ML20127G737
| ML20127G737 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 04/03/1973 |
| From: | Skovholt D US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Dienhart A NORTHERN STATES POWER CO. |
| References | |
| NUDOCS 9211170416 | |
| Download: ML20127G737 (34) | |
Text
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APR 3 1973 JO Doexet ;lo. 50-263
.torthern States Power Company J.TT;!: ;;r. Arthur V. Licuhart Vice President of Engineerinr, i
414 alcollet ;iall
- _inneapolis. ;'.innesota 55401' Change ;;o. 5 Provisional Operating-Centlemen
- .icense I;o. :Pn-22 Your letter...ateu 4:ovember.:0, 1;72, auomitted proposou channes to the Technical Specifications of Provisional Operating License rio. DPR-22 for the 2:onticello iiuclear Generating Plcut Unit 1.
T.ie request for cnanges involve proposou revisions to the isdministrative Controls section (G.C' of tne Technical Specifications, ano other areas af fected by these changes.
.,uring our review of the proposea changes, we informed your staff that certain t2ocifications to the Technical Specifications were necessary to r.ee t ra;,ulatory requirenento.
These nodifications have been race.
On tno basis of our review of your proposea changes, aa rocified, ue have conclucou that the proposed enanges do not present airnificant na::ards consicorations not described or implicit in the i:onticello Jafety Analysis T.eport and that there la reasonable assurance that the health ano sarety of the public will not.be encangered by operation of the Monticello Nuclear Generating Plant in the proposed manner.
Accordin:;1y, pursuant to Section 50.59 of 10 CPR Part 50, the Technical Specifications of Proviolonal Operating Licence Co. LPR-22 aro hereby l
changed as act forth in Attachment A to this letter.
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Sincerely, Med agese le
- . 4. C<>+-r*
uonald J.=3kovholt Assistant Director for. Operating P.cactors -
Oirectorate of Licensina Enclosure and cc: See next:page i
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RP R ading File e
Branch Reading file J RBuc hanan TWLaughlin
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.iorthern States Power Company ' '
,JJ S kovhol t RLTedesco ACRS (16)
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Attorney. OGC Gerald Charnoff DLZiemann Shaw, Pittsan, Potts, Trowbridge u Hadden TJCarter 910 - 17ta Street,. -....J.
NDube Wasnington, D. C.
20006 21Jinks (4)
RM Di ggs Howard J. Vogel JSears Anittle & Vogel JJShea o14 Flour 2xchan:;c du1161n:;
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?aul, !!1nnesota 55103 darriott Lansing, Zaquire
- .asistant City Attorney City of St. Paul 636 City dall 5t. Paul,
- linnesota 5510:'
Zen Dzut;an dinnesota Pollution Control Agency 717 Lelaware Street. 2. '.
'.:inneapoli.;..lanesota 33440 avironuental Protection Agency 1222 S.E. 4th Street dnneapolis, ;*lnnesota 55414 cc w/ enclosure and copy of riSP's ltr. dtd. 11/20/72:
.Jarren n. Lawson,... b.
Jecretary 6 Executivo Officer Stato Department of Health 717 Delaware Street, S. E.
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ATTACIDIENT A l
CHALICE NO. 6 TO TECIINICAI, SPECIFICATIONS J
PROVISIONAL OPERATING LICENSE NO. DPR-22 4
f NORTHERN STATES POWER COMPM4Y DOCKET No. 50-263 1
n 1.
In Section 1.0, Definitions, replace page I with the attached pages 1 and 1.A.
s 2.
On page ul, in Sectica 3.3.E., change ".
. Specifications 6.6" to read ".
. Specification 6.7.B.1."
l J.
On page 90:
a.
Change Specification 3.4.3.1 to replace the coma at the j
enu of the secono line with a period and delete the word l
2 "or" on line 3, and b.
Delete Specificativa 3.4.D.2 in its entirety, i
4.
On pages 108 and 113, celete Spec 1fication 3...: and its basis i
in their entirety.
5.
On ene followin:; pages and Specifications, delete the words "either 3.5.H shall be complied with or":
a.
98 - (3.5. A.5) b.
101 - (3.5.B.6)
S.
On the following pages and Specifications, delete the words "either the requirements of 3.5.11 shall be complied with or":
a.
102 - (3.5.C.5) b.
107 - (3.5.F.3) 7.
On the following pages and Specifications, delete the words "either 3.5.11 shall be complied with or procedures for":
a.
104 - (3.5.D.4) b.
105-106l- (3.5.E.4) l t
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On page 131, 4th paragraph, Dases 3.6 and 4.6, change ".
Specification b.6.E.3.d." to read ".
. Specification 6.7.C.4."
9.
On page 136, 2nd paragraph, Bases 3.b anc 4.6, change "..
Specification 6.6.E.3." to read ".
. Specification 6.7.C.3."
10.
i.eplace Specification 6.0 Administrative Controls consisting of pages 192 through 211 with the attached revised Section 6.0 consisting of pages 192 throu:;h 218.
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On page 131,- 4th paragraph, Bases 3.6 and' 4.6. change "...
Specification 6.6.E.3.d." to read "... Specification 6.7.C.4."
9.
- On page 136;. 2nd paragraph, Bases 3.6 and 4.6, change ".
l Specificarf d 6.6.E.3." to read "... Specification 6.7.C.3."
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.., place Specification 6.0 Administrative Controls consisting or pages 192 throur,h 211 with the attached' revised Section 6.0 consisting of pagea 192 through 218.
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INTRODUCTION These Technical Specifications are prepar'd in eccordance with the requirements of 10 CFR 50.36 and apply to the Monticello Nuc1 car Generating Plant, Unit No. 1.
The bases for these Specifications are included for information and understandability purposes.
1.0 DEFINITIONS The succeeding frequently used terms are explicitly defined so that a uniform interpretation of the Specifications may be achieved.
A.
Abnormal Occurrence 3
1.
A safety system setting less conservative than the limiting setting established in the Technical Specifications.
