westinghnuse Electric Corporation 5.2 FSAR 5.2.1 Chapter 5.0 5.2.2 Chapter 9.0, Section 9.3.4 5.3 PWR Primary Water Chemistry Guidelines - EPRI NP-4762-SR, Sept. 1986.
5.4 P&ID's 5.4.1 1X4DB111 Reactor Coolant System 5.4.2 lX4DB112 Reactor Coolant System.
5.4.3 IX4DB114 Chemical and Volume Control System Chemical and v lume Control System 5.4.4 IX4D114-118 o
PA;E No i
PROCEDURE No LEVIStoN VEGP 35110-C 10 17 of 44 5.5 PROCEDURES f
5.5.1 30025-C,
" Periodic Analysis Scheduling Program" 5.5.2 31045-C.
" Chemistry Logkeeping, Filin, Records Storage And Control And Imp ementation Of The Standing Order Book, Shift Turnover I.og, Required '.cading Book, And Laboratory Log Books" 5.5.3 34200-C,
" Operation And Celibration Of Liquid Proccan Munitors" 5.5.4 35515-C,
" Operation of The Nuclear Sampling System" END OF PROCEDURE TEXT i
i
)
)
I
i PROCEDUmE No EgV6sioN 18 of 44
'l eAaE NJ VEGP 35110-C 10 TABLE 1 SPECIFICATIONS FOR RCS SHUTDOWN /RHR (MODES 3, 4, 5 and 6)
TRANSIENT PARAMETER SPECIFICATIONS LIMIT CORRECTIVE ACTION Chloride 1 0.150 ppm i 1.50 ppm Increase letdawn Action Level 1 -
purification flow, ver'fy makeup water qualicy, check
> 0.15 ppm CVCS mixed Led outier quality, (ree Ster 3.1.1 for Tech Spee required action)
Fluoride 1 0.150 ppm
$1.50 ppm Increase letdowr.
Action Level 1 -
purification flow, verify makeup water quality, check
> 0.15 ppm CVCS mixed bed outlet quality, (see Step 3.1.1 for Tech Spec required action)
Dissolved 5 0.100 ppm 5 1.00 ppm If Tavg n 250*F add 1
Oxygen Tech Spec limits hydrazine to attain a when Tavs in 250*F concentration of 2 times Limits do not apply
- he dissolved oxygen if Tavg is 250*F concentration.
If Tavg
> 250*F see Step 3.1.1 for Tech Spec required action.
i I
Control of dissolv. oxygen must be achieved NOTE i
before the reactor coolant system temperature exceeds 180*F.
Before exceeding 180*F dissolved oxygen must be less than 2 ppm with l
excess hydrazine present in the coolant.
This.
condition is to be achieved with coolant in the RHR/RCS, all pressurizer spray lines open, ard a nitregen overpressure established in the Volume Control Tank.
If dissolved oxygen is r, renter than' j
0.1 ppm a hydrazine residual of at least twice the dissolved oxygen concentration must be present in the coolant before heatup heyond 180*F.
The CVCS inn exchange system should be valved out of service while hydrazine If no dissolved is being used for oxygen scavenging.
in the RCS, no Hydrazine addition is exypen is prenent necessary.
- 0 0. A
b PAGE No REVfStoN 19 sf 44 j
l EOcEDULE No 10 VEGP 35110-C l
f TABLE 1 (CONT'D.)
I
'RANS12NT CORRECTIVE ACTION
' PAFfMETEd SPECIFICATION 3 LIMIT i
l Boron
- Varies with plant condition j
and fuel burnup (Nominal 2000 ppm when system in refueling i
l Lovi add lithium-7 I
f Lithium During heatup hydruxide.
prior to exceeding l
lasI,i' 180*F. establish Hight use appropriate CVCS demin bed a lithium concentrayion (using Li OH) thac is coordinated witu the amount of Boron present.
(See Figure 7)
Gross Activity 5 100 g ucijg, l
(Reg'd in Modes 3,4) uci l
Isotopic '
i1
/gm and See Figure 1
.adine I
i i
l Isotopic iodine required 2-6 hours following a thermal 307:. ~
15% in 1 hr. period, (ie...
A trip to power change ofand if gross activity is out of specification.
Mode 3),
Isotopic lodines are required once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> in modes l
3, 4 and 5 until gross activity returns to within limit.u.
to perform Tech IfBoron5300$pmnotifyengineerinh09-C.
3 NOTE Spec Surv. 4.1.
.3B per procedure 54 i
i j
I t
PRocEc unE 0'o NEVisioN WAGEto W GP 35110-C 10 3 of 44 TABLE 2 GUIDELINES FOR RCS SHUTDOL'N :lHR (HODES ?,4,5 f.ND 6)
PARAMETER SPFCIFICATION CORRE" "VE ACTION Check Li, NH atJ Dirreleed 5
Vcriabic, see pH at Figure 3 or 4 Oxygen to deh,rmine cause.
i Add chemicris anc/ - use CVCS purification as neces:: cry.
Check Li, NH and Dissolved t
Conduc.1vity at
- Variable, Oxybentode2e,rminecause.
Adi 25'c t -hos/ cm censistent with additives presee.t.
chemicals and/cr use CVCS see Figure 5 cr 6.
purificarfon as necessary.
J Silica
$ 0.100 ppn.
Check CVCS mixed !af perfermance, che:1...L.
- ater, check boric acid stoa
,nks, use new CVCS mixed reed and biced.
Susper;ded 5 0.350 ppm Check VCT cover ga. for oxyger,
So '. id s Check RCS dissolved oxygen, Increase Letdown Aluminun i 0.080 ppm Check makeup water quality increase purification letdown flow, feed and bleed as required.
Calcium +
$ 0.080 ppm Check makeup water quality Magnesium increase purification lerdown flow, feed and bleed as required.
l' ague s i t;m 5 0.040 ppm Check makeup water quality increase purification letdown flow, feed and bleed as required.
Sulfare 5 0.100 ppm Check makeup water, quality increase purification lordiium flow, feed and bleed at required.
-.. e um 1,m
-M-Nm-
"~
i
~
PMoCEca?E NJ REVIStoN LAGE No
~
VEGP 35110-C 10-21'of 44
?
TABLE 3 4.
SPECIFICATIONS FOR TPE RCS DURI!fG 110RMAL POWER OPERATIOti TRANSIENT 4
SPr.CIF1 CATIONS LillIT CORRECTIVE ACTION PARAltETER d
Chloride 1 0.150 ppm 1 1.50 pom Increase letdown Acti n level 2 -
purification flow, Verify i
makeup water quality, Check
> 0.150 ppm CVCS mixed bed outlet i
Acrlon Level 3 -
quality (see Step 3.1.1 for
> 1.50 ppm Tech Spec required action) i fluoride 6 0.150 ppm 5 1.50 ppm Increase letdown Action level 2 -
purification flow, Verify makeup water quality, Chuck
> 0.150 ppm CVCS mixed bed outlet Action Level 3 -
quality (see Step 3.1.1 for i
> 1.50 ppm Tech Spec required action)
Dissolved 5 0.100 ppm
$ 1.00 ppm Check VCT gas space for i
Oxygen Action Leve* 2 -
hydrogen concentration,and
> 0.100 ppm overpressure.
