ML20246G994
| ML20246G994 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities, 05000000 |
| Issue date: | 04/26/1989 |
| From: | Muller D Office of Nuclear Reactor Regulation |
| To: | Commonwealth Edison Co, Iowa-Illinois Gas & Electric Co |
| Shared Package | |
| ML20246G998 | List: |
| References | |
| DPR-19-A-105, DPR-25-A-100, DPR-29-A-117, DPR-30-A-113 NUDOCS 8905150325 | |
| Download: ML20246G994 (100) | |
Text
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I Yp* etcqc; UNITED STATES
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NUCLE AR REGULATORY COMMISSION
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E' WASHINGTON, D. C. 20555
\\ '...M COMMONWEALTH EDIS0N COMPANY AND IOWA-ILLIN0IS GAS AND ELECTRIC COMPANY DOCKET N0. 50-254' 0VAD CITIES NUCLEAR POWER STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.117 License No. DPR-29 1.
The hutiecr Regulatory Commission (the Comission) has found that:
A.
The c.;rlication for amendment by Commonwealth Edison Company (the licensee) dated February 21, 1989, comp' lies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the Comunission's regulations; i
D.
The issuance of this amenament will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 l
of the Commission's regulations and all applicable requirements j
have been satisfied.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B. of Facility Operating License No. DPR-29 is i
hereby amended to read as follows:
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8905150325 890426 PDR ADOCK 05000237 P
PDC L-_------_------------_
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Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 117, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION k
Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Spec,ial Projects Attochment:
Changes to the Technical Specifications Date of Issuance: April 26, 1989 j
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l ATTACHMENT TO LICENSE AMENDMENT NO.117
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FACILITY OPERATING LICENSE NO. DPR-29 DOCKET N0. 50-254 Revise the' Appendix A Technical Specifications by removing the pages ider.tified below and inserting the attached pages. The reviseo pages are identifiec by the captioned amendnent number and contain marginal lines
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indicstil.; the area of change.
REliCVE INSERT vii vii C.1-1 6.1-1 C.1-2 6.1-2 f.2-?
6.1-3 6.1-4 6.1-4 6.1-5 6.1-5 6.1-6 6.1-6 6.1-7 6.1-7 6.1-8 6.1-8 6.1-9 6.1-9 6.1-10 6.1-10 6.1-11 6.1-11 Figure 6.1-1 Figure 6.1-2 6.2-1 6.2-1 6.2-2 6.2-2 6.3-1 6.3-1 6.4-1 6.4-1
t-4 L
QUAD CITIES DPR-29' i-TECHNICAL SPECIFICATIONS APPENDIX A LIST 0F FIGURES Number Title
. '2.1 - 1 APRM Flow Reference Scram and APRM Rod Block Settings 2.1-2 Deleted' 2.1-3 APRM Flow Bias Scram Relationship to Normal Operating Conditions 4.1-1 Graphical Aid in the~ Selection of an Adequate Interval Between Tests.
4.2 Test Interval vs. System Unavailability
~3.4-1 Deleted 3.4-2 Sodium Pentaborate Solution Temperature Requirements 3.5-1
. Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) vs. Planar Average Exposure 3.5-2 K factor M{nimur.TemperatureRequirementsperAppendixGof10CFR50 3.6-1 3.6-2 Minimur. Reactor Pressurization Temperature 4.6-l' Chloride Stress Corrosion Test Results at 500 F 4.8-1
- Locations of Fixed Environmental Radiological Monitoring Stress 6.1-1 Deleted 6.1-2 Deleted 6.1 Minimum. Shift Manning Chart i
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l vii Amendment No. 117
4 QUAD-CITIES DPR-29 6.0 ADMINISTRATIVE CONTROLS 6.1 ORGANI2ATION, REVIEW, INVESTIGATION, AND AUDIT A.
Or. sin at of fsite organizations shall be established for unit operation j
and corporate management, respectively.
The onsite and offsite organiza-tions shall include the positions for activities affecting the safety of 1
the nuclear power plant.
1.
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 descrip-tions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation.
These requirements shell be documented in
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the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organization Authority, Activities:
Section 6 Interdepartmental Relationships.
2.
The Station 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.
3.
The' Senior Vice President-Nuclear Operations shall have the corpo-rate 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.
I 4.
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.
B.
Deleted.
l C.
The shift manning for the station shall be as shown in Figure 6.1-3.
The Operating Assistant Superintendent, Operating Engineer, Shift Engi-I neers, and Shift Foremen shall have a Senior Operator's License. The l.
fuel Handling Foreman has a limited Senior Operator's License.
The l
Vice President BWR Operations on the corporatedaral:hasmesponsibility
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for the Fire Protection Program. The'Maintenan'ce Assistant Tsperintend- ~'~l-1 ent will be responsible for implementation of the Fire Protection Program.
A fire brigade of at least 5 members shall be maintained on-site at all times.
This excludes the shift crew necessary for safe shutdown of the plant, and any personnel required for other essential functions during a fire emergency.
6.1-1 Amendment No. 117
QUAD-CITIES DPR-29 L
Ove'"ications of the station management and operating staf f, excluding tre Health Physics Services Supervisor and the Radiation / Protection and Chemistry Technicians, shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel",
dated March 8, 1971.
The Health Physics Services Supervisor or the Lead l
Health Physicist shall meet the requirements of radiation protection manager of Regulatory Guide 1.8.
The individual filling the position of Technical Superintendent shall meet the minimum acceptable level for l
" Technical Manager" as described in Section 4.2.4 of ANSI N18.1-1971.
The Shift Control Room Engineer shall have a bachelor's degree or equiva-l lent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
The Radiation / Protection Technicians shall have successfully completed I
the established Radiation / Protection Technician training program.
The Chemistry Technicians shall have successfully ' completed the established Chemistry Technician training program.
Both shall have at least a total of one year of general power plant, chemical, or radiation protection experience or equivalent training.
In addition, the Radiation / Protection Technicians shall meet the criteria for " Individuals Qualified in Radia-tion Protection Procedures", as described in the D.L. Ziemann (NRC) letter to R. L. Bolger (CECO.) dated March 15, 1977.
The Radiation /
Protection or Chemistry Technician training programs consists of the l
following:
1.
Satisfactory completion of an academic program.
Topics of these l
courses include mathematics, nuclear physics, radioactive decay, chemistry, sampling techniques, reactor coolant parameters, radia-tion exposure, shielding, biological effects of radiation exposure,,
radiation survey techniques, personnel monitoring, and emergency procedures, as appropriate for their area.
I 2.
Satisfactory performance on a comprehensive examination following completion of academic training.
3.
On-Shift training under the supervision of a qualified Radiation /
Protection or Chemistry Technician.
I E.
Retraining and replacement training of Station perssnnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971.
A training program for the fire brigade shall be-maintained under the direction of the Station Fire Marshal and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975 except that training sessions shall be at least quarterly.
F.
Retraining for licensed operators, senior operators, and senior operators (limited) shall be conducted at intervals not exceeding 2 years.
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6.1-2 Amendment No. 117
1 QUAD-CITIES DPR-29 I
i G.
lne Review and Investigative Function and the Audit Function of activ-ities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below:
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1.
Tne Superintendent of the Offsite Review and Investigative Function l
shall be appointed by the Manager of Quality Assurance / Nuclear Safety-(QA/NS).
The Corporate Audit Function shall be the respon-sibility of the Manager of QA/NS and shall be independent of operations.
The Manager of QA/NS reports directly to the Chief Executive Officer and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety.
Policy is promul-gated through a central policy committee directed by the Manager of i
QA/NS.
The Manager of QA/NS has the responsibility for the perform-ance of periodic audits of each nuclear station and corporate departments to determine that QA/NS policy is being carried out.
a.
Offsite Review and Investigative Function The Superintendent of the Offsite Review and Investigative I
function shall:
(1) provide directions for the review and investigative function and appoint a senior participant to provide appropriate direction, (2) select each participant i
for this function, (3) select a complement of more than one participant who collectively possess background and qualifica-tions in the subject matter under review to provide comprehen-sive interdisciplinary review coverage under this function, (4) independently review and approve the findings and recom-mendations developed by personnel performing the review and investigative function, (5) approve and report-in a-timely manner all findings of noncompliance with NRC requirements to the Station Manager, Vice President BWR Operations, Manager of QA/NS, Assistant Vice President (AVP) Quality Programs and Assessment, and the Senior Vice President-Nuclear Operations.
During periods when the Superintendent of Offsite Review and Investigative Function is unavailable, he shall designate l
this responsibility to an established alternate, who satisfies the formal training and experience requirements for the Superin-tendent of the Offsite Review and Investigative Fundtion.
The responsibilities of the personnel performing this function are stated below.
The Offsite Review and Investigative Function shall review:
l (1) The safety evaluations for (1) changes to procedures, equipment, or systems as described in the safety analysis report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.
Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of QA/NS.
l-6.1-3 Amendment No. 117 L_________-___---____--__
s-QUAD-CITIES-DPR-29 (2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
(3) Proposed tests or experiments which involve an unreviewed safety question defined in 10 CFR 50.59.
(4) Proposed changes in Technical Specification NRC operating licenses.
(5) Noncompliance with NRC requirements, or of internal procedures, or instructions causing nuclear safety-significance.
(6) Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.
(7) Reportable events.
(E) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.
(9) Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change.
(10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Vice President BWR Operations, and AVP Quality Programs and Assessment.
b.
Station Audit Function l
The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of BWR Opera-tions.
Such responsibility is delegated to the Nuclear Quality Programs Manager.
The Nuclear Quality Programs Manager shall approve the audit l
agenda and checklists, the findings and the report of each audit. Audits shall be performed in accordance with the m
Company Quality Assurance Program and Procedures. Audits shall be performed to assure that safety-related functions are covered within a period of 2 years or less as designated below.
(1) Audit of the conformance of facility operation to provi-sions contained within the Technical Specifications and applicable license conditions at least once per year.
6.1-4 Amendment No. 117 l
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QUAD-CITIES DPR-29 (2) Audit of the adherence to procedures, training and qualification of the station staff at least once per year.
(3) Audit of the results of actions taken to correct defi-ciencies occurring in facility equipment, structures, systeas, or methods of operation that affect nuclear safety at least once per 6 months.
(4) Audit of the performance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B" 10 CFR 50.