2.
Violation of a limiting condition for operation established in the Technical Specifications.
3.
An uncontrolled or unplanned release of radioactive material from the site.
4.
Failure of one or more components of an engineered safety feature or plant protection system that causes or threatens to cause the feature or system to be inhap'ble of performing its a
intended function.
5.
Abnormal degradation of one of the several boundaries designed to contain the radioactive materials resulting from the fission process.
6.
An uncontrolled or unanticipated change in reactivity greater than 1% delta k/k.
7.
An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or threatens to cause the existence or development of an unsafe condition in connection with the operation of the plant.
8.
Conditions arising from a natural or man-made event that affects or threatens to affect the safe operation of the plant.
1.0-1 1
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B.
Alteration of the Reactor Core The act of moving any component in the region above the core support plate, below the upper grid and within the shroud.
(Normal operating functions such as control rod movemant.noing the normal drive mechanism, tip scana, SRM and IRM detector movements, etc., axe not to be considered core alterations.)
C.
Hot Standby Hot Standby means operation with the reactor critical in the startup mode at a power Icvel just sufficient to maintain reactor pressure and camperature.
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1.0-1A 1A
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6.0 ADMINISTRATIVE C0frrROIE 6.1 crganization A.
he Plant I-hnager has the overall full-time onsite responsibility for safe operation of l
the facility.
During periods when the Plant 1hnager is unavailable, he may delegate this responsibility to other qualified supervisory personnel.
B.
he Northern States Power corporate orgenizational structure relating to the operation of this plant is shown in Figure 6.1.1.
. C.
%e minimum functional organization for operation of the plant chall be as shown in Figure 6.1.2.
The minimum shift, complement for cpecial plant condit. inns shall be as follows.
1.
The unit shutdown and the reactor contains fuel: a Licensed Senior Operator on si-:e:
a Licensed Operator in the control room; and a plant operator on sfic.
2.
During cold startup, while shutting down the reactor and during recovery from any reactor trip:
a Licensed Senior Operator in the plant and a utuimum of two Licensed Operators in the control room.
3.
Fuel handling operations:
a Licensed Senior Operator shall be directly in charge of any refueling operation, alteration of the reactor core, and handling of irradiated fuel. and shall have no other concurrent duties.
4.
Any fuel on site:
an individual qualified in radiation protection shall be on site at all l
times that there is fuel on site.
D.
Minimum qualifications, training, replacement training and retmining of plant personnel shall be in accordance with that stated in the 'Standani for Selection and Training of Personnel for Nuclear Power Plants ANSI U18.1 - 1971.
he minimum frequency of the re-training program shall be every two years. The tmining program shall be under the.di-rection of a designated member of the plant staff.
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6.1 192
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PRESIDENT j
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GROUP VICE PRESIDDrt-POWER SUPPLY i
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o VICE PRESIDENT-VICE PRESIDENT-DIRECTOR OF l
POWER PRODUCTION &
NUCLEAR SUPPORT-ENGINEERING SYSTEM OPEPaTION SERV, ICES 6
i SAC Administration 1
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l MANAGER OF
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POWER PRODUCTION I
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SAFETY AUDIT i
COMMITTEE (SAC) 4 l
GENERAL SUPERINTENDENT l
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I OPERATION l.-
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PLANT MANAGER'.
Audit & Review.]
i MONTICELLO i
wI FIGURE 6.1.1 NSP CORPORATE ORGANIZATIONAL:
RELATIONSHIP TO ON-SITE OPERATING ORGANIZATION i
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s PLANT
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ItANAGER*
OPERATIONS C0fSilTTEE I
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SUPERINTENDENT-SUPERI!3TENDENT-OPERATION &
PIANT ENGINEERING S MAI!TTENANCE*
RADIATIOli PROTECTI0tP I,SO QUALITY ENGINEER
- I I
MAINTENANCE OPERATIOllS RADIATION PIANT ENGINEER-PLANT ENGINEER-SUPERVISOR
- SUPERVISOR
- l LSO PROTECTION TECIINICAL
- OPERATIONS
- ENGINEER
- SilIFr LSO SUPERVISOR
]/S
!!ECHANICAL LEAD PIANT 1/S TECIINICAL ENGINEERS FOR TECilNICAL SUPPORT AND EQUIP!!EllT &
SUPPORT &
NUCLEAR ENGINEER-FOR OPERATION, EIECTRICAL REACTOR OPERATOR 1.0 TECIINICIANS ING, INSTRUMENTATION, ifAINTE14ANCE, SUR, MAI!TTENANCE FOR RADIATION C0tfIROLS & COMPUTER; VEILIANCE, TESTING GROUP PIANT EQUIPMENT 1/S PR0rrECTION &
AND INSTRUMENT MEN AND REIRAINING
& REACTOR CHEMISTRY OPERATOR In ASSISTA!TE PIAtTr I/S EQUIIYtEfff OPERATOR PIANT ATTENDAlfr 1/S M0!TFICELLO NUCLEAR CENERATING PIA!TT CODE:
- Eey Supervisor Functional Organization For 1/S
- one/ shift On-Site Operating Group RO
- Licensed Operator SRO
- Licensed Senior Operator FIGURE 6.1.2 19b
w 6.2 Feview and Audit l
Organizational uaits for the review and audit of facility operations shall be constituted and have the responsibiltties and authorities outlined below:
/., Safety Au ht Committee (SAC)
The SAC must: verify that operation of the plant is consistent with company policy and rules, approvtJ operating procedures and operating license provisions
- review importent proposed plant f.hanges, tests and procedures; verify that unusual events are promptly investigated and corree ;cd in a mnner which reduces the probability of recurrence of such events; and detect trends which may not be apparent to a day-to-day observer.
Audits of selected aspects of plant operation shall be performed with a frequency commensurate with their safety significance and in such a manner as to assure that an audit of all nuclear safety related activities is completed within a period of two years.