(See Step Action Level 3 -
3.1.1 for Tech Spec required action) 4
> 1. 0 ppm Boron Varies with plant Controlled by Operations I
conditions Department l
determined by j
4 reactor power, iuel burnup Normal range 0-z000 ppm, at power < 1200 ppm Lithium Coordinated with With lithium oncentration at or above tne control as Li Euron, See Figure 7 value for Li/B coordinated 7
curve, use CVC9 demin bed to reduce Li concentration te lower control value.
Lithium concentration below control value for Li/B coordinated curve add
~
Lithium-7. hydroxide to upper control value.
NOTE If Boron $ 300 pmnotifycngineerinh09-C.to perform Tech I
Spec Sury. 4.1.
.3B per pence.'ure 54 e
44,t 4
l PAGE NO i
PROCEDURE NO L EVISION VECP 35110-C 10 2.'
of 44 TA07.E 3 (CONT'D.)
TRANS;ENT PARAMETER SPECIFICATIONS LIMIT CORRECTU!C ACT1tth Lissolved 25-35 cc(STP)/'
Check tha: VCT overpressure llydrogen Kgli,,0
> 15 psig.
Check byiugin Actt.on Level 1 -
concentration, increase or J
< '.' 5 decreove overprersure us
> 50 ce(STP)/
required: Low H
- increase, KgH.30 liigh H.3 decreas$,iPutgeif Action Level 2 -
concentration of E, is low.
i 1.15 cc(STP)/
KgM 0 9
Artfon Level 3 -
$ 5 cc(STP)/
\\
YgH,0 Dissolved 5 5 cc(STP)/
Incrccre 1crdovr, purge VCT 1
!!ydrogen KgN 0 with nitrogen. purge 9
prihr to opening pressurizer Steur.: Trree to the RCS VCT thru NFSG.
l i
1 j
o.
PAGE, No PMOctDUWE No REvrL.ub' 23 of 44 VEGP 35110-C 10 TABLE 4 CUIDELINES FOR THE RCS DURING NORMAL POWFR OPERATION PARAMETER SPECIFICATION CORRECTIVE ACTION pH at 25"C See Figure 3 Check Li concentration Check' Dissolved Oxygen concentration:
or 4 Add chemicals and/or use CVCS letdown purification as necessary.
Conductivity at See Figure 5 25'C umhos/cm or 6 Silica 1 0.100 ppm Check CVCS mixed bed performances check boric acid storage tanks.
Use new CVCS mixed bed or feed and biced.
Suspended
$ 0.200 ppm Check VCT cover gas for oxygen, Check RCS dissolved oxygen, Solids Increase Letdown Aluminum
$ 0.050 ppm Check makeup water quality, increase purification letdown flow, feed and bleed as required.
Calcium 4 5 0.050 ppm Check makeup water quality, increnne purificatien letdown Magnesium flow, feed and bleed as required.
Magnesium 10.025 ppm Check makeup water quality, increase purification. letdown flow, feed and bleed cs required.
l Sulfate 5 0.100 ppm Check makeup water quality, increase purification leidewn flow, feed and bleed as required.
%',44 %
~
-. - ~ -.
. ~.
....... ~... _
~
~
la AGE No PROCEDURE No REVistoN 24 of 44 VECP 35110-C 10 1
tau.; 5 i
RCS CPERAT!NG RADIOCllEMISTRY SPECIFICATIONS PARAMETER TECH SPEC LIMIT CORRECTIVE ACTION Doce equivcletit 5 1.0 microcurie See Step 3.1.2 for required
.ction lo ditie - 1.'1 per gram (DEQ I-131) 1 See Figure 1 Specific See Below See Step 3.1.?. for required action Activity (Performed as part.of. Gross Radioactivity Below) 1 1
-Gross.
i 100/E See Step 3.1.2 for required i
Radioactivity microcuries/ gram action 1
of gross radioactivity i
Specific activity analysis (gamma spectroscopy sampic ecunt) 1 iodine -131 anF gross normally encompasses both dose equivalent j.
activity analyses through the use of additional reports generated upon renuest of the gamma spectroscopy computer software.
4 l
4 4
l i
1 1
1 a
i i
1 vu.s
~
~~
~~
PAGE NO FMoCEDUME No REVISION 25 of 44 VECP 35110-C 10 TABLE 6 RCS OPFRATING RADIOCr!EMISTRY CU11)E1. !ET PARAMETFh VALUE Iodine Ratio 0.05-0.07 I-131/1-133 Nominni without fuel defects 0.5 - 0.7 Minin.a1 fuel defects RCS Crud Activity Monitor Monitor Tr! :.ium Hafnium - 181 Monitor (Nere 1)
Hafnium - 181 monitored as an indication of RCCA thinning Note 1:
87-19.
or cracking per NRC IE Information Notice No.
f 1 I s
2 4
NO
1 PJGCti MOCEDU,1 NO LEVl560N VEGP 35110-C 10 26 of 44 i
l TABLE 7 1
TRESSURIZER LIQUID CHEMISTRY r
\\
PARAMETER SPECIFICATION CORRECTIVE ACTION l
Chloride Same as for If a significant Flucrfde the RCS difference between the Pressurizer nr.F Boron RCS (eg. greater than 40 ppm be.ron) increare pressurizer spray te equali::e the RCS and Pressurizer, then follow the correctfec actions required per Tabic 3 end 4 i
l
)
i 1
I
^
nun
P90CEDUAE NO REVISION FAGE NO VEGP 35110-0 10 "I of 44 TABLE 8 PRESSURIZER VAPOR SPACE CllD!ISTRY GUIDELINES NORMAL PRIOR TO OPERATING OPENING PARAMETEP.
SPECIFIC.ATION SYSTEM CORRECTIVE ACTION Hydrogen 2 982
$ 41 Purge to VCT 1
0xyger
< 0.1%
< 0.1%
Purge to VCT 1
Nitroge-
< 22
> 952 Purge to VCT 1
1 Verify RCS dissolved hydrogen and dissolved oxyger,are in specification.
Verify with operators that correct type anc' pressure of cover gaa ir being supplied en the VCT.
i i
I
e
/
~
PMOCEDUmE NO E EVISION e AGE NO
/
VEGP 35110-C 10 28 of 44 TABLE 9 VCT VAPOR SPACE CllEMISTRY GUIDELINES PARAMETER SPECIFICATIONS CORRECTIVE ACTION llydrogen Same as for Increase / Decrease Hydrogen /
Oxygen Pressurizer Vapor Nitrogen pressure as apprcpriate Nitregen Space and purge to Gaseous Waste Management System i
\\
l t g 4*
i
PAGE No
~
PROCEDumE NO.