(5) Audit of the Facility Emergency Plan and implementing procedures at least once per year.
(6) Audit of the Facility Security Plan and implementing procedures at least once per year.
(7) Audit onsite and offsite reviews.
(8) Audit the Facility Fire Protection Program and implement-ing procedures at least once per 24 months.
(9) The radiological environmental monitoring program and the results thereof at least once per 12 months.
(10) The ODCM and implementing procedures at least once per 24 months.
(11) The PCP and implementing procedures for solidification of radioactive waste at least once per 24 months.
(12) Report all findings of noncompliance with NRC requirements and recommendations and results of each audit to the i
Station Manager, Manager of QA/NS, AVP. Quality Programs and Assessment, Vice President BWR Operations, the Senior Vice President-Nuclear Operations, and the Cnief Operating Officer.
c.
Authority i
The Manager of QA/NS reports to the Chief Executive Officer, i
The Manager of QA/NS has the authority to order unit shutdown 1
or request any other action which he deems necessary to avoid unsafe plant conditions.
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6.1-5 Amendment No. 117 l;.
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1 QUAD-CITIES DPR-29 The AVP Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations.
The AVP Quality Programs and Assessment has the authority to recommend unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions. All such disagreements shall be reported immediately to the manager of QA/NS and the Chief Operating Officer.
c Records (1) Reviews, audits, and recommendations shall be documented and distributed as covered in 6.1 G.1.a and 6.1.G.1.b.
(2) Copies of documentation, reports, and correspondence shall be kept on file at the station.
e.
Procedures Written administrative procedures shall be prepared and main-tained for the offsite reviews and investigative functions described in Specifications 6.1.G.1.a.
Those procedures shall ccver the following:
(1) Content and method of submission of presentations to the Superintendent of the Offsite Review and Investigative l
Function.
(2) Use of committees and consultants.
(3) Review and approval.
(4) Detailed listing of items to be reviewed.
(5) Method of (1) appointing personnel, (2) performing reviews, investigations, (3) reporting findings and recommendations of reviews and investigations, (4) approving reports, and (5) distributing reports.
(6) Determining satisfactory completion of action required based on approved findings and recommendations reported by personnel performing the review and investigative function.
f.
Personnel 1)
The persons, including consultants, performing the review and investigative function, in addition to the Super-
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intendent of the Offsite Review and Investigative Func-tion, shall have expertise in one or more of the following 6.1-6 Amendment No. 117
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QUAD-CITIES DPR-29 disciplines as appropriate for the subject or subjects
.being' reviewed and investigated:
a) nuclear power plant technology, b) reactor operations, c) utility operations,.
d). power plant design, e) reactor engineering, f) radiological safety, g) reactor safety analysis, _
h) instrumentation and control, i) metallurgy, j) any other appropriate disciplines required by unique characteristics of the facility.
2)
Individuals performing the Review and Investigative Function shall possess a minimum formal training and experience as listed below for each discipline.
a)
Nuclear Power Plant Technology Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/or operations.
b)
Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear power plant operations.
c)
Utility Operations Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering.
d)
Power Plant Design Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or l
operation.
e)
Reactor Engineering I
' Engineering graduate or equivalent.
In addition, at least 5 years of experience in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.
f)
Radiological Safety Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.
t 6.1-7 Amendment No. 117
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QUAD-CITIES DPR-29 g)
Reactor Safety Analysis-Engineering graduate or equivalent, with at least 5 years of experience in nuclear engineering.
h)
Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instrumentation and control design and/or operation.
i)
Metallurgy Engineering graduate or equivalent with at least 5 years of experience in the metallurgical field.
3)
The Superintendent of the Offsite Review and Investigative l
Function shall have experience and training which satisfy ANSI N18.1-1971 requirements for plant managers.
2.
~ m Onsite Review and Investigative Function shall be supervised by the Station Manager.
a.
Onsite Review and Investigative Function The Station Manager shall:
(1) provide direction for the Review and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a senior participant to provide appropriate directions; (2) approve participants for this function; (3) assure that a complement of more than one participant who collectively possess background and qualifications in the subject matter under review are selected to provide comprehensive interdisciplinary review coverage under_this_ function; 44) independently review and approve the findings and recommendations developed by personnel performing the Review and Investigative Function; (5) report all findings of noncompliance with NRC requirements, and provide recommenda-tions; and (6) submit to the Offsite Review and Investigative l
Function concurrence in a timely manner, those items described in Specification 6.1.G.I.a which have been approved by the Onsite Review and Investigative Function.
The responsibilities of the Personnel performing this function are stated below:
1)
Review of (1) procedures required by Specification 6.2 and changes thereto and (2) any other proposed procedures or changes thereto as determined by the Station Manager j
to affect nuclear safety.
2)
Review of all proposed tests and experiments that affect nuclear safety.
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6.1-8 Amendment No. 117 =
QUAD-CITIES DPR-29 L
3)
Review of all proposed changes to the Technical Specificat. ions.
4)
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
5)
Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence.
l' 6)
Review of facility operations to detect potential safety hazards.
7)
Performance of special reviews and investigations and reports thereon as requested by the Superintendent of the l
Offsite Review and Investigative Function.
E)
Review of the Station Security Plan and shall submit recommended changes to the Director of Corporate Security and the AVP Quality Programs and Assessment in lieu of the distribution in accordance with 6.1.G.2.C(1).
9)
Review of the Emergency Plan and station implementing procedures and identification of recommended changes.
- 10) Review of reportable events and actions taken to prevent recurrence.
- 11) Review of any unplanned on site release of radioactive material to the environs, including the preparation and forwarding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the Vice President BWR Operations and to the Superintendent of the Offsite Review and Investigative Function.
b.
Authority The Technical Staff Supervisor is responsible to the Station Manager and shall make recommendations in;a. timely manner in i
all areas of review, investigations, and quality control phases of plant maintenance, operation, and administrative procedures relating to facility operations and shall have the authority to request the action necessary to ensure 6.1-9 Amendment No. 117
QUAD-CITIES DPR-29 compliance with rules, regulations,.and procedures when in his opinion such action is necessary.
The Station Manager shall follow such recommendations or select a course of action that is more conservative regarding safe operation of the' facility.
All such disagreements shall be reported immediately to the Vice President BWR Operations and the l~
Superintendent of the Offsite Review and Investigative Function.
c.
Records 1)
Reports, reviews,. investigations, and recommendations prepared and performed for specification 6.1.G.2.a shall be documented with copies to the Vice President BWR Operations the Superintendent of the Offsite Review and Investigative.
Function, the Station Manager, and the AVP Quality Programs and Assessment.
2)
Copies of all records and documentation shall be kept on file at the station.
d.
Procedures Written administrative procedures shall be prepared and maintained for conduct of the Onsite Review and Investigative function.
These procedures shall include the following:
1)
Content and method of submission and presentation to the Station Manager, Vice President BWR Operations, and the Superintendent of the Offsite Review and Investigative Function.
2)
Use of committees when necessary.
3)
Review and approval.
4)
Detailed listing of items to be reviewed.
I 5)
Procedures for administration of the quality control activities.
6)
Assignment of responsibilities.
e.
Personnel 1)
The personnel performing the Onsite Review and Investigative Function, in addition to the Station Manager, shall consist of persons having expertise in:
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a) nuclear power plant technology, b) reactor operations, c) reactor engineering, 6.1-10 Amendment No. 117 1
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'd) radiological safety and chemist,.
e) instrumentation and control, and f) mechanical >and' electric systems.
2)
Personnel performing the Onsite Review and Investigative function : ball meet minimum acceptable levels as described.in ANSI NiS.1 1971, Sections 4.2 and 4.4.
H.
Fire Protection Program An indep'endent fire protection and loss prevention program inspection and audit shall:be performed at least once per 12 months utilizing-
'l either qualified offsite licensee personnel or an outside fire protection firm.
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.
6.1-11 Amendment No. 117
QUAD-CITIES DPR-29 6.2 PLANT OPER;'ING DROCEDURES A.
Detailed written procedures, including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to:
1.
Normal startup, operation, and shutdown of the reactor, and other systems and components involving nuclear safety of the facility.
2.
Refueling operations.
3.
Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.
4.
Emergency conditions involving potential or actual release of radioactivity
" Generating Station Emergency Plan" and station emercency and abnormal procedures.
5.
Instrumentation operation which could have an effect on the safety c' the facility.
6.
Preventive and corrective maintenance operations which could have an effect on the safety of the facility.
7.
Surveillance and testing requirements.
8.
Tests and experiments.
9.
Procedure to ensure safe shutdown of the plant.
10.
Station Security Plan and implementation procedures.
11.
Fire Protection Program implementation.
12.
ODCM implementation.
13 PCP implementation.
14.
Working hours of the Shift Engineer, Shift Control Room Engineer, l
Shift Foreman, and the Nuclear Station Operator job classifications such that the heavy use of overtime is not routinely required.
6.2-1 Amendment No. 117
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QUAD-CITIES DPR-29
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.6.2 PLANT OFERATING PROCEDURES l
E.
Radiation control procedures shall be maintained, made available to all' station personnel, and adhered to.
The procedures shall show permissible radiation exposure and shall be consistent with the l
requirements of 10 CFR 20.
This radiation protection program shall be organized to meet the requirements of 10 CFR 20.
C.
1.
Procedures for items identified in Specification 6.2.A and 6.2.B and a y changes to such procedures shall be reviewed and approved by the i
Technical Staff Supervi n r, an Assistant Superintendent or the l
Technical Superintendent, and department head responsible for the I
activity performed. 'At least one person approving each of the above procedures shall hold a valid senior operator's license.
In addition, these procedures and changes thereto must'have authoriza-tion by the Station Manager before being implemented.
l 2.
Work and instruction type procedures which implement approved r W ienance or modification procedures shall be approved and authorized by the Maintenance Assistance Superintendent where the s ": ten authority has been provided by the Station Manager.
The
' Maintenance Modification Procedure" utilized for safety related work shall be so approved only if procedures referenced in the
" Maintenance Modification Procedure " have been approved as required by 6.2.A.
Procedures which do not fall within the requirement of 6.2. A or 6.2.B may be approved by the Department Heads.
D.
Temporary changes to procedures 6.2. A and 6.2.B above may be made provided:
1.
The intent of the original procedure is not altered.
2.
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.
3.
The change is documented, reviewed on the On-Site Review and Investigative Function, and approved by the Station Manager within 14 days of implementation.