Periodic review of the audit programs sbuld be performed by the SAC at least twice a year to nosure that such nudits nre being accomplished in accordance with requirements of Technical Specifications. The nu-dits shall be ucrfomed in accordance with approprintc written instructions or procedures and shall include verification of compliance with internal rules, procedures (for example: normal,
'off-nomal, emergency, operating, maintenance, surveillance, test and radiath n control pro-cedures and the emergency and security plans), regulations involving nuclear safety and opera-ting license provisions; training, qualification and performance of operating staff; and cor-i rective actions following abnormal occurrenm or unusual events.
A representative portion of procedures and records of the activities per:brmed during the audit period shall be audited and, in addition, obser ntions of perfomance vf operating and maintennnce activities shall be included.
Written reports of such audits shall be reviewed at a scheduled meeting of the SAC and by appropriate members of management including those having responsibility in the crea audited.
Follow-up action, including reaudit of deficient areas, shall be taken when indicated.
1.
M mbership The SAC shall consist of at least five (5) persons.
a.
6.2-195
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s b.
The SAC Chairuan shall be a !;CP ranngenent representative appointed by the Group Vice Presiden:,-Power Supply.
Other SAC c.enbers shall be oppointed by the Group Vice Presi-dent-Pow.
Supply or such othar persor. cs he may desi6nate.
'Ile Chairman shall appoint a Vice Ci.ninnan from the SAC membersh.p to act in his absence, No more than two members of the SAC shall be from groups holding line renponsibility c.
for operation of the plant.
d.
The SAC members should collectively have the capability required to review problems in the following areas:
nuclear power plant operations, nuclear engineering, chem-istry and radiochemistry, metallurgy, instrumentation and control, radiological safety, mechanical and electrical engineering, and other appropriate fields asso-ciated with the unique characteristics of the nuclear power plant involved.
A minimum of four voting members shall have a minimum of a Bachelors Degree in Engineering or a scientific discipline and possess a minimum of three years of professional level experience in nuclear services, nuclear plant operation, or nuclear engineering. When the nature of a particular problem dictates, special consultants will be utiliced, as necessary, to provide expert advice to the SAC.
2.
Meeting Frequency The SAC shall meet on call by the Chairman but not less frequently than twice a year.
3.
Quorum A quorum shall include a majority of the permanent rembers, including the Chairmaa or Vice Chairman. No more_ than a minority of the quorum shall be from groups holding line responsibility for the operation of the plant.
4.
. Responsibilities - The following subjects should be reported to and reviewed by the SAC:
Proposed tests and experiments, and their results, when such tests or experiments a.
may constitute an unreviewed safety question as defined in Section 50.39(c) Part 50, Title 10, Code of Federal Regulations.
b.
Evaluations of proposed changes to procedures, equipment and systees completed under pro-visions of Section 50.59(b), Part 50. Title 10. Code of Federal Regulations to verify that such proposed changes do not constitute unreviewed safety questions.
6.2 196
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i c.
Proposed changes 13. procedures, equipment or systems which may involve an unreviewed safety question as defined in Section 50.5969, Part 50, Title 10, Code of Federal Regulations or changes referred to it by the operat!ng organization.
d.
Proposed changes in Technical Specifications or operating license.
e.
Violations of applicable statutes, codes, regulations, orders, Technical Specifications, operating license requirements, or of internal procedures or instructions having safety significance, f.
Significant operating abnormalities or deviations from normal and expected performance i
of plant equipment.
3 g.
Abnornal occurrences as defined in these Technical Specifications.
h.
Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems or components.
1.
Operations Committee proceedings and minutes to determine if matters considered by that-Committee involve unreviewed or unresolved safety questions.
J.
Training, qualification and performance of operating staff.
k.
Disagreementibetween'the> recommendations of the Operations Committee and the Plant Manager.
1.
Security and emergency plans and their implementing procedures.
m.
Environmental Monitoring Program and its results.
n.
Quality Assurance program and evaluate its adequacy.
Review of events covered under 4.e-4.h above shall include reporting to appropriate members of management on the results of investigations and recommendations to prevent or: reduce the probability of recurrence.
5.
Authority The SAC shall be advisory to the Group Vice President-Power Supply.
6.2 197
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l 6.
Records t'
liinutes shall be prepared and retained for all scheduled meetings of the Safety Audit.
j.
Committee and shall identify all documentary material reviewed.
The' minutes shall be dis I
i tributed to to Group ' Vice President-Power Supply, the Cencral Superintendent of' Nuclear..
Power Plant Operation, each member of the SAC and others designated by the' Chairman or Vice-j President.within one month of the meeting.
There shall be a formal approval of-the minutes.
I
)
..7 Procedures
' A written charter for the SAC shall be prepared that contains:
a.
Subjects within the purview of the group b.
Desponsibility and authority of the group _ including.rcoponsibility to identify' i
j i
probletus and to recommend solutions to appropriate management c.
&chanisms for convening meetings d.
Provisions for any use of specialists and subgroups j
Authority to obtain access to the nuclear power plant operating reconl filen and l
e.
operating personnel to perfonn the audit functio-1 t
i f.
Requirements for distribution of reports and minutes prepared oy the group to others in the USP organization r
3 g.
Identification of the management posLtion to which the SAC reports h.
Provisions for assuring that the SAC is kept inforrued on a timely basis of matters within its purview
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.6.2
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OperationsCommittee(OCJ L
1.
Membership i
The Operations Committee shall consist of at Icast nix (6) members drawn from the key super--
vitors of the on-site supervisory staff. Tim Plant Manager shall serve as Chairman of the OC and shall appoint a Vice Chairman from t12 OC membership to act in his absence.
2.
Weting Frequency i
'Ibe Operations Committee will meet n en11 1 y the Chairman or as requected by individual members and at least inonthly.
3 Quorum A quorum shall include a majority of the permanent members, including the Chairman or Vice Chairman, 4.
Responsibilities - The following subjects shall be reviewed by the Operations-Committee:
a.
Proponed testa nnd experlmnts and their recults.
b.