LEVM ON-VECP 35110-C-10
?c c,f 44 4
TABLE 10 i
CVCS DEMINERALIZER CUIDELINES J
i i
j PARAMETER SPECIFICATIONS CORRECTIVE, ACTION If detectable on effluent Chloride DF Nonitor imediately notify 4
1-Laboratory Supervsion i
Gross Activity DF Monitor I f Low (IE < ? ), verify no chemical contaminante. in effluent, have Laboratory Supervision evaluate for possible replacement.
Log DF results as sell an date resin loaded, date placed inte r.crvice and date resin discharged in the remarks section of the RCS Logcheet, updetc information on the Laboratory Resin Bed Status Board.
i i
i
-,e
4' j
)
POGE NO i
PROCEDURE NO.
REtflSION l.
VEGP 35110-C 10
?0 of 44 i
l j
ane 1
1 l-i h
t l
W i
l I
8 l
i I
S S
e W
G W
G S
W
- ' M 6F E M M M l
I
\\
Fi ure 1 I-131 Reactor Coo ant Specific Activity Limit Versus Percent of Rated Thermal Power with the Reactor Coolant Specific Dose Equivalent l
l 1.0 uCi/ gram Dose Equivalent.I-131 l
Activity l
l
-. - -. -.. -... ~ - ~
,.t-I aevision PAGE NO.
emocsougno g
7
///
=
l
. (\\
t l
//
7\\
//' /
g ff/ /
I,., 'l/
P^
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1 Page No Hemsson Procedure No 10 33 of 44 VEGP 35110-C LIWeel MIB2. gen eone 4.00 e.!39 0 50 e.75 t.00 t.25 8.Se t.75 2.e4 2 25 2 5e i
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ne, S'On Page No VEGP 35110-C 10 40 of 44 DATA SHEET 2 PAG 7. 1 0F I MONTH RCS SHl'TD0kN/RHR (HODES 3. 4, 5 AND f.)
YEAR UNIT T.S.
T.S.
T.S.
T.S.
T.54 1 150 $ 150 fl00
$1000 $80 $80 540 <0.35 (2)
(2) < 100 < 20 ( 3)
LIMITS VAR. VAR.
ppb ppb ppb VAR. VAR.
ppb ppb ppb ppb ppe ppb ppb (4)
Ca t1)
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FORMN.
) ATE TIME. P" COND Cl~
F-0 Li BORON S10 Al Hg Hg SOLIDS Activity 1-131'50 INIT. INIT.
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(1) LIMIT DOES NOT APPLY IF RCS T AVG. IS LESS THA!! OR EQUAL TO 250* F.
(2) Gross Act'vity req'd in modes 364, DEQ I-131 Req'd in mode 3, ? to 6 hrs following a trip; once per 4 hrs in modes 3, 4 & 5 when DEQ I-131 1 uct/gm or Gross Acttvity exceeds 100/E.
(3) A total organic carbon analysis should be performed anytime the fuel transfer canal has been flooded with the reactor vessel head off. 1he to her.( up above 180*F.
Laboratory analysis is to be performed prior supervision is to be notified if result is above limits.
(4) If Boron $ 300 ppe, notify engineering to perform Tech Spec. Surv.
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PAGE No PHOcEDUME NO LEVIStoN 43 of 44 VEGP 35110-C 10 DATA SHEET 5 POWER CHANCE EVENT NOTIFICATION RESPONSE A)
TYPE OF EVENT Startup Shutdown ISI Power Change /Hr Time /Date Notified (Central)
Time /Date Of Event (Central)
Notified By (Print Name)
B)
Pre-event Value,
uci/cc Date/Tfee (Central)
Post-event Val'ue uci/cc Dare/ Time (Central)
Pre-event / Post-event Ratio 53
>3 (chock one)
C)
P' ANT VENT (Caseous Monitor Reading) 12 Pre-evenc Value uci/cc Date/ Time (Central) uct/cc
(\\__ cpm X 0.62) Igain factor in uci/cc/ cpm) 12 Post-event Value uci/cc Date/ Time (Central) uei/cc (l__cpmX0.62) (gain factor in uci/cc/ cpm)
=
12 Pre-event / Post-event Ratio n3
>3 (check. one).
D)
CONDENSER AIR EJECTOR EXHAUST (Gr.reous Monitor Reading)
(Required when secondary water is contaminated by primary water).
2 Pre-event Value uci/cc Date/ Time (Central) uci/cc 2({__cpmX0.62) (gain factor in uci/cc/ cpm)
=
Post-event Value uci/cc Date/ Time (Central) uci/cc 2(\\__cpmX0.62) (gain factor in uci/cc/ cpm)
=
Pre-event / Post-event Ratio
$3
>3 (check one) 1 12444-C values may be used if 12442-C is out-of-service, same monitor must be used for both readings.
)
2 Use ten minute averages (ensure background not being run during period used)
PERFORMED BY:
DATE/I1ME (Central)
REVIEWED BY:
DATL/11ME (Gentral)
I muss
f.,*iihouneNo.
Lavision
, act No.
VEGP 35110-C 10 44 of 44
,l DATA SHEET 6 CALCULATION FOR LITHIUM ADDITION tTNIT,
A)
DESIRED INCREASE IN LITHIlfM CONCENTRATION (PPM) 1.
Present lithium concentration L
ppm
=
p 2.
Desired lithium concentration Ld" ppm AL=1 p,- Ld"I
} ~I
)
l B)
RCS VOLUME (GALLONS)
VOLUME HOT VRCS = 61,346 gallons or VOLUME COLD VRCS = 93,222 gallons C)
GRAMS OF Li-OH TO ADD Li
= 0.023 ( A L
- VRCs)
ADDITION Li
= 0.023 (
)
j ADDTTTON Li
= Crams of Li-OH to add ADDITION L
= Desired increase in Ifthium concentration (ppm) as calculated in Section A V
= Volume f RCS as datermined in Section B RCS Technician :
/
/
Date Tire Independent Verification:
/
/
Date Time Foreman:
/
/
Date Time I
7014 4
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,,,,,,,n, 9
o
"*1 of 26
/8 M 8 VOID CONDUCT OF OPERATIONS 1.0 PURPOSE This procedure establishes the responsibilities of erations Department personnel and provides inistrative instructions for daily conduct of plant a
operations.
2.0 ORGANIZATION AND RESPONSIBILITIES Figure 1 gives a basic organization chart for the Operations Department.
Specific responsibilities, duties and reporting relationships are as follows.
2.1 MANAGER OPERATIONS The Manager Operations is responsible for the overall mana ement of the Operations Department to ensure safe and fficient operation of Plant Vogtle.
Specific duties and reporting relationships are described in Plant Administrative Procedure 00001-C, " Plant Organization And Managerial Staff Responsibilities".
2.2 DEPUTY MANAGER OPERATIONS The Deputy Manager Operations reports to the Manager 0>erations.
He acts for the Manager Operations in his assence, and retains ~ signature authority for Manager Operations at all times.
He assists with management for safe and efficient plant operations.
- g 2.3 OPERATIONS SUPERINTENDENT (SHIFT OPERATIONS)
The Operations Superintendent (Shift Operations)
)
reports to the Hanager erations/ Deputy Manager Operations.