E.
Drills of the emergency procedures described in Specification 6.'2.A shall be conducted in accordance with the GSEP manual.
l 6.2-2 Amendment No. 117 1
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r QUAD-CITIES DPR-29 E.3. REPORTABLE EVENT ACTION I
A.
The following actions shal.1 be taken for Reportable Events:
1.
The Commission shall be notified and a report submitted pursuant
-to the requirements of Section 50.73 of 10 CFR Part 50.
-2.
Each Reportable Event shall be reviewed by the On-Site Review Committee, and the results of this review shall be submitted to
.the Off-Site Review and: Investigative Function and to the Vice President BWR Operations.
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.g-6.3-1 Amendment No. 117 -_
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i QUAD-CITIES DPR-29 l
6.4 ACTJON TO EE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED If a safet limit is exceeded, the reactor shall be shut dawn immediately, and reactor operation shall not be resumed until authorized by the NRC.
The conditions of shutdown shall be promptly reported to the Vice President BWR Operations or his designated alternate. The incident shall be reviewed pursuant to Specifications 6.1.G.I.a and 6.1.G.2.a and a separate report for each occurrence shall be prepared in accordance with Specification 6.3.A.I.
u 6.4-1 Amendment No. 117 ~~
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c, UNITED STATES j,
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D C. 20555 L.....',
COMMONWEALTH ED150h COMPAflY AND 10WA-ILLINDIS GAS AND ELECTRIC COMPANY DOCKET NO. 50-265 QUAD CITIES NUCLEAR POWER STATION, UNIT 2 AMENDHENT TO FACILITY OPERATING LICENSE Amendment No.113 License No. DPR-30 5
1.
The Nuclear Regulatory Concission (the Comission) has found that:
A.
The application for amendment by Commonwealth Edison Company (tbe licersee) dated February 21, 1989, complies with the standards anc requireraents of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFF. Chapter I; E.
The facility will operate in conformity with the application,
.the provisions of the Act, and the rules and regulations of the Commission; C.
Thereisreasonableassurance(i)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the commen defense and security or to the health and safety of the public; and j
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements j
have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, I
and paragraph 3.B. of Facility Operating License No. DPR-30 is i
hereby amended to read as follows:
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- e. eke.
.. E.
Technical Specifications The Technical Specific 6tions contained in Appendices A and B, as revised through Amendment No.113, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Muller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: April 26, 1989 l
l l.
ATTACHMENT TO LICENSE A!!ENDMENT N0.113 FACILITY OPERATING LICENSE NO. DPR-30 DOCKET NO. 50-265 R: vise the Appendix A Technical Specifications hy removing the pages identified telow and inserting the attached pages. The revised pages are 1
identified by the captioned amendment number and contain marginal lines indicating the erec of change.
REMOVE INSERT vi vi 6.1-1 6.1-1 6.1-2 6.1-2 C.! -
6.1-3 6.1-4 6.1-4 6.1-5 6.1-5 6.1-6 6.1-6 6.1-7 6.1-7 6.1-8 6.1-8 6.1-9 6.1-9 6.1-10 6.1-10 6.1-11 6.1-11 Figure 6.1-1 Figure 6.1-2 6.2-1 6.2-1 6.2-2 6.2-2 =..
6.3-1 6.3-1 6.4-1 6.4-1
~
QUAD-CITIES DPR-30 TECHNICAL SPECIFICATIONS APPENDIX A LIST OF FIGURES Number Titic 2.1-1 APRi4 Flow Reference Scram and APRM Rod Block Settings -
2.1-2 Deleted 2.1-3 AFRM Flow Bias Scram Relationship to Normal Operating Conditions l
4.1-1 Graphical Aid in the 1, election of and Adequate Interval Between Tests
'4.2-1 Test Interval vs. System Unavailability 3.4-1 Deleted 3.4-2 Sodiu~. Pentaborate Solution Temperature Requirements 3.5-1 Maximu-Average Planar Linear Heat Generation Rate (MAPLHGR) vs. Planar Average Exposure 3.5-2 Y. facter 3.0-1 Minim r Temperature Requirements per Appendix G of 10 CFR~50 4.6-1 Chloride Stress Cerrosion Test Results at 5000F 4.8-1 Locations of Fixed Environmental Radiological Monitoring Stress 6.1-1 Delete:
6.1-2 Deleted 6.1-3 Minimum Shift Manning Chart Amendment No.113 vi
QUAD-CITIES DPR-30 6.0 ADMINISTRATIVE CONTROLS CFGAN!:A!!DN, REVIEW, INVESTIGATION, AND AUDIT A.
cnsite end offsite organizations shall be established for unit cperation and corporate management, respectively. The onsite and offrite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
2.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and incleding all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent f orms of documentation. These requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organization Authority, Activities: Section 6 Interdepartmental Relationships.
2.
The Station Manager shall be responsible for overall unit safe eperation and shall have control over those onsite activities necessary f or saf e operation and maintenance of the plant.
2.
The Senior Vice President-Nuclear Operations shall have the 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.
4.
The individuals who train the operating staff and those who carry out health physics and, quality assurance functions may report to the appropriate onsite managers howcVer, they shall have sufficient organizational freedom to ensure their indspondence from operating pressures.
B.
DELETED.
C.
The shif t manning for the station shall be as shown in Figure 6.1-3.
The Operating Assistant Superintendent, Operating Engineer, Shift l
Engineers, and Shif t Foremen shall have a Senior Operator's License.
The Tuel Handling Toreman has a limited Senior Operator's License. The Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program. The Maintenance Assistant Superintendent will be responsible for implementation of the Fire Protection Program.
A fire brigade of at least 5 members shall be j
maintained on-site at all times. This excludes - the -shif t. crew necessary for safe shutdown of the plant, and any personnel required for other essential functions during a fire emergency.
1512B 6.1-1 Amendment No.
113
)
QUAD-CfTIES DPR-30 l
P.
C'4 2 i fications of the station management and operating staf f, excludinc
)
the Health Physics Services Supervisor and the Radiation Protection and Cheristry Technicians, shall meet minimum acceptable levels as 6a s cribed in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971.
The Health Physics Services l
Supervisor or the Lead Health Physicist shall meet the requirements of radiation protection manager of Regulatory Guide 1.8.
The individual filling the position of Technical Superintendent shall meet the minimum l
I acceptable level for " Technical Manager" as described in Section 4.2.4 of ANSI N18.1-1971.
The Shift Control Room Engineer shall have a l
l bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for transients and accidents.
The Radiation Protection Technicians shall have successfully completed the established Radiation Protection Technician training program. The Chemistry Technicians shall have successfully completed the established Chemistry Technician training program.
Both shall have at least a total of one year of general power plant, chemical, or radiation protection experience, or equivalent training.
In addition, the Radiation Protection Technicians shall meet the criteria for
" Individuals Qualified in Radiation Protection Procedures", as described in the D.L.
Ziemann (NRC) letter to R.L. Bolger (CECO.) dated March 15, 1977. The Radiation Protection or Chemistry Technician l
training program consists of the following:
1.
Satisfactory completion of an academic program. Topics of these I
courses include mathematics, nuclear physics, radioactive decay, i
chemis try, sampling techniques, reactor coolant parameters, radiation exposure, shielding, biological effects of radiation exposure, radiation survey techniques, personnel monitoring, and l
emergency procedures, as appropriate to thc8.- area.
2.
Satisf actory performance on a comprehensive examination following completion of academic training.
3.
On-Shif t training under the supervision of a quellflod Radiation Protectioe or Chemistry Technician.
E.
Retraining and replacement training of Station personnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel", dated March 8, 1971.
A training program for the fire brigade shall be maintained under the direction of the Station Fire Marshal and shall meet or exceed the requirements of Section 27 of the NFPA Code-1975-esoegt;that training sessions shall be at least quarterly.
T.
Retraining for licensed operators, senior operators, and senior operators (limited) shall be conducted at intervals not exceeding 2 years.
1512B 6.1-2 Amendment No.Il
QUAD-CITIES DPR-30 The Feview and Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below 1.
The Superintendent of the Offsite Review end Investigative Function shall be appointed by the Manager of Quality Assurance / Nuclear Safety (QA/NS). The Corporate Audit Tunction shall be the responsibility of the Manager of Quality Assurance / Nuclear Safety (QA/NS) and shall be independent of operations.
The Manager of QA/NS reports directly to the Chief Executive Officer and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and Nuclear Safety.
Policy is promulgated through a central policy committee directed by the Manager of QA/NS.
The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and ccrporate departments to determine that QA/NS policy is being j
carried out.
a.
Of f site Review and Investigative Function The Superintendent of the Offsite Review and Investigative function shalls (1) provide directions for the review and 1
investigative function and appoint a senior participant to j
provide appropriate direction, (2) select each participant for this function, (3) select a complement of more than one participant who collectively possess background and l
qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (4) independently review and approve the findings l
and recommendations developed by personnel performing the review and investigative function, (5) approve and report in a timely manner all findings of noncompliance with NRC requirements to the Station Manager, Vice President BWR Operations, Manager QA/NS, Assistant Vice President ( AVP)
Quality Programs and Assessment, and the Senior Vice President of Nuclear Operations. During periods when the Superintendent of Offsite Review and Investigative Tusction is unavailable, he shall designate this responsibility to an established alternate, who satisfies the formal training and experience requirements for the Superintendent of the Offstte l
Review and Investigative Function. The responsibilities of the personnel performing this function ere stated.below. The Of f site Review and Investigative Function shall reVlew:
1512B 6.1-3 Amendment No. Il
QUAD-CITIES DPR-30
- 1) The safety evaluations for (1) changes to procedures,,
equipment, or systems as described in the safety analysis l
report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question.. Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of QA/NS, l
2)
Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
l 3)
Proposed tests or experiments which involve en unreviewed safety question defined in 10 CFR 50.59.
I 4)
Proposed changes in Technical Specification NRC operating licenses.
- 5) Noncompliance with NRC requirements, or of internal procedures, or instructions cousing nuclear safety significance.
6)
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.
7)
Reportable events.
- 8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems, or components.
9)
Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such change.
- 10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Vice President BWR Operations, and AVP Quality Programs and Assessment.
b.
Station Audit Function The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of BWR Operations.
Such responsibility is delegated to the Nuclear Quality Programs Manager.