Modifications to plant systems or equipmenr. as described in Final Safety Analysis Report and having nuclear safety significance or which involve an unre't;ewed safe *, question as defined in 10 CFR 50.59.
Proposals which wou.1d effect permanent changes to normal and < mer6ency operating c.
procedures and any other proposed changes or procedures that are determined by the Plant Fhnager to affect nuclear safety.
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d.
Proposed changes to the Technical Specificn* ions or operating license.
All reported or suspected violations of Technical Specifications, operating license e.
requirements, administrative procedures, operating procedures.
Pesults of investi-gations, including evaluation and recommenclations to prevent recurrence, will be reported, in writing, to the General Superintendent of Nuclear Power Plant Operation and to the Chairman of the Safety Audit Committee.
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6.2 lee
f.
Abnormal Occurrences and unusual events as defined in these Technical Specifications.
g.
Drills on emergency procedures (includin6 plant evacuation) and adequacy of corrauni-cation with off-site support groups..
-l h.
All procedurea required by thece Technical Gpecifications, including Impicmenting procedures of the Dner6ency Plan - and the Security PJan shall be reviewed with a.
frequency ccmmensurate with their safety signit'icance but at an interval of not,
.more than two years.
1.
Perfom special rt views and investigntions, as requested by the Safety Audit Com-mittee.
5 Authority The OC shall be advisory to the Plant !bnager.
In the event of disagreement between -
the recommendations of the OC and the Plant !hnager, the course detemined by the,
Plant Ihnager to bc t he more conservative will be followed. A wrLtten summary of the dicagreement will be sent to the Genern1' Superintendent of Nuclear' Power Plant Opern-tion and the Chairman of the GAC for review.
6.
Peco rds Hinutes shall be recorded for all meetings of the OC and shall identiff all documentary material reviewed.
The minutes shall be distributed to each member of the OC, the' Chairman and each member of the Safety Audit Committee, the General Superintendent of Nuclear Power Plant I
Operation and othera designated by OC Chairman or Vice Chairman.
i f.
Proemdares
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. A written charter for the OC shall be prepared that contains:
a.
Responsibility and nuthority of the group b.
Content and method of submission of presentations te the Operations Committee 6.2I.
200
e c.
Mechanism for schedtaling meetings
[
f d.
Ibeting ngenda f
e.
Une or cubeemmttleen f.
Pev teu and approval, by trember 3, of OC nettono g.
Distribution of minuten f
63 Actions to be 'Iwken in the event o'r An Abnort-etl OccurrenCCln_ P19nkOUVG t19D.
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' A.
Any abnonrnl occurrence as defined in these Te hn t en1 Specir!entions shall be report.ed to the General Cuperintendent of N.sclear Power Plent Ope:ntion, er hic decignated alternate in his abcer.cc, and chall be reviewed by t he Opet.stions Committee.
A cepinte, sequentinlly numbe red, leport shall be prepared for each abnormal occurrence.
1hch report shall describe the circumstances.ending up to and resulting fro:n the occurrence, the con rective action taken, an attempt t.o dert ne the enune of the o.'currence and nhall recommend appr opriate action to prevent, or reduce the probability of n repetition of the encurrence.
'lhe Opern-tions Committee ahn11 review the report and recommend further action, if necennary.
j Copico of all such reportn and Operationu Co:r.mittee recomr. undations chall be submitted to the Chairman of the Gn Ay Audit rorrmittee for 2 cview and to the General Gup rintendent of Nuclear Power Plant Opt.ation for review and approval of any recommendations.
All abnomal occurrencen shall be reported to the AEC an specified in Section 6.7.B.1.
6.4 Action to be Thken I T n Patrety Limit in Exceeded If a Safety T.imit is exceeded, the reactor shall be shut down immediately.
An Irmediate report shcIl be m'ade to the General Superintendent of Nuc1 car Power Plant Operation, or his designated
, alternate in his absence. and reported as specified for an abnormal occurrence in Section
- 6.7.B.I.
A complete analysis of the circumstances ]cading up to and resulting from the situation,
'together with recommendations by the Operations Committee, shall also be prepared, This report shall be submitted to the General Superintendent. of Nuclear Power Plant Operation and the Chairman of the Safety Audit Corarai t t ee.
Reactor operation shall not be resumed until authorized by the U. S. Atomic Energy -Cor$trsion.
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6.3 '
201
e 6.5 Plant Operating procedures Detailed written procedures, including the applicable check-off and instructions, covering listed below shall be prepared and followed.
These procedures and changes thereto, arean cxecist as specified in 6.5.D shall be reviewed by the Operation Committee and approved by a member of plant management designated by the Plant ifanager.
A.
Plant Operations 1.
Integrated and system procedures for normal startup, operation and chutdown of the reactor and all cystems and components involving nuclear cafety of the facility.
2 2.
Fuel handling operations,
3 Actions to be taken to correct opecific and ficceen p&ential or actual malfunction of systems or componenta including responces to alarms, primary syotem Icaks and abnormal reactivity changes and including f ollow-up actions required after plent protective cystem actions have in'tiated.
h.
Surveillance and testing rc<ptirements that could have an ef fect on nnelear safety.
5 Implenenting procedures of the security pinn.
6.
Implementing procedures of the emergency pinn, including procedures for copir6 with emergency conditions involving potential or actual releases of rndicactivity.
1 Drille on the procedures cpecified in A 3 above chall be conducted as a part of the retrain-ing program.
Dril% on the procedures specified in A.6 above shall be conducted at least
'I remiannually, iniuding a check of communications with offsite support groups.
Ihdiolchical B.
Ibdiation enntml procedurco shall be maintained nrul made availabic to all pInnt perconnel.
These procedures shall show permircible radiation expocure and shall be consistent with t.he requirements of 10 CFR 20.
'Ihis radiation protection pro 6 ram shall be organized to meet -
the requirements of 10 CFR 20.
t 6.5 202
1.
n.
