ML20079D396
| ML20079D396 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 06/28/1991 |
| From: | BALTIMORE GAS & ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20079D395 | List: |
| References | |
| NUDOCS 9107120249 | |
| Download: ML20079D396 (18) | |
Text
,__
2 NITACllMENT (1)
The following 17 Unit 1 pages are included:
6-1 6-6 6-7 6-7a 6-8 6-Sa 6-8b 6-8c 6-9 9-10 6 11 6-12 6-13 6 -13a 6-14 6-20 6 22 l
l l
l l
9107120249 910628 PDR-ADOCK 05000317 PDR P
a l
ADMINISTRATIVE CONTROLS l
6.1 RESPONSIBILITY 6.1.1 The[P1 ant _ Genera 9 Manager shall be responsible for overall
\\
l facility operation and shall delegate in writing the succession to this responsibility during his absence.
-6.2 ORGANIZATION l
6.2.1 ONSITE & OFFSITE ORGANIZATIONS i
Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite crganizations shall include the positions 'for activities affecting the safety of the nuclear power plant, a.
Lines of authority, responsibility and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.
These requirements shall be documented in FSAR Chapter 12, and updated in accordance with 10 CFR 50.71(e).
1 b.
The[ Plant Genera Manager shall be responsible for overall unit
}
safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the
- plant, c.
The Vice President-Nuclear Energy shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety, d.
The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
6.2.2 UNIT STAFF a.
Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.
b.
At least one licensed Operator shall be in the control room when fuel is in the reactor.
Effective at 12:01 a.m. on November 30, 1988.
Replaces page 6-1(t).
CALVERT CLIFFS - UNIT 1 6-1 Amendment No. U lf)/JJE/JJJ/
AUG 31 1988 1
L AD31H111MIRLt0RIE0LS 6.3 FAtlllTY STAFF OVAllFICATIONS 6.3.
ich member of the facility staff shall meet or exceed the minimum qual
.ations of ANSI N18.1-1971 for comparable positions, except fo<
(1) tne Radiation Safety Engineer who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975, and (2) the Shift Technical Advisor who shall have a Bachelor's Degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant fcr transients and accidents.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the General Supervisor-Nuclear Training and shall meet cr exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and Appendix "A" of 10 CFR Part 55, as applicable.
6.4.2 A training program for the Fire Brioade shall be maintained under the direction of the General Supervisor (Planninband Support and shall meet or exceed the requirements of Section u of the NFPA Code-1975.
6.5 REVIEW AND AUDll 6.5.1 PLANT OPERATIONS AND SAFETY REVIEW COMMITTEE (POSRC)
FUNCTION 6.5.1.1 The POSRC shall function to advise the Plant General Manager on all matters related to nuclear safety.
COMPOSITI.0!N ThePOSRCshallbecomposedo_fjatleastseven,butnomoretha[
6.5.1.2
( ten, members, including the f.,hairman. Members shall collectively have j
{experienceinthefollowingareas:
Nuclear Operations Electrical and Controls Maintenance Chemistry Mechanical Maintenn ce l
M ucleab Engineering Radiation Safety Plant Engineerina (Design t.ngineering)
IMembers shall be appointed in writing by the Plant General Manager.
Members shall have a minimum of eight years power plant experience of which a minimum of three years shall be nuclear power experience.
At least one member shall have an SR0 license on Calvert Cliffs Units 1d CALVERT CLIFFS - UNIT 1 6-6 Amendment No. /E/fE/EJ/E//EE/
llEll}],
.4 ADMINISTRATIVE CONTROLS CHAIRMAN N
I 6.5.1.3 The Chairman-and' alternate Chairmen of the POSRC shall be appointed in writing by the Plant General Manager. Chairmen shall have a L
minimum of 10 years power plant experience of which a-minimum of three i
Jears shall be nuclear power experience.
ALTERNATES 6.5.lh All alternate members shall be aD)ointed in writing by th 7ueneral Manager. Alternate members shall lave a minimum of eight years i power plant experience of which a minimum of three years shall be nuclear L
(power experience y MEETING-FRE0VENCY
-6.5.105 The POSRC shall meet at least onca per calendar month and as convened by the POSRC Chairman or@ne of thldesignated alternate @
OU0 RUM 6.5.lb A ouorum of the POSRC shalllinclude the Chairman or one of the 3 (members, including alternates. designated alternate cnairmen and shall consist of No more than half of the quorum shall bej i
. Laiternates, including an alternate chairman.