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1513B 6.1-4 Amendment No.ll:
QUAD-CITIES DPR-30 The Nuclear Quality Programs Manager shall approve the audit
{
agenda and checklists, the findings and the report of each audit.
Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures. Audits shall be performed to assure that safety-related functions ere covered within a period of 2 years or less as designated below.
- 1) Audit of the conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per year.
- 2) Audit of the adherence to procedures, training and qualification of the station staff at least once per year.
- 3) Audit of the results of actions taken to correct defielencies occurring in facility equipment, structures, systems, or methods of operation that affect nuclear safety at least once per 6 months.
4)
Audit of the performance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B" 10 CTE 50.
5)
Audit of the racility Emergency Plan and implementing procedures at least once per year.
- 6) Audit of the racility Security Plan and implementing procedures at least once per year.
- 7) Audit onsite and offsite reviews.
- 8) Audit the racility Fire Protection Program and implementing procedures at least once per 24 months.
- 9) The radiological environmental monitoring program and the results thereof at least once per 12 months.
- 10) The ODCM and implementing procedures at least once per 24 months.
- 11) The PCP and implementing procedures for solidification of radioactive waste at least once per 24 months.
- 12) Report all findings of noncompliance with NRC
~
requirements and recommendations and results of each audit to the Station Manager, Manager of QA/NS, AVP Quality Programs and Assessment, Vice President BWR Operations, the Senior Vice President-Nuclear Operations, and the Chief Operating Officer.
1518B 6.1-5 Amendment No. Il
QUAD-Cf7IES DPR-30 Authority The Manager of QA/HS reports to the Chief Executive Officer.
{
The Manager of QA/NS has the authority to order unit shutdown l
request any other action which he deems necessary to avoid cr unsafe plant conditions.
The AVP Ouality Programs and Assessment reports to the Senior Vice President-Nuclear Operations. The AVP Quality Programs and Assessment has the authority to recommend unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions. All such disagreements shall be reported immediately to the Manager of QA/NS and the Chief Operating Officer.
d.
Records 1)
Reviews, audits, and recommendations shall be documented and distributed as covered in 6.1.G.I.a and 6.1.G.1.b.
2' Copies of documentation, reports, and correspondence shall be kept on file at the station.
e.
Procedures j
Written administrative procedures shall be prepared and maintained for the offsite reviews and investigative functions described in Specifications 6,1.G.1.a.
Those procedures shall cover the following:
- 1) Content and method of submission of presentations to the Superintendent of the Offsite Review and Investigative l
function.
- 2) Use of committeen and consultants.
- 3) Review and approval.
- 4) Detailed listing of items to be reviewed.
- 5) Method of (1) appointing personnel, (2) performing reviews, investigations, (3) reporting Lindings and recommendations of reviews and investigations, (4) approving reports, and (5) distributing reports.
- 6) Determining satisfactory completion of action required
' ~ ~
based on approved findings and recommendations reported by personnel performing the review and investigative function.
1512b 6.1-6 Amendment No.ll3 1
QUAD-CITIES DPR-30 f-Personnel
- 1) The persons, including consultants, performing the review and investigative function, in addition to the Superintendent of the Offsite Review and Investigative l
Function, shall have expertise in one or more of the following disciplines as appropriate for the subject or subjects being reviewed and investigated a) nuclear power plant technology, b) reactor operations, c) utility operations, d) power plant design, e) reactor engineering, f) radiological safety, 9) reactor safety analysis, h) instrumentation and control,
- 1) methilurgy,.
j) any other appropriate disciplines required by unique characteristics of the facility.-
2)
Individuals performing the Review and Investigative runction shall possess a minimum formal training and experience as listed below for each discipline.
a) Huclear Power Plant Technology Engineering graduete or equivalent with 5 years experience in the nuclear power field design and/or j
operations.
b)
Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear power plant operations.
c) Utility Operations l
Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering.
d)
Power Plant Design l
Engineering graduate or equivalent wit.h at least 5 l
years of experience in power plant design and/or operation.
l e)
Reactor Engineering Engineering graduate or equivalent.
In addition, at least 5 years of experience in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.
Amendment No.#241 1513B 6.1-7
QUAD-CITIES DPR-30 f) Radiological Safety l
Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.
g)
Reactor Safety Analysis Engineering graduate or equivalent, with at least 5 years of experience in nuclear engineering.
h)
Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instrumentation and control design and/or operation.
- 1) Metallurgy Engineering graduate or equivalent with at least 5 years of experience in the metallurgical field.
- 3) The Superintendent of the Offsite Review and l
Investigative Function shall have experience and training which satisfy ANSI N18.1-1971 requirements for plant managers.
2.
The Onsite Review and Investigative Function shall be supervised by the Station Manager.
a.
Onsite Review and Investigative Function l
The Station Manager shall:
(1) provide -direction for the Review and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a senior participant to provide appropriate directions; (2) l approve participants for this functions (3) assure that a complement of more than one participant who" collectively possess background and qualifications in the subject matter l
under review are selected to provide comprehensive interdisciplinary review coverage under this' functions (4)
Independently review and approve the findings and recommendations developed by personnel performing the Review and Investigative Functions (5) report all findings of noncompliance with NRC requirements, and provide recommendations; and (6) submit to the Offsite Review and Investigative Tnnetion concurrence in a timely manner, those items described in Specification 6.1.G.1.s which have been approved by the Onsite Review and Investigative Function.
The responsibilities of the personnel performing this function are stated below:
1513B-6.1-8 Amendment No.113
QUAD-CIT 2ES DPR-30 1)
Peview of (1) procedures required by Specification 6.2 and changes thereto and (2) any other proposed procedures changes thereto as determined by the Station Manager or to affect nuclear safety.
2)
Review of all proposed tests and experiments that affect nuclear safety.
3)
Peview of all proposed changes to the Technical Specifications.
4)
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
5)
Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence.
6)
Review of facility operations to detect potential safety hazards.
7)
Performance of special reviews and investigations and reports thereon as requested by the Superint.endent of the Offsite Review and Investigative Function.
8)
Review of the Station Security Plan and shall submit recommended changes to the Director of Corporate Security and the AVP Quality Programs and Assessment in lieu of distribution in accordance with 6.1.G.2.c.(1).
9)
Review of the Emergency Plan and station implementing p r o c,v, t ur. : and identification of recommended changes.
- 10) Review of reportable events and actions taken to prevent recurrence.
- 11) Review of any unplanned on-site release of radioactive material to the environs, including the preparation and forwarding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the Vice President BWR Operations, and to the Superintendent of the Offsite Review and Investigative function.
1512B 6.1-9 Amendment No. Il I
QUAD-CITIES DPR-30 1.
Authority The Technical Staff Supervisor is responsible to the Station Manager and shall make recommendations in a timely manner in all areas of review, investigations, and quality control l
phases of plant maintenance, operation, and administrative procedures relating to facility operations and shall have the authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary. The Station Manager shall follow such recommendations or select a course of action that is more conservative regarding safe operation of the facility.
All such disagreements shall be reported immediately to the Vice President BWR Dperations and the Superintendent of the Offsite Review and Investigative Tunction.
c.
Records 1)
Reports, reviews, investigations, and recommendations prepared and performed for Specification 6.1.G.2.a.
shall be documented with copies to the Vice President BWR Operations, the Superintendent of the Offsite Review and Investigative Function, the Station Manager, and the AVP Quality Programs and Assessment.
- 2) Copies of all records and documentation shall be kept on file at the station.
d.
Procedures
{
Written administn11v6 p;ocedures shall be prepared and maintained for conduct of the Onsite Review and investigative function. These procedures shall include the following:
1)
Content and method of submission and presentation to the Station Manager, Vice President BWR Operations, and the Superintendent of the Offsite Review and Investigative function.
- 2) Use of committees when necessary.
3)
Review and approval.
- 4) Detailed listing of items to be reviewed.
- 5) Procedures for administration of the quality control activities.
}
- 6) Assignment of responsibilities.
e.
Personnel 1512B 6.1-10 Amendment No. 32
i:
GUAD-CITIES DPR-30 l
l
- 1).The personnel Performing the Onsite Review and Investigative Function, in addition to the Station Manager. shall consist of Persons having expertise' int a) nuclear power plant technology, b) reactor operations, c) reactor engineering, d) radiological safety and chemist, e) instrumentation and control,.and f) mechanical and electric systems.
1
- 2) Fersonnel performing the Onsite Review and Investigative function shall meet minimum acceptable levels as described in ANSI N18.1 1971, Sections 4.2 and 4.4.
H.
Fire Protection Program An independent fire protection and loss prevention program inspection end audit shall be performed at least once per 12 months utilizing either qualified offsite licensee personnel or an outside fire protection firm.
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 anonths.
1512B 6.1-11 Amendment No.Il2 2.:.
QUAD-CITIES DPR-30 F L L ** ^ r r r :7Jg, FF00EDUFES A.
Leta;;ed written procedures, including applicable checkoff lists covering items listed below shall be prepared, approved, and adhetad to Normal sta:Lup, operation, and shutdown of the reactor, and other systems and components involving nuclear safety of the facility.
2.
Befueling operations.
3.
Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.
4.
Emeroeney conditions invoJving potential or actual release of radioactivity
" Generating Station Emergency Plan" and station emergency and abnormal procedures.
5.
Instrumentation operation which could have an ef fect on the safety ef the facility.
rreventive and corrective maintenance operations which could have an effect on the safety of the facility.
Surveillance and testing requirements.
8.
Tests and experiments.
9.
Procedure to ensure safe shutdown of the plant.
10.
Station Security Plan and implementation procedures.
11.
Fire Protection Program implementation.
12.
ODCM implementation.
13.
FCP implementation.
14.
Working hours of the Shift Engineer, Shift Control Room Engineer, l
Shift Foreman and the Nuclear Station Operator job classifications such that the heavy use of overtime is not routinely required.
15A3B/
6.2-1 Ame n d'a' n' ]y3
QUAD-CITIES DPR-30 t.1 FLAST W EFATING PROCEDUPES 5.
Radiation control procedures shall be maintained, made available to all station persennel, and adhered to.
The procedures shall show permissible radletion exposure and shall be consistent with the j
requirements of 10 CFR 20.
This radiation protection program shall be organi:ed t meet the requirements of 10 CFR 20.
1.