Paragraph 20.kO3 "Cnution signs, Inbeln, cignals and controls." In lieu of the
" Control device" or nintm signal reipiimd by paragraph 20.203 (c) (2), each high radiation.nren in which the intensity of radiation is 1000 mBem/hr 'or lens chnll Le barricaded and conspicuoucly ponted as a high radiut, ion nrea and ent,rance thereto shall be controlled by requiring 1scuance of a Padiation Work Permit and any individual or group of individuals permitted to enttr such arens chall he provided with a radiation monitoring device whic? continuously indicates the radiation doce rate in the area.
b.
He above procedure chnll also apply to each high radiation area in which the intensity of mdintion is greater thun 1000 mrem /hr, except that. locked doors shall be provided to prevent unnuthorized entry into these areas and the keys to thece locked doors chall be mintnitied under the administrative control of the Plant Ihnager.
2.
Pursunut to 10 CFR 20.103 (c) (1) and (3), allowance enn be mde tor the n,c or ren-piratory protective equipment in conjunct, ion with activities authorizel 'hy the opera-tinglicence for this plant in determinin6 whether individuals in restricted areas.nre exposed to concentrations in axcess of the limits specified in Appendix D, Table I, Column 1 of 10 CFR 20, subject to the following conditions and limitations:
7.
'Ihe limits provided'in Section 20.103 (n) and (b) are not execeded.
a.
b.
If the radioactive material in of such form that intake throu6h the skin or other additional route is likely, individual exposures to radioactive material shall be controlled so that the radioactive content of any critical organ from all routes of intake averaged 'over 7 consecutive days does not exceed that which would yecult from inha)'ng such radioactiva material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> at the pertinent concentration values provided in Appendix B, Table I, Column 1 of 10 CFR 20.
For radioactive materials designated "Gub" in the " Isotope" column of Appendix D, c.
Table I, Column 1 of 10.CFR 20, the concentration value specified is based upon ex-posure to the material as an external radiation source.
Individual exposures to these materials shall be. accounted for as part of the limitation of L individual dose in 20.101.
'Ihese materials shall be subject to applicable process and other engi-neering controls.
~
65
.203
3 In all operations in which adequate limitation of the inhalation or radionctive mater-1al b. the use of process or ot her engineering controls is impracticable, the licensee s
may permit an individual in a restricted area to use respiratory protective equipment to limit the inhalation of airborne mdioactive material, provided:
a.
The limite specified in parngraph 2 of this section are not exceeded.
b.
Respiratory protective equipment is selected and used so that the peak concentra-tions of airborne radioactive material inhaled by an individual wearing the equip-ment does not exceed the pertinent concentration values specified in Appendix B, Table I, Column 1 of 10 CFR 20.
For the purposes of this subparagraph, the concentration of radioact ive material that is inhaled when-respirators are worn may be. determined by dividing the ambient airborne concentration by the protection factor specified in Table 6.5 1, appended to - this Specification, for the renpiratory 1
protective equipun:nt worn.
If the intake of radioactivity is later determined by other measurements to have been different than that initially estimated, the latter quantity siwdl be used in evaluating the exposures.
The licensee advises each respirator user that he may leave t'he area at any time.
c.
for relief from recpirator use in case of equipment malfunction, physical or psychological discomfort, or any other condition that might cause reduction in the protection afforded the wearer, d.
'1he licensee maintains a respiratory protective program adequate to assure that the requirements above are met and incorporates practices for respiratory pro -
tection consistent with those recommended by the American thtional Standanls Institute ( Af1SI-7.138.2-1969).
Such a program shall include:
(1) Air sampling and o.her surveys sufficient to identify the hazard, to evaluate individual exposures and to permit proper selection of res-pimtory protective equipment.
(2) Written procedures to assure pioper selection, supervision ~and training of personnel using such protective equipment.
G
~. -
(3) Written procedures to aseure the odequate fittirig of respirators and the testing of respirntory pmtective equipment for opernbility immedLately 1.
prior to noe.
~
(4) Written procedures for muintenance to assure f* ll effectiveness of respira-tory protective equipment,. including issunuce, cleaning and deconta..iination, inspection, repair and stomge, t
'l (5) Written cpemtional and administmtive proceduces f'or proper use of respira-tory protective equipment includin$ provisions for_ platined limitations on workin6 t traes as necessi+ated by cperational conditions.
(6) Dicasceys and/or whole body counts of indtviduals (and other surveys, as appropriate) to evaluate individual exposures and to assess protection netual3y pmrided, e.
The licencee uses equipe nt opproved by the U.S. Bureau of Mines under i.ts appropri-atc Approval Schedules as set forth in Table 6 5 1 below.
Equirment not approved under U.S. Bureau of flines Approval Senedules may be used onlf If the licensee has evaluated the equipspent and can demonst rate by testirg, or on the basis of reliable test inforr.s ton, that the material and perfomance characteristics of the equipment are at least equal to those af forded by U.S. Bureau of Mines approved equipment of the same type, as specifind in Table 6.5 1 below.
f.
Unless othmiise authorized by the Commission, the licensee does not assign protec-tion factots in excess of those specified in 'lbble 6.5 1 below in selecting and using respimtory pmtective equipment.
~
N. Iter; Specifications with respect to the provisions of 20.103 chrill be superseded by adoption of proposed changes to 10 CFR 20 Section 20.103, which would make this Speci-fication unnecessary, s
6.5 ~
205
TABLE 6.51 PICTECTIOli FACTORS FOR REPIllAT0fG F110fferIOff FACTURS y GU1DW 10 SELECfl0Il CF LRUIf;1EfIT i
PARTICULATE IiUREAU OF MIriES APPICVAL SCllEDULES*
DECRIPTION MODP AND VAPolG AfiD FOIL IMUIFt1EITl' CAPABLE OF Pit 0VIDIrr. AT GACW IGCEPP IFAST EQU1VALEIIT PROTECTION FACIORS TRITIUMOXIDF3!