RESPONSIBIllTIES I
6.5.lb The POSRC shall be responsible forlthe following except for ThoseitemsdesignatedforreviewbytheProcedureReviewCommitte l-r QualifiedReviewerinaccordance'withSpecification6.5.2and6.5.3,j l
respectively: f
\\
a.-
Review of 1) all rocedures required by Specification 6.8.and
-changes thereto, an 2) any other aronm ed procedures or
-changes thereto as determined by tie [ Plant GeneraT) Manager to affect-nuclear safety.--
l-Cross-disciplinary reviews of these procedures are conducted in) accordance with administrative procedures in addition to the reviews conducted by POSRC, the Procedure Review Committee, or jl L
l (Qualified Reviewer o
b.
Review of all-proposed teits and experiments that affect nuclear safety, c.
Review of all-proposed. changes to Appendix "A" Technical Specifications, d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
CALVERT CLIFFS --UNIT 1 6-7 Amendment No. /E//p/f7/9//JSE/
U 119/171,
.=
ADlilNISTRATIVE CONTROLS Review of the Plant Security Plan and implementing procedures and shall submit recommended changes to the Off-Site Safety Review Committee.
Of.
Review of the Emergency Plan and implementing procedures and shall submit recommended changes to the Off-Site Safety Review Committee.
0 9 Review of changes to the PROCESS CONTROL PROGRAM and the OFFSITE DOSE CALCULATION MANUAL.
l h.
Review of all 10 CFR 50.59 Safety Evaluations that support procedures in 6.5.1.7.a and changes or modifications in j 6.5.1.7.d.,
Oi, Investigation of all viciations of the Technical Spacifications including the preparation and forwarding of reports covering nvaluation and recommendations to prevent recurrence to +be (Plant General Manager, the)Vice President Nuclear Energy and to Tne i.na uiaan 61 the Ott-Site Safety Review Committee.
Review of all REPORTABLE EVENTS.
g k
Review of facility operations to detect potential safety
}
hazards.
Review of any accidental, unplanned or uncontrolled radioacthe f
01.
release that exceeds 25% of the limits of Specification 3.11.1.2, 3.11.2.2 or 3.11.2.3, including the preparation of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence and for forwarding of these reports to the Plant General Manager and the Off-Site Safety Review Committee.
I m.
Performance of special reviews, investigations or analyses and reports thereon as requested by the Chairman of the Off-Site Safety Review Committee.
CALVERT CLIFFS - UNIT 1 6-7a Amendment No. JE/30/fJ/9f/JpEl 119/171,
~
...~. -
.j-n ADMINISTRATIVE CONTROLS
-AUTHORITY
-6.5.lh The Plant Operations and Safety Review Committee shall:
Recommend to the approval authority approval or disapproval of a.
procedures considered under 6.5.1.7.a f h Recommend to thefPlant GeneraD er appro r disapproval of_ items considerec under 6.5.1 through above.
Q Render determinations in writing regard t hether_or not-each item considered under 6.5.1 a through h above constitutes an unreviewed-safety question, fd.
Evaluate root causes and recommended actions to prevent
- L recurrence for items considered.under 6.5.1.7(1) through (1).
Oe. Provide written notification _with@24' hours to the Vice President-Nuclear Energy and the/ Chairman of the70ff-Site Safety Review Committee of disaoreement between the POSRC and Jthe responsible approval authority in the case of Otem 6.5.1.7.a or between the POSRC and the Plant Genera]l Manager; however, the Plant GeneraHManager shall have responsibility for reso u on of such disagreements pursuant to 6.1.1 above.
RECORDS 6.5.lh The-POSRC shall maintain written minutes of each meeting and Ecopies shall be provided to the Vice President-Nuclear Energy, Chairman of-the Off-Site Safety Review Committee,(and the Plant. General Manageg 5.5.2~PROCEDUREREVIEWCOMMITTEE
-FUNCTION' 16.5.2.1 The_ Procedure Review Committee may function to review items listed-in Specification 6.5.1.7(a) in lieu of review by POSRC or-
' Qualified Reviewer as-directed by the Plant General Manager.