Treceistes for items identified in Specification 6.2.A and 6.2.B and any changes to such procedures shall be reviewed and approved by the Technical Staff Supervisor, an Assistant Superintendent or Technical Superintendent, and department head responsible for the
)
activity performed. At least one person approving each of the above procedures shall hold a valid senior operator's license.
In addition, these procedures and changes thereto must have authorization by the Station Manager before being implemented.
2.
Work and instruction type procedures which implement approved maintenance or modification procedures shall be approved and esthorized by the Maintenance Assistant Superintendent where the written authority has been provided by the Station Manager. The
" Maintenance Modification Procedure" utilised for safety related work shall be so approved only if procedures referenced in the
" Maintenance Modification Procedure have been approved as required by 6.2.A.
Procedures which do not fall within the requirement of 6.2.A or 6.2.B may be approved by the Department Heads.
D.
Temporary changes to procedures 6.2.A and 6.2.B above may be made provided:
1.
The intent of the original procedure is not altered.
2.
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.
3.
The change is documented, reviewed on the On-Site Review and Investigative function, and approved by the Station Manager within 14 days of implementation.
E.
Drills of the emergency procedures described in Specification 6.2.A l
shall be conducted in accordance with the GSEP manual.
l 1513B/
6.2-2 AP'"d**"t }"T3
.-________________---_-__a
i-QUAD-CITIES DFP-30 FETC 7AELE E*/ENT A;; ION A.
The following actions shall be taken for Reportable Events:
1.
The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50.
2.
Eact Reportable Event shall be reviewed by the On-Site Review Committee, and the results of thir. review shall be submitted to the OfI-Site Review and Investigative function and to the Vice i
President BWR Operations, i
I l
l 1514B 6.3-1 e'u'"' n4** n ' 11"3 -
l' 1
I OUAD-CITIES DPR-30
'.J C ION TO EE TAFEN IN THE EVENT A SATETY LIMIT IS EXCEEDED' If a safety limit is exceeded, the reactor shall be shut down immediately, and Ieactor operation shall not be resumed until authorized by the NRC.
The.
conditier.s cf shutdown shall be promptly reported to the Vice President BWR Operations or his designated alternate. The Incident shall be reviewed pursuant ~ to Specifications 6.1.G.I.a and 6.1.G.2.a and a separate report for eacn occurrer.ce shall be prepared in accordance with Specification 6.3.A.1.
l 2515B 6.4 1 Amevhner?q8"
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'g UNITED STATES NUCLE AR REGUL ATORY COMMISSION
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COMMONWEALTH EDISON COMPAfiY DOCKET NO. 50-237 ETESDEh i1UCLEAR POWER STATION, UNIT 2 AMENDMENT TO PROVIS10ftAL OPERATING LICENSE Amendment No.105 License No. DPR-19 1.
The huclear Regulatory Comn.ission (the Comission) has40und that:
A.
The application for amendment by the Commonwealth Edison Company (the licenstt) dated February 17, 1989 and supplemented March 20, 1969 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and reguistions set forth in 10 CFR Chapter I; B.
The fecility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorfzed I
by this amer.cnent can be conducted without endangering the het.ith and safety of the public, and (ii) that such activities-will be conducted in compliance with the Comission's regulations; l
D.
The issuance of this amendment will not be inimical to the comnon l
defense and security or to the health ano safety of the pblic; and E.
The issuance of this amendnent is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 3.0. of Provisional Operating License No. DPR-19 is hereby amended to read as follows:
l l
.. =
l l
L l
2-5.
Technical Specifications l
The Technical Specifications contained in Appendix A, as revised through Amendment No.105, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of tie date of its issuance.
FOR THE' NUCLEAR REGULATORY COMMISSION J A.??/ 8 Daniel R. Muller, Direct',
Project Directorate III.
Division of Reactor Pro.iects - III IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuar.ce: April 26,1989 i
L.
l ATTACHMENT TO LICENSE AMENDMENT NO.105 PROVISIONAL OPERATING LICENSE DPR-19 DOCKET NO. 50-237 Revise the Appencix A Technical Specifications by reinoving the pages identified below anc inser* ir.g the attached pages. The revised pages are identified by the captioned amendment number and_ contain marginal lines indicating the area of change.
REMOVE INSERT vi vi vil vii viii viii C-1 6-1 l-L 6-2 f-3(Figure 6.1-1}
t-2 ; figure 6.1-2j 6-5 6-4 6-C 6-3 6-7 6-5 6-8 6-6 6-9 6-7 6-10 6-8 6-11 6-9 6-12 6-10 6-13 6-11 6-14 6-12 6-15 6-13 6-16 6-14 6-17 6-15 6-18 6-16 6-19 6-17 6-20 6-18 6-21 6-19 i
6-22 6-20 l
6-23 6-21 1
6-24 6-22 6-25 6-23 6-26 6-2t., 25 I
i
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r
=c t
1 x.
DRESDEN II DPR-19 Amendment No. 82, 83, 86, 105 (Table of Contents. Cont'd.)
E.BM
_.9'
. Auxiliary Electrical Systems 3/4.9 - 1 4
4.9.A Station Batteries 3/4.9 - 1
' 4.9.B
'(N/A) 4.5.C Diesei fuel 3/4.9 - 4
- 4. 9. D Diesel Generator Operability 3/4.9 - 4 4.10 Refueling-3/4.10- 1 4.10.A Refueling Interlocks 3/4.10- 1 4.10.8 Core Monitoring 3/4.10- 1
-4.10.C Fuel Storage' Pool Water Level 3/4.10- 2 4.10.0 Control Rod Drive and Control Rod Drive Maintenance 3/4.10- 3 4.10.E. Extended Core Maintenance 3/4.10- 4 4.10.F Spent Fuel Cask Handling 3/4.10- 5 4.11 High Energy Piping Integrity 3/4.11-1 4.12 Fire Protection Systems 3/4.12-1 4.12.A Fire Detection Instrumentation 3/4.12-1 4:12.B Fire Suppression Water System 3/4.12-2 4.12.C. Sprinkler Systems 3/4.12-5 4.12.D C0 System 3/4.12-7 7
4.12.E Fire Hose Stations 3/4.12-8 4.12.F Penetration Fire Barriers 3/4.12-9
-4.12.G Fire Pump Diesel Engine 3/4.12-10 4.12.H lialon System 3/A.12-13 5.0 Design features 5-1 5.1 Site 5-1 5'2.
Reactor 5-1 5.3 Reactor Vessel 5-1 5.4 Containment 5-1 5.5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1 6.'
Organization, Review, Investigation and Audit 6-1 6.2 Plant Operating Procedures 6-13 6.3 Actions to be taken in the Event of A Reportable Occurrence in Plant Operation 6-15 6.4 Action to be taken in the Event a Safety Limit is Exceeded 6-15 6.5 Plant Operating Records 6-15 6.6 Reporting Requirements 6-17 6.7' Environmental Qualification
~6 - 21 6.8 Offsite Dose Calculation Manual (ODCM) 6-21 6.9~
Process Control Program (PCP) 6-23 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) 6-24 vi AMEND"ENT NO. 105 i
_______m_
DRESDEN II DPR-19 Amendment No. 84, 85, 86, 90, 105 List of Tables
.P_aBe Table 3,1,1 Reactor Protection System (Scram) 3/4.1 - 5 Instrumentation Requirements Table 4.2.1-Scram Instrumentation Functional Tests 3/4.1 - 8 Table 4.1.2 Scram Instrumentation Calibration 3/4.1 -10 Table 3.2.1 Instrumentation that Initiates Primary Containment Isolation Functions 3/4.2 - 8 Table'3.2.2 Instrumentation that Initiates or Controls the Core and Containment Cooling System 3/4.2 -10 Table 3.2.3 Instrumentation that Initiates Rod Block 3/4.2 -12 Table 3.2.4 Radioactive Liquid Effluent Monitoring Instrumentation 3/4.2 -14 Table 3.2.5 Radioactive Gaseous Effluent Monitoring Instrumentation 3/4.2 -15 Table 3.2.r Post Accident Monitoring Instrumentation Requirements 3/4.2 -17 Tu t 4.2.1 Mininx Test and Calibration Frequency for Core and Containment Cooling Systems Instrumentation, Rod Blocks, and Isolations 3/4.2 -19 Table 4.2.2 Radioactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2 -22
. Table 4.2.3 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2 -24 Table 4.2.4 Post Accident Monitoring Instrumentation Surveillance Requirements 3/4.2 -26 Table 4.6.2 Neutron Flux and Sample Withdrawal B 3/4.6-26 Table 3.7.1 Primary Containment Isolation 3/4.7 -31 Table 4.8.1 Radioactive Gaseous Waste Sampling and Analysis Program 3/4.8-22 Tsble 4.8.2 Maximum Permissible Concentration of Dissolved or Entrained Noble Gases Released From the Site to Unrestricted Areas in Liquid Waste 3/4.8-24 Table 4.8.3 Radioactive Liquid Waste Sampling and Analysis Program 3/4.8-25 l
Table 4.8.4 Radiological Environmental Monitoring Program 3/4.8-27
-Table 4.8.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3/4.8-28 Table 4.8.6 Practical Lower Limits of Detection (LLD) for Standard Radiological Environmental Monitoring Program 3/4.8-29
. Table 4.11-1 Surveillance Requirements for High Energy Piping Outside Containment 3/4.11-3 l
Table 3.12-1 Fire Detection Instruments B 3/4.12-17 l
Tcble 3.12-2 Sprinkler Systems B 3/4.12-18 Tcble 3.12-3 C0 Systems B 3/4.12-19 Table 3.12-4 FifeHoseStations B 3/4.12-20 & 21 Table 6.1.1 Minimum Shift Manning Chart 6-4 Table 6.6.1 Special Reports 6-22 vii AMENDMENT NO. 105
I DRESDEN II DPR-19 Amendment No. 83, 84, 86, 90, 95 97, 104, 105 List of Figures
.5 Figure.2.1-3 APFsM Bias Scram Relationship to Normal Operating Conditions B 1/2.1-17 Figure 4.1.1 Graphical' Aid in the Selection of an Adequate Interval Between Tests B 3/4.1-18 Figure 4.2.2 Test Interval vs. System Unavailability B 3/4.2-38 Figure 3.4.1 Standby Liquid Control Solution Requirements 3/4.4-4 Figure 3.4.2-Sodium Pentaborate Solution Temperature Requirements 3/4.4-5 Figure 3.5-1 MAPLHGR Limit vs Bundle Average Exposure ANF 8x8 Fuel (Sheet 1 of 3) 3/4.5-18 Figure 3 E '.