- cr schedule superseding for equipment of tyle listed 4
I, KLR-PURITYI!U REPUTATORS Facepiece, half-mnsk 14] ]/
fiP 5
21B 30 CFR 6 14.h (b ) (h )
(b) (5); 1! F 30 CFR 13 Facepiece, full ]/
HP 100 2]B 30 CFR a 14.1 4
6 I1.
AU10GFilEl(E-SUPPLY LfIG REPIIW1VR 1.
Airline renpirator CF 100 19B 30 CI'R A 12.2 ( c ) ( 2 ) Type C ( 1 )
Facepiece, hrtlf-mask L'
CF 1,000 19B 30 CFIt 612.2 (c) (2) Type U (1)
Facepiece, full Facepiece, fullJ/
D 500 19B 30 C}R a 12.2 (c) (2) Type C (ii) 000 19B 30 CFil 912.2 (c) (2) Type C (iii) 1,g j6, Facepiece, full PD Hood
. -[C F - :-
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6 Suit 2.
Self-contained breathing apparatus (SCIn)
Faceplece, full ]/
D
":n 13E 30 CFil 8 11.it (b) (2) { L)
(b) (d) 111)
Facepiece, full PD 1,000 13E 30 CFR 0 11.14 Facepiece, full R
1,000 13E 30 CFR D 11.4 (b) (1) g III.
CCHBINATION RESPI!1ATOR Protection factor for 19B CFI B 12.2 (e) or applicable Any combination of air-purifyirq and atmosphere-type arat mode of opera-schedules as listed abo e tion as listed above snpplyi;g respi-ntor l_/, 2./, M, U/: p,{/,]/,
(These notes are en the so11oving pages)
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'See the following symbols CF:
Continuous Flow D:
Demand
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Negative Pressure.(i.e., : negative phase during inhalation) -
- [
PD:
Pressure Demand
- (i.e., ~ always positive preocure)
R:
Recirculating (closed circuit)
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(a) For purposes of this Specificntion the protection fnetor is a measure.of the
- {
2]
degree of protection afforded.by. a recpirator, defined 'as the ratio of the -
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concentration of airborne radioactive material outaide' the respiratory pro-tective equipment! to.that in. Ide the equipmer t (usually inside the ' facepiece) J t
d-under conditions of use.. It.is applied to the a:abient airborne concentration '
j i
to estimate the concentration. Inhaled by the wenrer according to the following fonnula:
I i
Ambient Airborne Concentration Protection Factor -
l Concentration Inhaled
=
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(b)' The protection factors apply:
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(1) only for trained individuals wearing properly fitted respirators used E
and maintained under supervision in a well-planned respiratory pro-tective program.
J (ii) ' for air-purifying respirators only when high efficiency (above.99 9%
removal efficiency by. U.S. Pureau of Mines type diocty3 ; phthalate (DOP) test) particulate filters and/or sorbents appmpriate to the i
i hazani am.used in atmospheres not deficient in oxygen.
I' (iii) for atmosphere-supplyang respirators only when supplied with adequate mspirable air.
[
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Excluding radioactive. contaminants that present an absorptio'n or submersion hazard.
~
For tritium oxide approxinntely half of the intake occurs by: absorption.through the i
skin so that an overall pmtection. factor of not mom than approximately 2 is ap-pmpriate when atmosphem-supplying respirators are used to pmtect a6ainst : tritium oxide. ' %ir-purifying respirators are not recommended for use a6ainst tritium oxide.
See also footnote g, bel a, concerning supplied-air.suita and hoods.
- 6. 5.
_..._ _ _ _ _ _ _ _._.. _. _ _ _. _ _ _ _ _ _ 2. _ _ a _, _ 2 _ _ _
a, 207
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4 14j Under chin type only.
Hot recommended for use where it might be possible for the ambient airborne concentration to reach instantaneous values greater than 50 times the pertinent values in Appendix B, Table I, Column 1 oi 10 CFR Part 20.
5]
Appropriate protection factors must be detennined taking ru :ount of the design of the cult or hood and its.pemeability to the contaminant under conditions of use.
No protection factor greater than 1,000 shall be used except as authorized by the Commission.
6]
Na approval ochedules currettly available for this equipment.
Pquipment must be evaluated by. testing or on basis of available test informition.
J/
Only for shaven faces.
NOTE 1: Protection factors for respirators, as may be approved by the U.S. Bureau of 111nes according to approval schedules for respinitors t.o protect against airborne radionuclides, may be used to the extent that they do not exceed the protection factors listed in this Table.
'Ihe protection factorc in-this.
Table may not be appropriate to circumstancec.where qhemien1 or other respi-rotory hazards exist in addition to radioactive hazards.
'ihe selection and use of lespirators for such circumstances :,hould take.into account approvals
.-of' the U.C3 Bureau of Mines in acconlance with its applicable schedules.
N01'E 2: Iladioactive contaminants for which the concentration values in Appendix B, Table I of 10 CFR Part 20 are baced on internal doce due to inhalation my, in addition, present external exposure hazards at higher concentrations.
Under such circumstances, limitr', ions on occupancy may have to be governed by external dose limits.
m 4
~
6.5 206
.~
' C.
Maintenance and Test
'lhe following maintenance and test procedures will be developed to satisfy routine inspec-tion, preventive maintenance programs, ar.d operating license requirements!
1.
Routine testing of Engineered Safe 6uards and equipment as required by the facility license and the Technical Specifications.
2.
Routine testing of standby and redundant equipment.
3 Preventive or corrective maintenance of plant equipment and systems that could have -
an effect on nuclear safety.
4.
Calibration and preventive unintenance of instrumentation that could affect the nuclear-snfety of the plant.
5 Special testing of equipment for proposed changes to operational procedures or pmposed system design changen.
D.
Temporary Changes to Procedures Temporary changes to procedures described in A, B, and C above, which do not change the intent of the original procedures may be made with the concurrence of two individuals holding senior operator licenses.
Such changes shall be documented, reviewed by the Operations Committee and approved by a member of plant management designated by the Plant Manager within one month.