. COMPOSITION.
6.5.2.2 The Procedure Review Committee shall be composed of a Chairman and eight individuals who shall collectively have expertise in the areas contained in Technical Specification 6.5.1.2.
CALVERT CLIFFS -. UNIT 1 6-8 Amendment No. /J/JJE/JJJ,
<r~w we w -.s w
,,..-c.-
-.-s..+ar e-w ew w
-..-,+-w3 w=or - -- wryr,
-iv.,,-v-*w m.,-
=
wwwwrr-,
wwww--=,,
e,--w-g r re-+siv it grv-r,s*-
p e -w mvn+=
- -=r*w
M,f _
ADMINISTRATIVE CONTROLS Members shall be appointed in writing by the Plant General Manager.
Members shall have a minimum of eight years power plant experience of
-which a minimum of three years shall be nuclear power experience. At fleast one member shall be a POSRC member or alternate.
The charter for the Procedure Review Committee shall include a description of membership,
.. qualifications, functions, and reports and 'shall be described in-plant administrative procedures. The Procedure Review Committee may be dissolved-at the discretion of the Plant _ General Manager.
CHAIRMAN-i 6.5.2.3 The Chairman and alternate Chairmen of the Procedure Review Committee shall be appointed in writing by the Plant General Manager.
Chairmen shall;have a minimum of eight years power plant experience of which a minimum of _three years shall be nuclear power experience.
ALTERNATES
--6.5.2.4 ' A11 alternate members shall be appointed in writing by the Plant General Manager. _. Alternate members shall have a minimum of _ eight years power plant experience of which a minimum of three years shall be nuclear power experience.
MEETING:FDE0VENCY
- 6.5.2.5.. The Procedure Review Committee shall meet at least once per calendar month and as. convened by the Chairman or his designated
- alternates.
.QV0 RUM 6.5.2.6 A quarum for the Procedure Review Committee shall consist of the Chairman or one-of the designated alternate Chairmen and-three primary or alternate members provided at least four disciplines are represented.
AUTHORITY 6.5.2.7 The Procedure Review Committee shall:-
a.
Recommend'to the Approval Authority approval or disapproval of' procedures considered under 6.5.1.7(a).
b.
Render. determinations in writing with regard to whether or not eachprocedureunder6.5.1.7(a) constitutes an unreviewed safety question, c.
Frovide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President-Nuclear Energy and the Chairman of the Off-Site Safety Review Committee:of disagreements between the Procedure -f Review Committee and the responsible approval authority. The Plant General Manager shall have responsibility for-resolution [
_ /
of such disagreements pursuant-to 6.1.1 above.
N CALVERT CLIFFS - UNIT 1 6-8a Amendment No.
~..
. -. ~ -.. - -. -....
ADMill1SJRA111LCONIROLS gggpg
)
6.5.2.8 1he Procedure Review Committee shall maintain written minutes nf each meeting and copies shall be provided to the Plant General Manager.
El___QUAULIG RLUMRft EV11Cll.03 6.5.3.1 The Plant General Manager may designate specific procedures or classes of procedures described in Specificaticci 6.5.1.7.a to be reviewed by Qualified Reviewers in lieu of review by POSRC or the Procedure Review Committee.
6VIHORITY 6.5.3.2 Qualified Reviewers shall:
a.
Recommend to the approval authority approval or disapproval of designated procedures and changes considered under 6.5.1.7.a, and b.
Render determination in writing with regard to whether or not each procedure under 6.5.1.7.a constitutes an unreviewed safet) question, c.
Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Vice President Nuclear Energy and the Chairman of the Off-Site Safety Review Committee of disagreements between the Qualified Reviewer and the approval authority. The Plant General Manager shall have responsibility for resolution of such disagreements pursuant to 6.1.1. above.
CERTiflCATIOR 6.5.3.3 Qualified Reviewers shall be nominated, trained, and certified in accordance with administrative procedures.