MAPLH2 -Limit vs Bundle Average Exposure ANF 9x9 Fuel (Sheet 2 of 3) 3/4.5-19 Figure 3.5-1 MAR.HGR Limit vs Average Planar Exposure GE 8x8 LTAs (Sheet 3 of 3) 3/4.5-20 Figure 3.5-1A Sleady State Linear Heat Generation Rate vs Nodal Exposure 3/4.5-21 Figure 3.5-1B Transient Linear Heat Generation Rate vs Nodal Exposure for all ANF Fuel 3/4.5-22 Figure 3.5-2 MCPR Limit for Reduced Total Core Flow (Sheet 1 of 2) 3/4.5-25
-Figure 3.5-2 MCPR Operating Limit for Automatic Flow Control (Sheet 2 of 2) 3/4.5-26 Figure 3.6.1 Minimum Temperature Requirements per Appendix G of 10 CFR 50 3/4.5-23 Figure 3.6.2 Thermal Power vs Core Flow Limits for Thermal Hydraulic Stability Surveillance in Single Loop Operating 3/4.6-24 Figure 4.6.1 Minimum Reactor Pressurization Temperature B 3/4.-6 l Figure 4.6.2 Chloride Stress Corrosion Test Results at 500 F B 3/4.6-31 Figure 4.8.1 Owner Controlled / Unrestricted Area Boundary B 3/4.8-38 l
Figure 4.8.2 Detail of Central Complex B 3/4.8-39 Figure 6.1-1 Offsite Organization - Deleted Figure 6.1-2 Station Organization - Deleted viii AMENDMENT NO. 105
)
0 DRESDEN II DPR-19
. Amendment No. 82, 86, 97, 105 6.0 ADM]NISTRATIVE CONTROLS 6.1 C~ ?tization. Review, Investigation and Audit A.
Onsite and offsite organizations shall t,e established for the unit operation and corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
1.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through the 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 department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation.
The requirements
- 1 ' be documented in the Quality Assurance Manual Manual or the Management Plan for Nuclear Operc'. ions, Section 3 Organiza-tic T Authority, Activity; Section 6 Interdepartmental Relationships.
2.
The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of plant.
3.
The Senior Vice President-Nuclear Operations shall have the 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.
4.
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 operational pressures.
B.
DELETED C.
The shift manning for the station shall be as shown in Table 6.1.1.
The Operating Assistant Superintendent, Operating Engineers, Shift Engineers, and Shift Foremen shall have a Senior Operating License.
The Fuel Handling Foreman shall have a limited Senior Operating License.
The Vice President BWR Operations on the corporate level i
has responsibility for the Fire Protection Program.r An 0 pes ting 1
Engineer at the station will be responsible for implementation of the Fire Protection Program.
A fire brigade of at least 5 members shall be maintained on site at all times.
This excludes the shift crew necessary for safe shutdown of the plant and any personnel required for essential functions during a fire emergency.
6-1 AMENDMENT NO. 105
1 DRESDEN II DPR-19 Amendment No. 82, 86, 97, 105
- 6. 0 ADMINISTRATIVE CONTROLS (Cont'd.)
D.
Qualifications of the station management and operating staff shall meet minimum acceptable levels as described in ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971, with the exception of the Health Physics Services Supervisor who shall l
rest or exceed the qualifications of Radiation Protection Manager of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor I
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 for transients and accidents.
The individual filling the position of Technical Superintendent shall meet l
the minimum acceptable level for " Technical Manager" as described in 4.2.4 of ANSI N18.1 - 1971.
E.
Retraining and replacement training of Station personnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Pi n Personnel," dated March 8, 1971.
A t ' -.ing program for the fire brigade shall be maintained unaer the direction of the Operating Engineer and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1975, except for fire brigade training sessions which shall be held at least quarterly.
F.
Retraining shall be conducted at intervals not exceeding two years.
G.
The Review and Investigative Function and the Audit-function of activities affecting quality during facility operations 4
shall be constituted and have the responsibilities and authorities outlined below:
1 1.
The Superintendent of the Off-site Review and Investigative Function shall be appointed by the Manager of Quality Assurance /
Nuclear Safety (QA/NS).
The Corporate Audit Function shall be the responsibility of the Manager of QA/NS and shall be independent of operations.
The Manager of QA/NS reports directly to the Chief Executive Officer and has the responsibility to set Corporate Policy for both the areas of Quality Assurance and i
l Nuclear Safety.
Policy is promulgated through A central policy t
committee directed by the Manager of QA/NS.
The-Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate department to determine that QA/NS policy is being carried out.
d.
Off-site Review and Investigative Function The Superintendent of the Off-site Review and Investigative l
Function shall:
(i) provide directions for the review 6-2 AME!!DMENT t:0.105 iw__-_________-_________---
l 1
DRESDEN II DPR-19 Amendment No. 82, 86, 97, 105
. 6. 0 ADMINISTRATIVE CONTROLS (Cont'd.)
and investigative function and appoint a senior participant to provide appropriate direction, (ii) select each participant for this function, (iii) w.ect a complement of more than one participant who cc11ectively possess background and qualifications in the subject matter under review to provide compre-hensive interdisciplinary review coverage under this function, (iv) independently review and approve the findings and recommendations developed by personnel performing the review and investigative function, (v) approve and report in a timely manner all findings of noncompliance with NRC requirements and provide recommendations to the Station Manager;-Vice President BWR y Operations, Manager of QA/NS, Assistant Vice President (AVP) Quality Programs and Assessment, and the Senior Vice President Nuclear Operations.
During periods when the Superintendent of the Off-site Review and Investigative t
Function is unavailable, he shall designate this respon-l sibility to an established alternate who satisfies the formal training and experience requirements for the Super-intendent of the Off-site Review and Investigative Function.
The responsibilities of the personnel performing this function are stated below.
The Off-site Review and i
Investigative Function shall review:
(1) The safety evaluations for 1) changes:to procedures, equipment or systems as described in the safety analysis report and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that l
such actions did not constitute unreviewed safety questions.
Proposed changes to the Quelity Assurance Program description shall be reviewed and approved by the Manager of QA/NS.
l (2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
l (3) Proposed tests or experiments which involve-an l
unreviewed safety question as defined in 10 CFR 50.59.
j (4) Proposed changes in Technical Specifications or NRC operating licenses.
6-3 AMENDMENT NO. 105 - 9Y
___-______________________-______-_D
ORESDEN ))
DPR 19 Amendment No. 82, 86, 97, 105 TABLE 6.1.1 M]NIMUM SHIFT MANNING CHART (1)
CONDITION OF UNITS NUMBER OF MEN IN EACH POSITION 5TA or NON-RAD WITH FUEL FIRST UNIT SECOND UNIT THIRD UNIT SROI2)
I3)
MEN Colc Snutdown Cold Shutdown Cold Shutdown 1
1 0
5 1
ONE Above Cold Shutdown Cold Shutdown Cold Shutdown 2
2 1
5 1
Cold Shutdown Cold shutdown Cold shutdown 1
2 0
5 1
TWO Above Cold Shutdown Cold Shutdown Cold Shutdown 2
3 1
5 1
Above Above Cold Shutdown Cold Shutdown Cold Shutdown 2 3
1 5
1 Cold shutdown Cold Shutdown Cold Shutdown 1
3 0
5 1
THREE Above Celd Shutdown Cold Shutdown Cold Shutdown 2
4 1
5 1
Above Above Cold Shutdo-n Cold Shutdown Cold shutdown 2
4 1
5 1
At'ove Above Above Cold shutdown Cold Shutdown Cold Shutdown 2
4 1
.5 1
- Senior Reactor Operator. At least one SRO aust remain in the Control Room at all times when one or more units is above cold shutdown.
This person may, however, leave the Control Room for periods not to exceed 10 minutes, provided another SRO acts as relief operator.
The SCRE or shift Supervisor can fulfill this requirement.
- Reactor Operator (For each reactor containing fuel, one R0 will be in the Control Room at all times.)
- Station Control Room Engineer (STA with Senior Reactor Operator's License).
NON-LIC.
- Equipment Operators and Equipment Attendants.
RAD MEN
- Radiation Protection Men.
NOTE.5: (1) - Shift crew composition may be less than the einfeum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-dui shif t crew members provided immediate action is taken to restore the ahlf t cre=
composition to within the minimum requirements.
(2) - Does not include the licensed Senior Reactor Operator or Senior Reactor Operator limited to fuel handling, supervising CORE OPERATIONS.
(3) - Shall not operate units on which they are not licensed.
ADDITIONAL REQUIREMENTS A.
SR0 can be RO at controls.
B.
SRO in Control Room cannot provide relief to SR0/R0 at controls.
C.
SRO in Control Roon must be in sight of or audible range of operator at all times --
or be in audible range of annunciators.
6-4 AMENDMENT NO. 105
9
'O i
i DRESDEN II DPR-19 Amendment No. 82, 86, 97, 105
- 6. 0 ADMINISTRATIVE CONTROLS (Cont'd.)
i (5)' Noncompliance with NRC requirements, or of internal l
procedures or instructions having nuclear safety
. significance.
(6) Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the On-site Review and Investigative Function.
(7) Reportable events under 10 CFR 50.73.
(8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems or components.
(S)
Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such changes.
(10) Review and report findings and recommendations regarding all items referred by the Technical Staff Supervisor, Station Manager, Vice President BWR Operations and AVP Quality Programs and Assessment.
b.
Station Audit Function l
The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of BWR Operations.
Such responsibility is delegated to the Nuclear Quality Programs Manager.
Either of the above, or designated Corporate Staff or Supervisor approved by AVP Quality Programs and Assessment shall approve the audit agenda and checklists, the findings and the report of each audit. Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures.
Audits shall be performed to assure that safety-related functions are covered within-the period designated below:
(1) Audit of the Conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at least once per year.
6-5 AMENDMENT NO. 105 l
DRESDEN II DPR-19 Amendment No. 82, 86, 97, 105 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
(2) Audit of the adherence to procedures, training and qualification of the station staff at least once per year.
(3) Audit of the results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or methods of operation that affect nuclear safety at least once per six months.