6.6 Plant opemting Records A.
Records Retained for Five Years Decords and logo relative to the following items shall be retained for a minimum of five years:
1.
Ikarmal plant opetution including such items as power level, periods of opemtion at each level, fuel exposure and shutdowns.
2.
Written shift supervisory and reactor logs.
3 Periodic checks, inspections, tests and calibrations of components and systems, as related to these 'Ibchnical Specifications.
4.
Deviews of chan6es cnde to procedtireu or equipraent and revim.6 offtests and experiments.
209
- 6.6
s 5.
Principal maintenance activities, iacluding inspection, repairs and substitution or replacement of principal items of equipment pertaining to nuclear safety.
6.
Records of changes to plant procedures and records of special tests and experiments.
7.
Becords of wind speed and direction.
B.
Records of individual plant staff m3mbers showing qualifications, training and retraining.
B.
Records Retained for Plant Life Becords and logs relative to the following items.shall be retained,for the life of the plant!
1.
Liquid and gaseous radioactive releases _to the environs u diation exposures for all plant, visitor and contractor personnel 2.
n 3.
Off-site environmental monitoring curveys 4.
Fuel accountability including new and opent fuel inventories and transfers, and fuel assembly histories
- 5. Radioactive shipments 6.
Abnormal occurrences
- 7. Plant radiation and contamination' rurveyn Changes made to the plant as it is described in the Final Safety Analysis Beport, 8.
reflected in updated, corrected an. as-built drawings 9, cycling beycnd normal limits for those components that have been designed to operate safely for a limited number of cycles beyond such limits
.710
10.
Reactor coolant system in-service inspections 11.
Minutes of meetings of the Safety Audit Committee 6.7 Plant Reporting Requirements The following information shall be submitted to the USAEC in addition to the reports required by Title 10, Code of Federal Regulations.
A.
Operation Reports Operation reports shall be submitted in writing to the Director of 1,1 censing, USAEC, Washington, D. C.
20545.
1.
Startup Report A summary report of the facility startup and power escalation testing shall be submitted following receipt of operating licenses, following amendment to the licenses involving a plc.,ned increase in power level, following installation of fuel that has a different design and/or has fuel supplier, or following modifications to en extent. that becu manufactured by a different The thermal, or hydraulic performance of the unit may be significantly altered.
the nuclear, report shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison with design predictions and Any corrective actions that were rec,ulred to obtain satisfactory operation specifications.
shall be described.
Startup reports shall be submitted with 60 days following cornencement of commercial power operation, i.e., initially following synchronization of the turbo-generator to produce commercial power or resumption of commercial power operation.
~
Sem annual Operating Report
- i 2.
A report covering a six-month period shall be submitted within 60 days after January 1 and July 1 of each year and include the following:
- A single submittal may be made for a multiple facility station.
The report shall combine those sections such as environmental monitoring that are common to all the facilities at the station.
211 6'. 7
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Operations Summe y_
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A summary of operating experience occurring during the reporting period that relates
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to safe operation of the facility, including & summary.of (1) changes in facility-design,
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-(2)- performance characteristics (e.g., equipment. and' fuel performance),s
. (3). changes in operating methods which. vere necessitated 1by. (1) and -(2) or which 1
lotherwise were required to improve'the: safety of facility operations, f
(4) results of surveillancey tests and J aspections ' required by' these technical spectilcations,
-(
)
(5) the results of any periodic containment. leak rate tests performed-duringLthe
.i reporting period, 1
(6) - a brief stnmaary. of those changes, tests'and'experimenta. requiring authorization from the Commission'pursusnt to 10 CFR 50.59(a), and t
(7) changes in the. plant operating staff for those. positions which'are designated as t
key supervisory personnel on Figure 6.1.2.
b.
Power Generation A summary of power generated.during the reporting period-including:
)
(1) ~ gross thermal power generated (in'MWH),
4 (2) gross electrical power' generated (in HWH),
(3) net electrical power generated (in MWH),
(4) number of hours the reactor was critical, (5) number of hours the generator was on-line, and (6) histogram of thermal. power vs. time.
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c.
Shutdown Descriptive material covering all outagca occurring during the reporting period.
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For each outage, information shall be provided ont i
(1) the cause of the outage, (2) the method of shutting down the reactor; e.g., trip, automa'ic rundown, or manually contro led deliberate shutdown, (3) duration of the outage,.
(4) unit status during the outage; e.g., cold shutdown or hot shutdown, and (5) corrective action taken to prevent repetition, if appropriate.
.d.
Maintenance A discussion of corrective maintenance'(excluding preventative maintenance) performed during the reportin g period on safety related systems and components
~
!~afety related is defined in ANSI-N18. 7-1972 ( ANS-3.2, Nov. 2,1972)] and on systema and components that reduce or prevent the release cCaradioactive material to the environs. For any malfunctions for which corrective maintenance was
)
required, information shall be provided on:
(1) the system or component involved, (2) the cause of the malfunction, (3) the results and effect on safe operation, (4) corrective action taken to prevent repetition, and (5) cpecial precauticas taken to provide for reactor safety during repair.
e.
Changes, Tests and. Experiments A brief description and the summary of the safety. evaluation for those changes. tests, and experiments which were carried out without prior Commission approval, pursuant-to' the requirements of 550.59(b) of the Commission's. regulations.
6.7
.213-A
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f.
Radioactive Effluent Releases
- - ~ ~
A statement of the quantities of radioactive effluent released from the plant, with data summarized on a monthly basis folloutng a standard format as issued by the AECs (1) Gaseous Effluents (a) Cross Radioactivity Releases (i)
Total gross radioactivity (in curies), primarily noble and activation gases.
t (ii) Maximum gross radioactivity release rate during any one-hour period.
(iii) Total gross radioactivity (in curies) by nuclide released, based on representative isotopic analyses performed.
(iv) Percent of technical specification limit.
(b)
Iodine Releases (i)
Total' iodine radioactivity (in curies) by nuclide released, based on represnetative isotopic analyses performed.