Certification shall be by a department manager.
6.5.3.4 Certification requirements of personnel desig'ated as Qualified eviewers shall be in accordance with adatinistrative procedures CALVERT Cliffs - UNIT 1 6-Bb Amendment No.
ADMINISTRAllVE CQHIRQLS ualified Reviewers shall have:
a.
A Bachelors degree in engineering, related scierece, or technical discipline, and two years of nuclear power plant experience; 08 b.
Six years of nuclear power plant experience 0.8 c.-
Equivalent combination of education and experience as approved by a Department Manager.
RECORDS Review of procedures by Qualified Reviewers shall be documented) i (6.5.3.5 in accordance with administrative procedures.
6.5 @ OFF-SITE SAFETY REVIEW COMMITTEE (OSSRC)
FUNCTION 6.5h1 The Off-Site Safety Review Committee shall function to provide independent review and audit of designated activities in the areas of:--
a.
nuclear power plant operations b.
nuclear engineering c.
chemistry and radiochemistry d.
metallurgy and non-destructive examination e
instr. entation and control-f.
radiological safety g.
mechanical and electrical engineering h.
quality assurance practices CALVERT CllFFS - UNIT 1 6 8c Amendment No.
..,.+,. -.. - --.
-,,-.....-....,z.-,.-..-.-
~
_. y
.x ADMINISTRATIVE wNTRQLS COMPOSIT),Q!i 6.5b42 The OSSRC shall be composed of at least seven members, including the Thairman. Members of the OSSRC may be from the Nuclear Energy Division or other BG&E organization or from organizations external to BG&
nd shall collectively have expertise in all of the areas of 6.5 1.
WALIFICATIONS C.5h4 The Chairman, members and alternate members of the OSSRC shall be aYpointed in writing by the Vice President-Nuclear Energy and shall have an academic degree in engineering or a physical science, or the equivalent, and in addition shall have a min m of five years technical experience in one or more areas given in 6.5 1.
No more than two alternates shall participate as voting membe in OSSRC activities at any one time.
CONSULTANTS 6.5 4 Consultants shall be utilized as determined by the OSSRC Cha man to provide expert advice to the OSSRC.
MEETING FRE0VENCY 6.Sh The OSSRC shall meet at least once per six months.
000 RUM 6.5 4-The quorum of the OSSRC necessary for the performance of the OSSF. review and audit functions of these Technical Specifications shall consist of more than half the OSSRC membership or at least four members, whichever is greater.
This quorum shall include the Chairman or his appointed alternate and the OSSRC members, including appo ed alternates, meeting the requirements of Specification 6.5
- 13. No more than a minority of the quorum shall have line responsibil y for operation of the plant.
CALVERT CLIFFS - UNIT 1 6-9 Amendment No. ///JJP/
,y y 4u,
+
ADMINISTRATIVE CONTROLS REVIEW 6.h7 The OSSRC shall review:
L a.
The safety evaluations for 1) changes to procedures, squipment or systems and 2) tests or experiments completed under the provisions of Section 50.59, 10 CFR, to verify that such actions did not constitute an unreviewed safety question.
b.
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in Section 50.59, 10 CFR.
c.
Proposed tests or experiments which involve an unrev',ewed safety question as defined in Section 50.59, 10 CFR.
d.
Proposed changes in Technical Specifications or this Operating
- License, e.
Violatior, of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance.
f.
Significar c operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
g.
All REPORTABLE EVENTS.
h.
All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components i.
Reports and meetings minutes of the POSRC.
l l
l 1
l CALVERT CLIFFS - UNIT 1 6-10 Amendment No. SM
g f,, y,
I
@MildSIRAI1YLCOMIE0LS MD115 6.5C48.1 Audits of facility activities shall
, performed under the L
cognTzance of the OSSRC. These audits shall ent...apass:
a.
The conformance of facility operation to provisions contained within the Technical Specifications and applicab10 Itcense conditions at least once per 12 months.
b.
The performance, training and qualification of the entire facility staff at least once per 12 months.
c.
The results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per 6 months.
d.
The performance of activities required by the Quality Assurance Program to meet the criteria of Appendix *B", 10 CFR Part 50, at ieast once per 24 months, e.