He has the allowing duties and responsibilities:
l l
a.
Directs the safe and efficient plant operation, b.
Ensures plant operations are conducted in accordance with the Technical Specifications and approved procedures,
~0Lolik'O & & Nff l
mocaouas ao.
navision Paoa wo.
f).
VECF 10000-C 9.
2 of 26 1
I c.
Conducts routine adstinistration and scheduling of operations shift activities, and coordinates these activities with the other plant departments, when f
necessary, d.
Serves on the Plant Review Board when designated, Performs appropriate reviews of the equipment e.
clearanca logs to ensure coun11ance with Plant Administrative Procedura 003)4-C, " Equipment Clearance And Tagging",
f.
Provides operations input to the plant Work Planning Group, I
Provides operations input to outage work g.
schedules, h.
Hay function as Manager Operations when specifically designated.
h 2.4 ON-SHIFT OPERATIONS SUPERVISOR The On-Shift Operations Supervisor (OSOS) reports to the Operations Superintendent (Shift Operations).
The OSOS is the senior operations representative on each shift and is responsible for the safe and efficient operation of the plant. He has the following duties and responsibilities.
a.
Functions as senior management representative for plant operations on shift,
)
b.
Has authority and responsibility to declare emergencies in accordance with the VECP Emergency Plan.
Also, the 0505 functions as site Emergency Director until relieved by a higher ranking
- manager, c.
Ensures that plant operations are conducted in accordance with the Technical Specifications and approved procedures, d.
Reviews operations narrative logs and round sheets in accordance with 10001-C "Logkeeping",
e.
Ensures shift relief is conducted in accordance with 10004-C, " Shift Relief",
f.
Ensures standing orders and night orders are carried out,
)
l.
_ _ _ _ ~
oceouna wo.
nevneow men wo.
] *.L VEGP 10000-C 9
3 of 26 Ensures that the shift is properly manned, the
)
g.
Fire Team constituted and team captain designated in accordance with 10003-C, " Manning The Shift",
j
]
h.
Ensures appropriate notifications of reportable occurrences are performed, 1
i.
Maintains a broad pers pactive of operational conditions affecting the safety of the plant as a j
natter of highest priority at all times j.-
Does not become involved in any single operation that distracts him when multiple operations are 1
required in the Control Room.
During plant l
transients or an emergency he should not become totally involved in any single operation that j
distracts him from the rest of the operations required in the Control Room, 4
i k.
Ensures that shift activities are conducted in a manner that keeps personnel radiation exposures 4
as low as reasonable achievable, I
l 1.
Ensures temporary procedure changes are properly administered on shift in accordance with j
00052, " Temporary Changes To Procedures",
f Tours plant areas on a routine basis, noting j
m.
condition of the plant and equipment, and i
monitoring rounds performance.
l 2.5 SHIFT SUPERVISOR One Unit Shift Supervisor (USS) is assigned to each operating unit on each shift.
He is responsible for i
the safe and efficient operations of the assigned unit.
r l
The USS(s) reports to the 0505 and has the following j
specific duties and responsibilities:
o a.
Ensures that unit operations are conducted in j
accordance with Technical Specifications and i
approved procedures, f
b.
Directs reactor to be shut down when:
(1)
Safety of the reactor is in jeopardy, or i
j (2)
Operating parameters exceed any of the reactor protection system trip setpoints and automatic reactor trip does not occur, or I
(3)
Personnel or equipment safety require it, or (4)
Unusual circumstances warrant it.
j b'
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_--~.. _. _
PAGE NO.
E07F* JE NO.
HEVISION 4 of 26
?
VEGP 10000-C 9
Directs operational activities of the assigned
)
c.
unit from the Control Room unless relieved by a qualified licensed SRO, d.
Authorizes maintenance and/or testing activities f
to be performed on the assigned unit, and ensures plant conditions are suitable for performing such activities.
Maintains status of equipment, and datermines operability of equipment upon return to l
service.
Issues equipment clearances and ensures proper e.
control of tags in accordance with Plant Administrative 00304-C, " Equipment Clearance And Tagging",
j f.
Ensures proper control of temporary.',umpers, lifted wires, and pulled annunciato cards in accordance with 00306-C, " Tem Jumper And Lifted Wire Control", pot.ary end 10018-C,
" Annunciator Status Control",
L i
Explains plans, procedures, and safety precautions g.
to shift operating personnel prior to infrequent or unusual activities, i
h.
Ensures shift relief is conducted in accordance with 10004-C. " Shift Relief",
1.
Maintains the Shift Supervisor narrative log and administers logkeeping in accordance with l
10001-C, "Logkeeping i
j.
Supervises operators assigned to specific shift j
positions on the unit, l
k.
Maintains operating work spaces in a clean and orderly condition, and ensures good housekeeping l
practices by operators assigned to the unit, l
i 1.
Conducts periodic safety meetings for operators 4
on-shift, enforces safe practices, ensures appropriate protective equipment is used, prepares l
accident reports, and obtains medical attention, when needed, Limits access to the Control Room in accordance m.
with Procedure 00301-C
" Main Control Room Access 1
And Personnel Conduct".
Tours plant areas on a routine basis, noting n.
condition of the plant and equipment, and monitoring rounds performance.
j 4
.s 4
v
4-PAGE No.
PeoCE. JaE NO.
REVISION 5 of 26 VEGP 10000-C 9
2.6 SUPPORT SHIFT SUPERVISOR The Support Shift Supervisor (SSS) reports to the OSOS.
He provides technical and administrative assistance to Specific duties and responsibilities include the USS.
but are not lOmited to Coordinates clearance and. tagging review for the a.
- USS, Coordinates control of keys required for plant b.
operation er Procedure 00008-C, " Plant Lock And Key Contro Performs maintenance work order and deficiency c.
card reviews for the USS, or I
Supervises shift operators common to the plant, d.
who are not assigned a specific shift position.
l Assists the OSOS in implementing work scheduled per the Plan-of-the-Day, and provides input to the e.
POD work process, May serve as Fire Team Leader if designated by the f.
4
- OSOS, Tours plant aress on a routine basis, noting g.
condition of the plant and equipment and monitoring rounds performance.
2.7 REACTOR OPERATOR The Reactor Operator (RO) reports to the USS.
He is che licensed operator assigned to operate the reactor Specific i
and related controls from the Control Room.
duties and responsibilities include:
Maintains the unit in a safe condition, including s.
shutting down the reactor when:
(1)
Safety of the reactor is in jeopardy, (2)
Operating parameters exceed any of the reactor protection circuit set points and automatic shutdown does not occur, (3)
Required to protect personnel and equipment, or Unusual circumstances warrant it.
s (4)
B f
M4 $ gg4 l
E
. PHOCEDURE No REVIStoN PAGE No.
VEGP 10000.,
9 6 of 26 3'
b.
Initiates 0mmediate actions necessary to maintain tha unit in a safe condition during abnormal and emergency operations, Performs shift operations and surveillance testing c.
in accordance with approved procedures, standing orders, and the Technical Specifications, d.