(ii) Percent of technical specification limit for I-131 released.
(c) Particulate Releases (i)
Total gross radioactivity QdhI) released (in curies) excluding background radioactivity.
(ii)
Cross alpha radi a 2ivity. released (in curies) excluding background radioactivity.
(iii) Iotal gross radioactivity (in curies) of nuclides with-half-lives greater than,cight days.
(iv) Percent of technical specification limit for particulate radioactivity with half-lives greater.than eight days.
6.7.
214
(2) Liquid Effluents (a) Total gross radioactivity (/(d released (in curies) excluding tritium and average concentration. released to the unrestricted area.
l (b) The maximum concentrat ion of gross radioactivity (4'i I' released to.the K
unrestricted area.(averaged over the period of release).
(c) Total tritium and total alpha radioactivity (in curies) released and~
l average concentration released to the unrestricted area.
I (d) Total dissolved gas radioactivity (in curies) and average concentration released to the unrestricted area.
1
[
(e) Total volume (in liters) of liquid waste-released.
l
'(f) Total volume (in liters) of dilution water used prior to release from the restricted area.
(g) Total gross. radioactivity (in curies) by nuclide released :bssed on representative isotopic analyses performed.
l (h) Percent of technical specification limit for totd1 radioactivity.
I
- g. ' Solid Waste
.. W (1) The total amount'of solid vaste packaged (in cubic feet).
(2) The total estimated radioactivity (in curies) involved.
(3) Disposition including date and destination if shipped offsite.
4 l
h.
Environmental Monitoring 1
d (1)
For each medium sampled, e.g., air, river bottom, surface water, soil, fish, include:
1 (a) Number of sampling locations, 1
(b) Total number of sample s, (c) Number of locations at which levels are found to be significantly. above local backgrounds,
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lowest, and the annual average concentrations or Icvels of
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(d) radiation for the sampling point with the highest average and description of the location of that point with respect to the site.
If levels of radioactive materials in environmental media as determined by an (2) environmental monitoring program indicate the likelihood of public intakes in excess of 1% of those that could result from continuous exposure to the concentration values li ted in Appendix B, Table II, Part 20, estimates of the likely resultant exposure to individuals and to population groups, and assumptions upon which estimates are based shall be provided.
If statistically significant variation of offsite environmental concentrations (3) with time are observed, correlation of these results with effluent release shall be provided.
~
1.
Occupational Personnel Radiaton Exposure s ;~
Tabulate the number of personnel exposures for plant personnel by duty function in the following exposure increments for the reporting period:
less than 100 mrem, 100 - 500 mrem, 500 - 1250 mrem, 1250 -2500 mrem, 2500 - 5000 mrem, above 5000 mrem.
Annually tabulate the number of personnel having an exposure greater than 2500 mrem and report the major cause(s).
B.
Non-Routine Reports 1.
Abnormal Occurrence Reports Notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph to the Director of the Regional Regulatory Operations Of fice (cc to the Director of Licensing), followed by a written report within 10 days to the Director of Licensing (cc to the Director of the Regional Regulatory Operations Office)
In the event of the abnormal occurrences as defined in Section 1.0.
The written report on these abnormal occurrences, and to the extent possible, the preliminary telephone and telegraph notification, shall:
(a) describe, analyze and evaluate safety implications, (b) outline the measures taken to assure that the cause of the condition is determined, (c) indicate the corrective action (including any changes made to the procedures and to the quality assurance program) taken to prevent repetition of the occurrence and of similar occurrences involving similar components or systems, and (d) evaluate the safety implications of the incident in light of the cumulative experience obtained f rom the record of previous failures and malfunctions of similar systems and components.
216 f
} 6.7
2.
Unusual Events A written report shall be forwarded within 30 days to the Director of Licensing, and to the Director of the Regional Regulatory Operations Office, in the event of:
Discovery of any substantial errors in the transient or accident analyses, or in the a.
methods used for such analyses, as described in the Safety Analysis Report or in the bases for the technical Specifications.
b.
Discovery of any substantial variance from performance specifications contained in the technical specifications or in the Safety Analysis Report.
Discovery of any conditioninvolving a possible single failure which, for a system.
c.
designed against assumed single failures, could result in a loss of the capability of the system to perform its safety function.
G.
Special Reports
~
The following special reports shall be submitted in writing to the Director of Licensing, USAEC, Washington, D. C.
20545:
Specification Area Reference Submittal Date 1.
Primary Containment 4.7A 90 days after completion Leak Rate Tests of each test requiring a sunnary technical report 2.
Secondary Containment 4.7C 90 days after completion Leak Rate Tests (1) of the first refueling outage 3.
Th-service Inspection 4.6F & 4.6F Bases 90 days after the "five-Evaluation & Development year" inspection has been completed (2) 4.
Analysis of Surveillance 4.6B Bases Within one year after Specimens removal from the vessel
'5.
Main Steam Line Isolation 4.7A Bases 90 days after completion Vaise Leakage 6 Closure Time of leak rate tests e
'67 217
E -
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Specification Area Submittal Date I
4 E
6.
Summary Status of Fuel 2.1 Bases 90' days after each refueling outage starting with second
-[
refueling outage 7.
Failed Fuel Detection 3.2 Dasea 5 years-(2) l, 8.
Primary Coolant Leakage 4.6D Bases Annual Report by March 31 to Drywell
- of following year l
I
. 9.'
Instrument Line Flow.
4.7D Bases 90 days after completion Check Valve Evaluation, of.first. refueling outage j
i NOTE:
(1) This suussary technical report should include data on the wind speed.. wind direction, outside and.inside temperatures during the test, concurrent reactor building pressure, and emergency l
ventilation flow, rate.
The, report shall also include' analyses and interpretations of these data which demonstrate compliance with the specified leak rate limits. Surveillance testing.
at refueling outages after the first operating cycle should be reported in the semiannual operating reports.
l (2) _The an==ary technical report shall be submitted within the period of time listed based on the initial comunercial.ssevice date as the starting point.
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