- Deleted, f.
The Safeguards Contingency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR 73.40(d).
g.
Any other area of facility operation considered appropriate by the OSSRC or the Vice President Nuclear Energy.
h.
The Facility Fire Protection Program and implementing procedures at least once per 24 months, i.
An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j.
An inspection and audit of the fire protection and loss prevention program shall be performed by a qualified outside fire consultant at least once per 36 months.
k.
The radiological environmental monitoring program and the results thereof at least once per 12 months, 1.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months.
m.
The PROCESS r0NTROL PROGRNi and implementing procedures for processing
,.o packaging of radioactive wastes at least once per 24 morn,
i CALVERT CLIFFS - UNIT 1 6-11 Amendment No. JE/E//JEJ/JJE/
^IV
[
8DMINISTRATIVL10111110LS n.
The performance of activities required by The Quality Assurance Program for effluent and environmental monitoring at least once per 12 months.
6.5048.2 Review of facility activities shall be performed under the cogrTfzance of the OSSRC. These reviews shall encompass:
a.
The facility Emergency Plan and implementing procedures at least once per 12 months in accordance with 10 CFR Part 50.54(t).
AUTHORITY 6.5 9 The OSSRC shall report to and advise the Vice President-luclear Ene onthoseareasofresponsibilityspecifiedinSection6.5@7and 6.5 8.
RECORDS 6.5 4 10 Records of OSSRC activities shall be prepared, approved and I
dis, ibuted as indicated below:
a.
Minutes of each OSSRC meeting shall be prepared, a) proved and forwarded to the Vice President-Nuclear Energy wit 1in 14 days following each meeting.
Reports of reviews encompassed by Section 6.5h4 7 above, shall b.
be prepared, approved and forwarded to the Vi Y. President-Nuclear Energy within 14 days following completion of the
- review, AuditreportsencompassedbySection6.5h4 above, shall be I
c.
forwarded to the Vice President-Nuclear.1fergy and to the i
managtment positions responsible for the areas audited within 30 days after completion of the audit.
6.6 REPORTABLE EVENT ACTION C.5 1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVEMT shall be reviewed by the POSRC and the results of this review shall be submitted to the OSSRC and the Vice President-Nuclear Energy.
\\
CALVERT CLIFFS - UNIT 1 6-12 Amendment No /E/p//J//Jps/JJp/
o l
ADHUll!illM11YI_C.0lilR0tS 6.7 SAFETY LIMil VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
a.
The facility shall be placed in at least 110T STANDBY within one
- hour, b.
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within one hour.
The Vice President-Nuclear Energy and the OSSRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, c.
A Safety Limit Violation Report shall be prepared. _The report shall be reviewed by the POSRC.
This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the OSSRC and the Vice President-Nuclear Energy within 14 days of the violation.
6.8 PROCEDURES 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Refueling operations.
c.
Surveillance and test activities of safety related equipment.
d.
Security Plan implementation.
e.
Emergency Plan implementation, f.
Fire Protection Program implementati g.
The amount of overtime worked by plant staff members performing safety related functions must be limited in accordance with the NRC Policy Statement on working Hours (Generic letter No.
82-12).
POSRC is only required to review Fire Protection procedures and changes thereto which affect nuclear safety.
CALVERT CLIFFS - UNIT 1 6-13 Amendment No. 75/f7/7E/EJ/JEE/
I Ji9/JEl,
ADMllf1SIMllVLCDli1EDLS h.
PROCESS CONTROL PROGRAM implementation.
i.
Of fSill DOSE CALCULATION MANUAL imphmentation.
b6.8.2 The Plant General Manager may designate spec:fic procedures or classes of procedures in writing to be reviewed by the Procedure Review Committee or by Qualified Reviewers in lieu of review by the POSRC.
Review by the Procedure Review Committee shall be in accordance with paragraph 6.5.2.
Review by Qualified Reviewers shall be in accordance with paragraph 6.5.3.
6.8.3 Procedures listed in 6.8.1 shall be approved by the Plant General Manager or by cognizant Managers, Superintendents, or General St >rvisors (or Directors) that report directly to a Manager prior to impli
.tation as specified by administrative requirements.