Exercises continuous surveillance of unit Remains in the conditions and sy' stem parameters.
"at the controls area unless r
eri relieved.
"At the controls" is defined 003 C, " Manning The Shift",
Instructs the Balance of Plant Operator and the e.
plant equipment operators to perform prescribed plant operations, f.
Manipulates the controls and equipment to start up, operate, and shut down the unit as required by operating schedules and load demand, Maintains the Unit ~ Control Log and completes round g.
sheets for his position.
Maintains recorder charts for his work station, h.
Promptly notifies the USS of unusual conditions, i.
Remains alert and knowledgeable of all unit operations in progress that involve the functioning of equipment controlled from the Main Control Room, J.
Functions as a team member during initiation of the Site Emergency Plan, k.
Coordinates startup and shutdown operations of the nuclear reactor, turbine generator and auxiliary equipment, 1.
Responds to the system operator requests at the direction of the USS.
i t
m
i PMcCEoWRE No.
REyessoM ~
PAGE No.
7 of 26 VEGP 10000-C 9
2.8 BALANCE OF PLANT OPERATOR The Balance of Plant Operator (BOP) is a second licensed operator assigned to each unit.
He reports to the USS. He normally operates balance of plant equipment and controls.
Specific duties and responsibilities include:
Maintains the unit. in a safe condition, including a.
shutting down the reactor when:
(1)
Safety of the reactor is in jeopardy, (2)
Operating parameters exceed any of the reactor protection circuit set points and automatic shutdown does not occur,
)
(3)
Required to protect personnel and equipment, or (4)
Unusual circumstances warrant it, b.
Initiates the innsediate actions necessary to maintain the unit in a safe condition during abnormal or emergency operations, Performs shift operations and surveillance testing c.
in accordance with approved procedures, standing orders, and Technical Specifications, d.
Exercises continuous surveillance of unit j
conditions and system parameters, Receives instruction from the Reactor Operator, s.
f.
Completes check lists for his position, maintains recorder charts for his work station, and assists the Reactor Operator in maintaining the Unit' 4
Control Log, g.
Promptly notifies the USS of unusual conditions.
h.
Remains alert to and knowledgeable of all unit operations in progress that involve the functioning of equipment under his control, l
i.
Functions as a team member during initiation of the Site Emergency Plan, l
j.
Maintains the Control Room in a clean and orderly condition, l
PROCEDURE NO.
REVIS4ON PAGE NO.
VEGP 10000-C 9
8 of 26
~
k.
Directs activities of Plant Equipment Operators as
- required, 1.
Relieves the RO when authorized by the USS, Normally remains in the Control Room unless m.
performing necessary duties elsewhere in the plant.
2.9 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor (STA) provides engineering expertise during operational emergencies to assess plant status and assist in implementing E0Ps.
An STA is not required on shift if the OSOS or a USS holds a bachelors degree in engineering or a related science.
The SSS may also be designated to perform the STA function, if qualified.
If an STA is assigned on shift, he or she will report to the OSOS.
2.10 PLANT EQUIPMENT OPERATORS There will normally be four Plant Equipment Operators (PEO) on shift for each unit: A Turbine Building Operator (TO), an Auxiliary Building Operator (AO), an Outside Area Operator (OAO) and a Control Building Operator (CBO).
The PEOs report to the USS, but may also receive direction from the RO or BOP.
Specific duties and responsibilities includes Performs rounds to ensure proper operation of a.
equipment in assigned work area, b.
Executes routine shift duties as directed by the
- USS, Removes equipment from service and execute c.
clearance orders restore equi'> ment to service and remove clearances as directed my the USS, d.
Maintains clean and orderly work area, r
Acts as Fire Team member when designated by the e.
OSOS.
,n
~~ "
' AoE No.
e PROCEDURE NO AgygstoN 9 of 26 VEGP 10000-C 9
2.11 RADWASTE OPERATOR E
'Ihe Radvaste Operator reports functionally to the USS and administrative 1y to a Radwaste Foreman.
Specific duties and responsibilities include:
Operates Radwaste Systems in accordance with a.
approved procedures and Standing Orders, b.
Maintains round sheets and logs for his position, Executes routine shift duties as directed by the c.
I Radvaste Foreman or USS, t
d.
Maintains clean and orderly work area, I
Acts as Fire Team member when designated by the s.
OSOS.
2.12 OPERATIONS SUFFRINTENDENT (SUPPORT)
The Operations Superintendant (Sup ort) reports to the l
Hansger Operatiens/ Deputy Manager erations.
He has the following duties and responsibi ities:
Supervises the preparation and review of plant a.
operating procedures, b.
Provides input to the Training Department for i
development and conduct of training and
[
qualification of Operations Department personnel, 1
Develops and maintains personnel records such as l
c.
shift schedules, vacation schedules, and seniority i
- lists, d.
Serves on the Plant Review Board when designated, i
l May function as Manager Operations when e.
specifically designated.
l A
4
l lE l'I Ih I ~PROCEDumE NO.
REVISION 10 of 26 l
VEGP 10000-C 9
2.13 OPERATIONS SUPERVISOR (ENGINEERING)
The Operations Supervisor (Engineering) reports to the and has the Operations Superintendent (Su> port) following duties and responsi')111 ties:
Coordinates Operational Experience Assessment a.
Program activities pertaining to plant operation (with Nuclear Safety and Compliance Section),
b.
Maintains Emergency Operating Procedures and Abnormal Operating Procedures current and
- accurate, Reviews plant design changes to ensure timely c.
revisions to operating procedures when necessary, d.
Provides technical and administrative support to the Operations Superintendents, Supervises administration of the Operations e.
Required Reading Book per Procedure 10017-C,
" Operations Reading Books",
f.
Serves on the Plant Review Board when designated.
OPERATIONS SUPERVISOR (TRAINING C00RDINiTOR) 2.14 Oserations Supervisor (Training Coordinator) reports to tie operations Superintendent (Support) and has the following duties and responsibilities:
Assures that each applicant has the knowledge and a.
skills to competently perform the assigned
- position, b.
Monitors on-the-job-training (0JT) performance and Operations Department training needs, Primarily and routinely interfaces with the c.
Training Department, d.
Maintains Training Qualification Checklist and OJT documents, Obtains and distributes training material, s.
f.
Attends training course IN-001, " Instructor Development Program" within one year of being l
appointed to the position, Establishes and maintains a list of approved 3
Operations Department OJT Trainers / Evaluators, h.
Serves on the Operations Training Committee.
l
FAuc to P640CEDURE NO REvlslON of 26
{
VEGP 10000-C 9
1 2.15 SHIFT SUPERVISOR (TRAINING COORDINATOR)
The Shift Supervisor (Training Coordinator) reports to the Operations Supervisor (Training Coordinator) and has the following duties:
Coordinates and schedules evaluations and a.
- training, b.
Performs evaluations and training, E
Attends training course IN-001, " Instructor c.
Development Program" within one year of being appointed to the position, d.
Identifies area of candidate's deficiencies and provides feedback to Training and operations management.