(4) Audit of the performance of activities required by the Quality Assurance Program to meet the. Criteria of Appendix "B", 10 CFR 50.
(5) Audit of the Facility Emergency Plan and implementing procedures at least once per 12 months.
(6) Audit of the Facility Security Plan and implementing procedures at least once per 12 months.
(7) Audit on-site and off-site reviews.
(8) Audit of Facility Fire Protection Program and implementing procedures at least once per 24 months.
(9) The radiological environmental monitoring program and the results thereof at least once per 12 months.
(10) The ODCM and implementing procedures at least once per 24 months.
(11) The PCP and implementing procedures for solidifi-cation of radioactive waste at least once per 24 months.
(12) Report all findings of noncompliance with NRC requirements and recommendations and results of each audit to the Station Manager, the Stanager of l
QA/NS, the Vice President BWR Operations, AVP Quality
)
l Programs and Assessment, the Senior Vice President-Nuclear Operations and the Chief Operating Officer.
l 6-6 At1ENDMENT NO. 105 l
DRESDEN II DPR-19 Amendment No. 82,'83, 86, 97, 105
' 6.' O ADMINISTRATIVE' CONTROLS (Cont'd.)
c.
Authority The Manager of QA/NS reports to the Chief Executive Officer.
The Manager of QA/NS has the authority to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.
The AVP Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations.
The AVP Quality Programs and Assessment has the authority to recommend unit shutdown or request any other action which he deems necessary to avoid-unsafe plant conditions.
All such disagreements shall be reported immediately to the Manager of QA/NS and the Chief Operating Officer.
c.
Re:crds (1) Reviews, audits and recommendations shall be documented and distributed as covered in 6.1.G.1.a and 6.1.G.I.b.
(2) Copies of documentation, reports, and correspondence shall be kept on file at the station.
e.
Procedures i
Written administrative procedures shall be prepared and maintained for the Off-site Reviews and Investigative Functions described in Specifications 6.1.G.I.a.
These procedures shall cover the following:
l' (1) Content and method of submission of presentations to the Superintendent of the Off-site Review and Investi-gative Function.
(2) Use of committees and consultants.
(3) Review and approval.
(4) Detailed listing of items to be reviewed.
(5) Method of (a) appointing personnel, (b) performing reviews, investigations, (c) reporting findings and recommendations of reviews and investigations, (d) approving reports, and (e) distributing reports.
6-7 A'iENDMENT NO. 105 l
l
DRESDEN II DPR-19 Amendment No. 82, 83', 86, 97, 105 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
(6) Determining satisfactory completion of action required based on approved findings and recommendations reported by personnel performing the review and investigative function.
f.
Personnel (1) The persons, including consultants, performing the review and investigative function, in addition to the Superintendent of the Off-site Review l
i and Investigative Function, shall have expertise in one or more of the following disciplines as appropriate for the subject or1;ubjects-being reviewed and investigated.
(a) nuclear power plant technology (b). reactor operations (c) utility operations (d) power plant design (e) reactor engineering (f) radiological safety (g) reactor safety analysis (h) instrumentation and control (i) metallurgy (j) any other appropriate diciplines required by unique characteristics of the facility.
(2)
Individuals performing the Review and Investigative Function shall possess a minimum formal training and experience as listed below for each discipline.
(a) Nuclear Power Plant Technology Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/or operation.
(b) Reactor Operations
.=
Engineering graduate or equivalent with 5 years experience in the nuclear power plant operations.
(c) Utility Operations Engineering graduate or equivalent with at least 5 years of experience in utility operation and/or engineering.
AMEN MEU W. M 6-8
{
_____-____.____-_m._
1 DRESDEN II DPR-19 Amendment No. 82, 86, 97,
- 6. 0 A?"N:3W~T ii CONTROLS (Cont'd. )
1 (d) Power Plant Design i
Engineering graduate or equivalent with at least 5 years of experience in power plant
' design and/or operation.
(e) Reactor Engineering l
Engineering graduate or equivalent.
In addition, at least 5 years of experience in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor' physics is required.
(f) Radiological Safety Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.
(g) Safety Analysis Engineering graduate or equivalent with at least 5 years of experience in nuclear engineering.
(h) Instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instruments-tion and control design and/or operatiori.
(i) Metallurgy Engineering graduate or equivalent with at least 5 years of experience in the metallurgical field.
(3) The Superintendent of tne Off-site Review and l
Investigative Function shall have experience and l
training which satisfy ANSI N18.1 - 1971 requirements for plant managers.
2.
The On-site Review and Investigative Function shall be l
supervised by the Station Manager.
The Station Manager can l
designate this responsibility to an alternate who satisfies the ANSI N18.1 (March 8, 1971) experience requirements for~ Plant Manager 6-9 AMENDMENT NO. 105 lE
_A
DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97,_10!
6.0' ADMINISTRATIVE CONTROLS (Cont'd.)
a.
On-site Review and Investigative Function l
The Station Manager (or designee) shall:
(i) provide direction for the Review and Investigative Function and appoint the Technical Staff _ Supervisor, or other comparably qualified individual as a senior participant to provide appropriate direction; (ii) approve participants for this function; (iii) assure that a complement of more than one participant who collectively possess background and qualifications in the subject matter under review are selected to provide comprehensive inter-disciplinary l
review coverage under this_ function; (iv) independently review and approve the findings and-neceamendations developed by personnel performing the Review and Investigative Function; (v) report all findings of noncompliance with NRC requirements, and provide recommendations and (vi) submit to the Offsite Review d
and Investigative function for concurrence in a timely manner, those items described in Specification 6.1.G.I.a which have been approved by the On-site Review and l
Investigative Function.
The responsibilities of the personnel performing this function are stated below:
(1) Review of:
- 1) procedures required by Specifica-tion 6.2 and changes thereto, 2) any other pro-posed procedures or changes thereto as determined by the Station Manager (or designee) to affect nuclear safety.
(2) Review of all proposed tests and experiments that affect nuclear safety.
(3) Review of all proposed changes to the Technical Specifications.
(4) Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
(5) Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence.
(6) Review of facility operations to detect potential safety hazards.
6-10 AMENDMENT NO. 105 l
. _ _ _ =
.+
I DRESDEN II DPR-19 I
Amendment No. 82, 83, 86, 97, 105 L6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
(7) Pe'rformance of special reviews and investigations -
and reports thereon'as requested by the Superintendent o.f the Off-site Review and: Investigative Function.
(8) Review of the Station Security Plan and shall submit recommended changes to the Director of 1
Corporate Security and the AVP Quality Programs and.
Assessment in lieu of distribution in accordance with 6.1.G.2.'c.(1).
(9). Review of the Emergency Plan and station implementing procedures.and identification of recommended changes.
'(10) Review of reportable events and actions taken to' prevent recurrence.
-(13) Review of any unplanned on-site release of-radioactive material to the environs-including the preparation and forwarding of. reports covering-evaluation recommendations and disposition of the corrective action to prevent recurrence-to the Vice President BWR Operations and to the Superintendent of the Off-site Review and Investigative Function.
(12) Review of changes to the PCP and ODCM and major.
changes to the radwaste. treatment systems.
b.
Authority The Technical Staff Supervisor is responsible to the Station Manager (or designee) and shall make recommenda-tions in a timely manner in all areas of review, investiga-tion, and quality control phases of plant maintenance, operation and administrative procedures' relating to facility operations. The Technical Staff Supervisor shall have the authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary. The Station Manager (or designee) shall follow such recommendations or select a course of action that is-more conservative regarding safe operation of the facility.
All such disagreements shall be reported immediately to the Vice President 8WR Operations and the Superintendent of the Off-site Review and Investigative Function.
6-11 AMENDMENT NO. 105
'I 4
DRESDEN II' DPR-19 lC Amendment No. 82, 83, 86, 97, 105 6 0. ADMINISTRATIVE CONTROLS (Cont'd.)
c.-
Records (1) Reports, reviews, investigations, and recommendations prepared and performed for Specification 6.1.G.2.a shall be documented with copies to the Vice President BWR Operations, the Superintendent of'the Off-site Review and Investigative Function, and the AVP Quality Programs and Assessment.
(2) Copies of all records and documentation shall be kept on file at the station.
o.
Procedures Written administrative procedures shall be prepared and maintained for conduct of the On-site Review and l
Investigative Function.
These procedures shall include the following:
(1) Content and method of submission and presentation to the Station Manager (or designee), Vice president
.BWR Operations and the Superintendent of the Off-site Review and Investigative Function.
(2) Use of committees.
(3) Review and approval.
(4) Detailed listing of items to be reviewed.
(5) Procedures for administration of the quality control activities.
(6) Assignment of responsibilities, e.
Personnel (1) The personnel performing the On-site Review and l
Investigative Function, in addition to the Station Manager (or designee) 4, hall consist of
_ i.
persons having expertise in:
~
(a) nuclear power plant technology (b) reactor operations (c) reactor engineering (d) radiological safety (e) chemistry (f) instrumentation and control (g) mechanical and electric systems.
6-12
_ ______ -__ _ _-_ll__
DRESDEN II DPR-19 Amendment No. 82, 86, 97, 105 1
L 6.0' ADMl'ISTRATIVE CONTROLS (Cont'd.)
N (2) Personnel performing the On-site Review and:
l Investigative Function shall meet minimum l
acceptable levels as described in ANSI N18.1-1971, Sections 4.2 and 4.4.
H.
Fire Protection.
1.
An independent fire protection and loss prevention program inspection and audit shall be performed at least once per 12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm.
2.
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.
6.2 Plant Operatinc; Procedures A.
Detailec written procedures including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to:
1.
Normal startup, operation, and shutdown of the reactor and other systems and components involving nuclear safety of the facility.
2.
Refueling operations.
3.
Actions to be taken to correct specific and foreseen potential malfunctions of systems or components including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.
4.
Emergency conditions involving potential or actual release of radioactivity
" Generating Stations Emergency Plan" and station emergency and abnormal procedures.
5.
Instrumentation operation which could have an effect on the safety of the facility.
6.
Preventhe and corrective maintenance operations which could have an effect on the safety of the facility.
7.
Surveillance and testing requirements.
6-13 AMENDMENT NO. 105 l
DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97, 105 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
E.
Tests and experiments.
9.
Procedures to ensure safe shutdown of the plant.
K Station Security Plan and implenienting procedures.
i 11.