The approval aut Ity for specific procedures or classes of procedures shall be designat. in writing by the Plant General Manager and shall be a different individual kfromtheQualifiedReviewer.
l 6.8h Each procedure of 6.8.1 above and changes thereto shall be l
reviewed periodically as set forth in administrative procedures.
CALVERT CLIFFS - UNIT 1 6-13a Amn dment No. JEl# //E/EJ/ipEl 119/DJ,
- *x 4
<f 4..~p,,,*
ADMINISTRATIVE CONTROLS 6.8b5 Temporary changes to procedures of 6.8.1 above may be made provTded:
a.
The intent of the original procedure is not altered, b.
The change is approved by two members of the plant management staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected, Thechanceisdocumented,revieworfhvthePOSRC,[theProcedure) c.
(Review Comittee, or by a Qualified Reviewerland approved Dy theldesignateo_aoprovalauthorityJwithin14daysof implementation. ~
6.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.
iTARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include c description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain saticfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
CALVERT CLIFFS - UNIT 1 6-14 Amendment No. 29//J/EJ/Jf//#E/
11#/131/
mw,w.x - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
a,vyiejg ADri1N111MUK10NIfLOLs d.
Records of radiation exposure for all individuals entering radiation control areas.
e.
Records of gaseous and liquid radioactive material released to the environs.
f.
Records of transient or operational cycles for those facility emponents identified in Table 5.7-1.
g.
Records of training and qualification for current members of the plant staff.
h.
Records of in-service inspections performed pursuant to these Technical Specifications.
i.
Records of Quality Assurance activities identified in the NRC approved QA Manual as lifetime records.
J.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
k.
Records of meetings of the POSRC,he Procedure Revih
[ Committee,) and the OSSRC.
i 1.
Records of Environmental Qualification which are covered under the provisions of paragraph 6.13.
m.
Records of the service lives of all safety related snubbers including the date at which the service life commences and associated installation and maintenance records.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel l
1 radiation exposure.
l l
6.12 HIGH RADIATION AREA l
6.12.)
In lieu of the " control device" or " alarm signal" required by l
paragraph 20.203(c)(2) of 10 CFR Part 20:
l' A high radiation area in which the intensity of radiation is a.
greater than 100 mrem /hr but less than 1000 mrenVhr shall be barricaded and conspicuously posted as a High Radiation Area and entrance thereto shall be controlled by issuance of a Special or Radiation Work Pennit and any individual or group of individuals permitted to enter such areas shall be provided with a radiation monitoring device which continuously indicates the radiation dose rate in the area.
CALVERT CLIFFS - UNIT 1 6-20 Amendment No. #f/JJJ/
myc p
-49 x.ag
.i ADMINISTRATIVE CONTROLS G.16 PROCESS CONTROL PROGRAM (PCP) 6.16.1 The PCP shall be approved by the Comission prior to implen.entation.
6.16.2 Licensee initiated changes to the PCP:
1.
Shall be submitted to the Comission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made. This submittal shall contain:
a.
An evaluation supporting the premise that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and b.
A reference to the date and the POSRC meeting number in which the change (s) were reviewed and found acceptable to 1
the POSRC.
2.
Shall hacorre effective upon review by the POSRC and approval of the(P.ltn_t GeneraD Manager.
[
6.17 0FFSITE DOSE CALCULATION MANUAL (ODCM) 6.17.1 The ODCM shall be approved by the Comission prior to j
implementation.
6.17.2 Licensee initiated changes to the ODCM:
1.
Shall be submitted to the Comission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective.
This submittal shall contain:
a.
Sufficient information to support the rationale for the change.
Information submitted should consist of a package of those pages of the ODCM to be changed with each sage numbered and provided with a change number and/or c1ange date together with appropriate analyses or evaluations justifying the change (s);
b.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and c.
Documentation of the fact that the change has been reviewed and found acceptable by the POSRC.
2.
Shall harama affective upon review by the POSRC and approval of the(PlantGeneral] Manager.
CALVERT CLIFFS - UNIT 1 6-22 Amendment No. JJJ/JJJ/JJJ/JJJ/
JIJ/
.