2.16 OPERATIONS SUPERINTENDENT (WASTE MANAGEMENT)
The Operations Superintendent (Weste Management) reports to the Manager Operations / Deputy Manager Operations.
He has the following duties and responsibilities:
Plans and directs processing of liquid, solid, and a.
gaserwis radioactive waste processing, and coordinai.as these activities with other plant departments as necessary, b.
Ensures radweste operations are conducted in accordance with state and federal regulations, and approved procedures, Tracks and trends water usage in the plant, and c.
coordinates water management activities plant wide to ensure efficient and safe operations, d.
Serves on the Plant Review Board when designated.
J
. 1 IlM IMEM
PAGE NO.
PAOCEDURE NO REYWON VEGP 10000-C 9
12 of 26 1
9 2.17 RADWASTE SUPERVISOR The Radwaste Supervisor reports to the Operations Superintendent (Waste Management).
He has the following duties and responsibilities:
Supervises Operations Department liquid a.
radioactive vastes processing, and coordinates these activities with other plant departments as necessary, b.
Conducts routine administration and scheduling of i
radwaste personnel, Advises the Training Department on requirements c.
for developing and conducting training of radwaste personnel, d.
Ensures liquid radwaste operations are conducted in accordance with state and federal regulations, j
and approved procedures.
2.18 RADWASTE FOREMAN The Radwaste Foreman reports to the Radwaste Supervisor.
He has the following duties and responsibilities:
Directs the activities of the Radvaste Operators, a.
b.
Coordinates and schedules radwaste activities, c.
Reviews Radwaste Operator logs.
d.
Initiates corrective actions for out-of-limit conditions and notifies the Radwaste Supervisor and the USS, e.
Coordinates and schedules Chemistry, Health Physics and Maintenance support, f.
Conducts the Radwaste Operator Qualification Program.
l i
e Atl44%
notno
.....wwn u.v us v,g,ou 13 of 26 VEGP 10000-C 9
4 2.19 RADWASTE LABORATORY SUPERVISOR The 'Aadwaste Laboratory Supervisor reports to the He has 0)ertations Superintendent (Wasta Management).
th following duties:
Supervises solid radwaste processing and a.
coordinates this activity with other departments, Ensures solid radwaste processing operations are b.
conducted in accordance with federal and state regulations and approved procedures, Maintains the Process Control Program and burial c.
and shipping contracts.
2.20 OPERATIONS SUPERINTENDENT (STARTUP)
The Operations' Superintendent (Startup) reports to the He has Manager Operations / Deputy Manager Operations.
f the following duties and responsibilities:
Directs operations activities to support a.
construction and preoperational testing of Unit 2, Plans for safe and efficient transition of Unit 2 4
b.
from the preoperational to commercial operations
- status, l
Serves on the Test Review Board when designated.
c.
3.0 SHIFT OPERATIONS 3.1 SHIFT COMPLEMENT The OSOS thall ensure that the operating shift is j
l l
groperly manned, in accordance with Procedure 10003-C, Manning The Shift".
f.
3.2 SHIFT WORK HOURS 3.2.1 Shift Hours The shif ts will be conducted on a 24-hour clock system.
using Central Standard Time (or Central Daylight Savings Time).
Specific shift schedules will be posted by the Operations Superintendent (Shift Operations).
3.2.2 overtime l
Overtime should not be routinely scheduled to meet the shift crew staffing requirements.
In the event that overtime must be used, the overtime restrictions of l.'
Procedure 00005-C, " Overtime Authorization", will be l
l followed.
4'WM l
i
i PROCEDURE NO.
REVISION PAGE No.
VEGP 10000-C 9
14 of 26 1
3.2.3 Notification of Absences Anyone expecting to be late or unable to report for shift duty at the scheduled time shall, at the earliest possible time, inform the OSOS or USS.
3.2.4 Call out Authority The OSOS is authorized to call out anyone required for the safe plant operation, per Plant. Administrative Procedure 00006-C, " Recall Of Off Duty Personnel".
3.3 GENERAL WORK PRACTICES All personnel assigned to shift operations shall:
Be aware that the primary responsibility of the a.
operating shift is to assure the safe operation of the plant under all conditions, b.
Protect plant personnel, the health and safety of the public and plant equipment,
. Conduct major plant operations in accordance with c.
approved written procedures, f
d.
Be attentive to the condition of the plant at all times.
They must be alert to ensure that the plant is operating safely and take action to
)
prevent any progress toward a condition that might be unsafe, e.
Believe and respond to instrument indications l
until they are proven to be incorrect, f.
Not bypass, reset bypasses, defeat safety systems or interlocks or remove Category 1, 2, or 3 instrument channels from service, unless allowed to do so by an approved procedure.
vue.
o Pnocaount No.
newsson Paos no.
VEGP 10000-C 9
15 of 26 y
3.3.1 Shift Conduct t
3.3.1.1 Each member of the shift crew shall perform in a professional manner.
Potentially distracting activities shall not be conducted in the Control Room Activities prohibited include loitering, area.
listening to music, hobbies,. non job-related reading h
material, and horseplay. The full focus of the shift complement's attention shall be the safe and efficient operation of the plant.
l 3.3.1.2 Operations personnel on shift must be aware of and responsible for the plant status at all times.
This includes supervisors being responsible for the performance of personnel assigned to their shift who could affect plant safety.
3.3.1.3 All Operations personnel on shift must be alert and remain within their work areas until properly relieved.
erators are responsible for monitoring the (vinstrumentation and controls located within their work They are responsible for taking timely and areas.
proper actions to ensure safe operation of the j
facility.
3.3.1.4 Controls that directly affect the reactivity or power level of a reactor shall only be manipulated by licensed operators, except for training purposes.
3.3.1.5 Mechanisms and apparatus, other than controls, that may indirectly affect the power level or reactivity of a reactor shall only be operated with the knowledge and prior consent of a licensed operator.
3.3.2 Abnormal Indications I
The 0505, USS, and RO, and BOP have the authority and responsibility to perform the tasks necessary to limit plant operations or to shutdown the unit when such action is warranted by unit conditions, unusual circumstances, or unidentified events.
When analyzing i
auch situations, shift operating personnel shall consider instrument readings and control indications to be true unless they are proven to be incorrect.
When abnormal indications occur, operations personnel shall determine the cause of the abnormal indication and initiate appropriate corrective action.
9 l
1 mu.s
.7.
I
~
PAGE No.
t*ROCED:";E No LEVI &loN 16 of 26 VEGP 10000-C 9
3.3.3 Instrument Setpoints
)
Shift operating personnel shall not manipulate instrument control or alarm setpoints, other than those i
available on the control console or those normally Setpoint changes required during routine operation.
shall be entered in the Unit Control Log or the Shift Supervisor's Log.
Anyone performing a function that may affect a unit's operation or a Control Room indication shall notify the l
control Room operators before initiating the function.
l 3.3.4 Control Room Access Control Room access shall be limited to official business only in accordance with Plant Administrative Procedure 00301-C, " Main Control Room Access And i
Personnel Conduct".
3.3.5 Generator Load Changes Normally generator load changes will be made as If approved by the requested by the System Operator. conditions and gerational OSOS, and if plant operatin erator will comply with orders permit, the Reactor the request.
The RO shall form the USS when the requested load change is completed.
Whenever plant conditions require a load change, the System Operator shall be notified as soon as possible of.the proposed load and rate of change.
Scheduled outage requests shall be initiated by the Operations Manager and approved by the General Manager and System Operator prior to scheduled plant shutdown.
3.3.6 Control Room Housekeeping The Control Room will be maintained in a clean and orderly condition in the interest of safe and efficient Dusting and cleaning of control consoles, operations.
instrument panels, and computer consoles will be performed by shift operating personnel.
i i
l j
Z ' /
-Q,y e
PAGE NO.
. 'PROCEDuhEic
- IyessoN 17 ef 26
+
VED 20000-C 9
3.4 NOTIFICATION REQUIREMENTS The OSOS is responsible for the notification of the NRC, plant management and staff in special situations.
Notifications required during day shift. Monday thru Friday, should be to the Manager Operations.
Requirements occurring at other times should be first 4
to the Duty Officer, who may direct the OSOS to call a l
department superintendent or the General Manager.
j f
3.4.1 Notification Of Duty Officer
'1he 0505 shall notify the Manager Operations or Duty officer if the following occur:
j Reportable Occurrences requiring NRC red phone a.
notification per Plant Administrative Procedure 00152-C, " Federal And State Reporting i
l Requirements",
l b.
Conditions that require the use of Abnormal I
Operating Procedures, i
Unscheduled entry into an LCO action statement c.
j with less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> restoration time, d.
Unannounced inspections by regulatory agencies.
such as the NRC (other than resident inspector),
s OSHA, State 7nspectors, etc, j
l e.
Equipment "silures that could necessitate a derate.
f.
A major failure resulting in structural damage to company property, f
g.
Any serious personnel injury, h.
Any call for offsite assistance, j
i.
A fire with activation of the plant fire team, J.
Serious environmental problems, such as toxic chemical, oil, or hazardous waste spills, k.
Any "neer miss" events that could have resulted in reactor trip or safety injection, 1.
Technical assistance or management direction is 1
l needed for issues of reportability, operability,l technical specification compliance, or procedura adequacy.
I WWN*WWW -MT.Y&M i
PAGE No.
PROCEDURE NO-4.EVIStoN VEGP 10s. -C 9
.i.8 of 26 3.4.2 NRC lunediate Nocification Events 3
The OSOS is responsible for notifientien of the NEC Operations Center for prompt reportable occurrences in i
accordance with Plant Administrative Procedure 00152-C,
" Federal And State Reporting Requirements".
3.5 SHIFT RELIEF AND EVOLUTION BRIEFINGS l
3.5.1 Each shif t relief shall be conducted in an orderly, i
professional manner in accordance with Procedure 10004-C, " Shift Relief".
The OSOS may add to these minimum requirements as he sees fit 3.5.2 Briefings shall be conducted for individuals involved in complex or unusual evolutions.
The detail of the briefing is dependent on the degree of complexity, d.
routineness, logistics, or number of people involve 3.5.3 The individual who is to perform an activity is res onsible to adequately review its rocedure, to ful y understand what he.is doing, an to be cognizant of all the limitations and precautions and requirements.
3.5.4 Evolutions involving many individuals, especially from two or more departments or disciplines, may require large formal briefings or pre-planning sessions.
If the evolution is complex and involves close coordination, the briefing session should include:
A review of the appropriate sections of the a.
procedure by key parties, b.
An examination of each individual's specific involvement and responsibility, A discussion of expected results or performance, j
c.
d.
A review of limitations, hold points, A review of emergency action to be taken in s.
contingencies, f.
Checks to ensure that everyone understands the interface and communications required, Identification of individual in charge of the g.
t evolution.
l It 4
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i PAGE No.
~hCEDURE No.
REVISkoN 19 of 26 P9s VEGP 10000-C 9
3.6 SHIFT RECORDS Shift records include logs, round sheets, check lists, recorder charts, compucer prin'. sues and other data generated during operations.
3.6.1 Logs Operations narrative logs, round sheets, recorder charts and computer printouts shall be kept in accordance with the provisions of 10001-C, "Logkeeping".
3.6.2 Hight Orders and Standing Orders Night Orders and Standing" orders are issuad in accordance with 10002-C, Plant Operating Orders".
3.6.3 Reactor Trip Review The OSOS shall initiate review of reactor trip,s in accordance with 10006-C, " Reactor Trip Review.
3.7 KEY CONTROL Keys required for plant op'eration are controlled in accordance with 00008-C, Planc Lock And Key Control".
3.8 RADIO 1DGICAL CONTROLS 3.8.1 Each person on the plant staff is responsible to use proper radiological practices and procedures.
Everyone must be continuously aware of the radiological aspects of the work he is involved in and take appropriate actions to minimize exposure and to control the generation and spread of radioactive contamination.
3.8.2 Refer to 43007-C, " Issuance, Use And Control Of Radiation Work Permit", for control of work in radiation and high radittion areas.
3.9 SAFETY CLEARANCE AND TAGGING Clearance and tagging for personnel and e pipment safety is conducted in accordance with 00304-C.
" Equipment Clearance And Taggit g".
4
% g4.%
J
~
Pass wo.
)
pnocsouns wo.
ncvacu
,i VEGP 10000-C 9
20 ef 26 i
i
~i 3.10 EQUIPMENT RETURN TO SERVICE 1
Following maintenance on or modification to a systam or l
component, Operations shall verify the operable Verification condition of that system or component.
l may be by functionally testing or by surveillance j
testing.
If the component or system is not covered by a surveillance procedure and a special functional test is not performed, a return to service functional inspection should be performed.
The inspection should
{
address items such as the following:
a.
Mechanical coupling,
~
Blind flanges installed / removed, i
b.
i c.
Electrical connections,
~
J d.
Area cleanliness, e.
Valve alignment, ji 1
f.
Proper lubrication, I
g.
System integrity.
h.
Function of remotely operated valves.
(
/e 3.11 TECHNICAL SPECIFICATION INTERPRETATIONS 3.11.1 Technical Specification interpretations may be made using Figure 3 as follows:
I a.
Immediate Need The requestor will contact one of the below listed t
l l
individuals:
(1)
On-Shift Operations Supervisor, (2)
Manager Operations, (3)
Operations Superintendent (Shift Operations).
I (4)
Deputy Manager Operations.
l The interpretation vill be given verbally, followed up by the interpreter with a written request form.
e 5
Mt'X20URE No.
KEVISloM PAGE NO.
VEGP 10000-C 9
21 ef 26 b.
Normal Need The requestor fills in the first two portions of the request form and forwards it to the M nager t
a 1
i Operations.
Af ter interpretation is made and approved by Operations Management, copies are distributed end the original is placed in the Technical Specification Interpretation Book.
This l
book will be maintained in the Control Room area.
4, 4.0 PLANT OPERATINC PROCEDURES
- i 4.1 PROCEDURE COMPLIANC5 4.1.1 Operating personnel will follow approved plant procedures as directed by 00054-C, " Rules For i
Performing Procedures".
l 4.1.2 In emergencies, Operations personnel are directed to take such action as is necessary to minimize personnel injury and damage to the plants to return the plant to a stable, safe conditions and to protect the health and safety of the general public and personnel on site.
4 i
4.1.3 In emergencies, personnel may take reasonable action that departs from a license condition or a Technical 3pecification when this action is immediately needed to l
protect the public health and safety and no action i
consistent with license conditions and Technical l
Specifications that can provide adequate or equivclent l
protection is immedately apparent.
4.1.4 Personnel action permitted by Paragraph 4.1.3 shall be approved, as a minimum, by a licensed Senior Operator Li prior to taking the action.
i 4.2 PROCEDURE IMPLEMENTATION l
4.2.1 Procedures for other than simple, frequently-performed i
operations shall be followed step-by-step with the procedure present.
Many procedures will require l
signoffs.
Routine procedural actions that are j
frequently performed may not necessitate the presence of a procedure.
If the operator is not completely familiar with the procedural action to be performed, the procedure must be present.
Immediate operator actions of emergency procedures shall be committed to memory.
4.2.2 Independent Verifications required by procedures which do not have signoff spaces shall be documented using Il879-C. " Independent Verification Documentation Log i-Sheet".
mon
..o..
v j."
enocaDungNo KEvtsloN 22 of 26 VEGP 10000-C 9
1 If an evolution is suspended for an extended period of 4.2.3 time, reverification of the initial conditions is required.
4.3 SYSTEM LINEUPS AND SYSTEM STATUS FILE System lineups establish and confirm the status of The current lineup for each equipment and systems.
The file j
system is maintained in a system status file.
contains the mosc recent complete lineup and those 2
partial lineups performed subsequently which collectively reflect the current status of the entire system.
l 4.3.1 Complete system lineups are performed as directed in unit operating procedures.
Partial lineups are performed on portions of systems inside clearance boundaries, after clearances are released, when directed by the Shift Supervisor.
Partial lineups are also performed on portions of systems affected by procedure revisions when directed by the Operations j
(Shift Operations).
Comalete or partial Superintendent lineups may be performed when directed 'sy the USS.
1 j
Lineups should be performed in sequence identified in 4.3.2 Lineup procedure unless otherwise directed by the USS.
The operator shall compare the position of the j
4.3.3 component with the position required on the alignment.
and initial in the spaces provided.
Unless instructed l
otherwise, he shall reposition any component found nc*
co be as required.
Control valve position is serifi6.
l i
power or air, as appropriate, is by ensuring that available to the valve operator and that no physical obstructions that could prevent operation are apparent.
j All components left in other than the condition 4.3.4 rap ired shall be noted on the comments section of each alis ment procedure and the reason for the exception I
shall be entered.
4.3.5 Independent position verification shall be performed in i
accordance with 00308-C
" Independent Verification Policy" and Sub-nubsection 4.2.2.
t t
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Nb
m-PAGE No.
P#oCEDURE No.
REVIStoN 23 of 26 9
VEGP 10000-C The USS or SSS shall review the completed system lineup 4.3.6 for completeness and to ensure exceptions do not The original lineup warrant further corrective action.
is placed in the system status file.
Superceded j
Care must lineups are forwarded to Document Control.
be taken when removing lineups from the file to ensure that the file reflects the current status of the j
systems (e.g., partial lineups can supercede only partial lineups partial lineups cn the same componentscan only supercede com i
they constitute a complete lineup.)
4.4 SURVEILLANCE TESTING 4.4.1 Operations Surveillance Tests f
The Operations D2partment shall perform, document and 4.4.1.1 review operations surveillance tests.
4.4.1.2 The approval of th2 USS shall be obtained before starting each surecillance test.
The operator performing the ten: shall record information as procedure and initial each step as required by the :est it is completed.
He shall sign and date the procedure If a step is not upon completion rf the test.
completed the exp'anation shall be recorded on the procedure.
If a rest does not meet the specified acceptance criteria, the USS shall be notified and corrective actica initiated.
The OSCS or USS rhn11 review all operations 4.4.1.3 surveillance tests performad on his shift for completeness and cecuracy. He shall indicate his review by signing and dt. ting the procedure in the appropriate space.
" Surveillance Test Tracking Program" 4.4.1.4 Refer to 00404-C, for method of t-
- ing Tech. Spec. surveillance tests during normal ec-trinns.
4.4.2 Special Conditie tr Off-Normal Surva 11.ance Requirements 14915-1, "Special Condition The USS shall e-
"e Surveillanca Le "' is or has been initiated as required to comply with Technical Specifications in conditional or off-normal sit";tions.
14000-1 " Operations Shift & Daily 4.4.3 The USS shall err ~re' surveillances are started within 2 Surveillance to hours of shift t"rncver and worked to completion, provided circums* nces warrant.
PAGE NO
)
PHut LDUH6 NO REVISION VEGP 10000-C 9
24 of 7<-
5.0 REFERENCES
5.1 FSAR - Chapter 13 5.2 VEGP Technical Specifications 5.3 PROCEDURES 5.3.1 10001-C.
"Logkeeping" 5.3.2 10002-C,
" Plant Operating Orders" 5.3.3 10003-C,
" Manning The Shift" 5.3.4 10004-C,
" Shift Relief" 5.3.5 10006-C,
" Reactor Trip Review" 5.3.6 11879-C,
" Independent Verification Documentation Log Sheet 5.3.7 14915-1, "Special Conditions Surveillance Logs" 5.3.8 00001-C,
" Plant Organization And Managerial Staff Responsibilities And Authority" 5.3.9 00004-C.
" Plant Crmuunications" 5.3.10 00005-C,
" Overtime Authorization" 5.3.11 00006-C,
" Recall Of Off Duty Personnel" 5.3.12 00008-C,
" Plant Lock And Key Control" 5.3.13 00054-C,
" Rules For Performing Procedures" 5.3.14 00152-C,
" Federal And State Reporting Requirements" 5.3.15 00304-C.
" Equipment Clearance And Tagging" 5.3.16 00308-C,
" Independent Verification Policy" 5.3.17 00404-C,
" Surveillance Test Program" 5.3.18 43007-C, "In:.uance, Use And Control Of Radiation Work Permits" 5.3.19 91102-C, "Dui 's of The Emergency Director".
END OF PROCEDURE TEXT l
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PAGE NO EOCEDung NU REvtSION VEGP 10000-C 9
26 of 26 3,
PLANT VOGTLE UNITS 1 & 2 TECH SPEC INTERPRETATION TECH SPEC i:
QUESTION OR AREA NEEDING CLARIFICATION:
0 INTERPRETATION:
h V
Approved By:
Date Manager Operations xc:
Manager Operations 1
Nuclear Safety & Compliance Manager ort Superintendent Engineering Supp& Emergency Prepardness Manager Plant Training Plant Manager Required Reading Book I.'
1 FIGURE 2 nws
,