Fire Protection Program implementation.
12.
ODCM implementation.
13.
PCP implementation.
14.
Working hours of the Shift Engineer, Station Control Room Engineer, Shift Foreman, and Nuclear Station Oeprator job classifications such that the heavy use of overtime is not routinely required.
B.
Ra::iation control procedures shall be maintained, made available to all station personnel and adhered to.
These procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20.
This radiation protection program shall be organized to meet the requirements of 10 CFR 20.
C.
1.
Procedures for items identified in Specification 6.2.A and any changes to such procedures shall be reviewed and approved by the Operating Engineer and the Technical Staff Supervisor in the areas of operation, fuel handling, or instrument maintenance, and by the Maintenance Assistant Superintendent and Technical Staff Supervisor in the areas l
of plant maintenance and plant inspection.
Procedures for items identified in Specification 6.2.B and any changes to such procedures shall be reviewed and approved by the Health Physics Services Supervisor.
At least one person l
approving each of the above procedures shall hold a valid senior operator's license.
In addition, these procedures and changes thereto must have authorization by the Station Manager (or designee) before being implemented.
2.
Work and instruction type procedures which implement approved maintenance or modification procedures.shall-be approved and authorized by the Maintenance Ass'Istant Super-l intendent where the written authority has been provided by the Production Superintendent.
The " Maintenance / Modification Procedure" utilized for safety related work shallibe so -
approved only if procedures referenced in the
" Maintenance / Modification Procedure" have been approved as 6-14 AMENDMENT NO. 105
DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97, 105 6.0 ADMINISTRATE]VE CONTROLS (Cont'd.)
required by 6.2.A.
Procedures which do not fall within the requirements of 6.2.A or 6.2.8 may be approved by the Department Heads.
D.
Terro"ary changes to procedures 5.2.A and 6.2.B above may be mace provided:
1.
The intent of the original procedure is not altered.
?.
The change is approved by two members of the plant manage-ment staff, at least one of whom holds a Senior Reactor Operator's License on the unit affected, t
3.
The change is documented, reviewed by the On-site Review and Investigative Function and approved by the Station Manager (or
{
'enee) within 14 days of implementation.
N E.
D"lls c' the emergency procedures described in Specification E.2.A.4 shall be conducted at the frequency specified in the Generating Station Emergency Plan.
These drills will be planned so tnat during the course of the year, communication links are tested and outside agencies are contacted.
- 6. 3 Atticn to be Taken in the Event of a Reportable Event in Plant Operation Any reportable event shall be promptly reported to the Vice President BWR Operations or his designated alternate.
The incident shall be promptly reviewed pursuant to Specification 6.1.G.2.a(5) and a separate report for each reportable event shall be prepared in accordance with the requirements of Specification 6.6.B.
6.4 Action to be Taken in the Event of a Safety Limit is Exceeded If a safety limit is exceeded, the reactor shall be shut down immediately and reactor operation shall not be resumed until authorized by the NRC.
The conditions of shutdown shall be promptly reported to the Vice President BWR Operations or his designated alternate.
The incident shall be reviewed pursuant to Specification 6.1.G.1..a and 6.1.G.2.a and a separate reportdor each event shall be prepared in accordance with Specification 6.6.B.
6.5 Plant Operating Records A.
Records and/or logs relative in the following items shall be kept in a manner convenient for review and shall be retained for at least five years.
6>15 AMENDMENT NO. 105
.a DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97, 105 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
1.
Records of normal plant operation, including power levels and periods of operation at each power level.
2.
Records of principal maintenance activities, including inspectiorcand' repair, regarding principal items of equipment pertaining to nuclear safety.
3.
Records and reports of reportable and safety limit events.
4.
Records and periodic checks, inspection and/or calibrations performed to verify the Surveillance Requirements (See Section 4 of these Specifications) are being met.
All equipment failing to meet surveillance requirements and the corrective action taken shall be recorded.
5.
Reccrds cf changes made to the equipment or reviews of tests anc experiments to comply with 10 CFR 50.59.
6.
Records of radioactive shipments.
7.
Records of physic tests and other tests pertaining to nuclear safety.
6.
Records of changes to operating procedures.
9.
Shift Engineers Logs.
10.
By product material inventory records and source leak test -
results.
B.
Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the life of the plant.
1.
Substitution or replacement of principal items of equipnv9nt pertaining to nuclear safety.
2.
Changes made to the plant as it is described in the Safety Analysis Report.
1 3.
Records of new and spent fuel inventory and assembly l
histories.
4.
(Deleted) l 5.
Updated, corrected, and as-built drawings of the plant.
^" "
l 6-16
L DRESDEN II DPR-19 y
Amendment No. 82, 86, 97, 105 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
6.
Records of plant radiation and contamination surveys.
7.
Records of off-site environmental monitoring surveys.
6.
Records of radiation exposure for all plant personnel, including all contractors and visitors to the plant in accordance with 10 CFR 20.
9.
Records of radioactivity in liquid and gaseous wastes released to the environment.
10.
Records of transient or operational cycling for those components that have been designed to operate safely for a limited number of transient or operational cycles.
11.
Recorcs of individual staff members indicating qualifications, experience, training and retraining.
12.
Inservice inspections of the reactor coolant system.
13.
Minutes of meetings and results of reviews performed by the Off-site and On-site Review Functions.
I 14.
Records for Environmental Qualification which are covered under the provisions of paragraph 6.7.
6.6 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following identified reports shall be submitted to the Regional Administrator of the appropriate Regional Office of the NRC unless otherwise noted.
A.
Routine Reports 1.
Startup Report A summary report of plant startup and power _ escalation testing shall be submitted following (1) receipt of an operating license, (2) amendment to the licenseMnvolving 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 nuclearrthermal, or hydraulic performance of the plant.
The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of the operating conditions or characteristics obtained 6-17 AMENDMENT NO. 105 l
j l
DRESDEN II DPR-19 Amendment No. 82, 86, 97, 105
' 6. 0 ADMIM STRATIVE CONTROLS (Cont'd.)
during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisf actory operation shall also be described.
Any accitional specific details required in license conditions based on other commitments shall be included in this report.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of. commercial
. power operation, or (3) 9 months following initial criticality, whichever is earliest. 'If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or c r u ncement of commercial power operation), supplementary reports shall be submitted at least every three months ur.til-all three events have been completed.
2.
A tabulation shall be submitted on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work anc job functions, (See Note); e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work j
functions.
3.
Monthly Operating Report l
Routine reports of operating statistics and shutdown experiences shall be submitted on a monthly basis to the l
United States Nuclear Regulatory Commission,-Washington, DC
~
20555, with a copy to the appropriate Regional Administrator, to arrive no later than the 15th of each month following the calendar month covered by the report.
Note:
This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
6-18 AMENDMENT NO. 105
1 i
i DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97, 10!
- 6. 0 ADMINISTRATIVE CONTROLS (Cont'd.)
E.
Reportable Events-Reportable events will be submitted as required by 10CFR 50.73.
C.
Unict+ Reporting Requirements 1.
Radioactive Effluent Release Report (Semi-Annual) l A report shall be submitted to the Commission within 60 days 4
af ter January 1 and July 1 of each year specifying the quantity of each of the principal radionuclides released to unrestricted areas in liquid and gaseous effluents during the previous 6 months.
The format and content of.the report shall be in accordance with Regulatory Guide 1.21 (Revision 1) dated June 1974.
Any changes to the PCP shall be included in this report.
2.
En.ircnmental Radioactivity Data (Annual Report) a.
Standard Radiological Monitoring Program (1) Non-Routine Report (a) If a confirmed measured radionuclides concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level given in Table 4.8-1 and if the radioactivity is attributable to plant operation, a written report shall be submitted to the Regional Administrator of the NRC Regional Office, with a copy of the Director, Office of Nuclear Reactor Regulation, within 30 days from the end of the quarter. When more than one of the radionuclides in Table 4.8-1 are detected in the medium, the reporting level shall have been exceeded if IC /(RL)$
is equal to or greater than I g
th where C is the concentration of the i radionuclides in the medium and RL is the reporting level of radionuclides 1.
(b) If radionuclides other than those in Table 4.8-1 are detected and are due to plant effluents, a reporting level is exceeded if the potential annual dose to an individual is 6-19 AMENDMENT NO. 105 l
DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97, 105 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
equal to or greater than the design objective doses of 10 CFR 50, Appendix 1.
(c) This report shall include an evaluation of any release conditions, environmental factors, or other aspects necessary to explain the anomalous effect.
(2) Annual Operating Report An annual report containing the data taken in the standard radiological monitoring program (Table 4.8-1) shall be submitted by March 31 of the next year.
The content of the report shall include:
(a) Results of environmental sampling summarized on a quarterly basis following the format of Regulatory Guide 4.8 Table 1 (December 1975);
(individual sample results will be retained at the station);
In the event that some results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results.
Summaries, interpretations, and analysis of trends of the results are to be provided.
(b) An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from plant emissions of radioactivity including the maximum ~ noble gas gamma and beta air doses in the unrestricted area.
The assessment of radiation doses shall be performed in accordance with the ODCM.
(c) Results of the census to determine the l
locations of animals producing milk for human i
consumption, and the pasture season feeding practices at dairies in the monitoring program.
(d) The reason for the omission if the nearest dairy to the station is not in the monitoring program.
(Table 4.8-5) 1 (e) An annual summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency 6-20 AMENDMENT NO. 105
DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97, 105 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
distributions of wind speed, wind direction, and atmospheric stability.
(f) The results of the interlaboratory comparison program described in Section 3.8.E.7.
l (g) The results of the 40 CFR 190 uranium fuel cycle dose analysis for each calendar year (h) A summary of the monitoring program, including maps showing sampling locations and tables giving distance and direction of sampling locations from the station.
3 See:ial Reports Special reports shall be submitted as indicated in Table t.t...
6.7 Environmental Qualification A.
By no later than June 30, 1982 all safety-related electrical ecu4p ent in the facility shall be qualified in accordance with the provisions of Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (00R Guidelines); or, NUREG-0588
" Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment", December 1979.
Copies of these documents are attached to Order for Modification of License DPR-19 dated October 24, 1980.
B.
By no later than December 1, 1980, complete and auditable records i
must be available and maintained at a central location which l
describe the environmental qualification method used for all safety related electrical equipment in sufficient detail to document the degree of compliance with the D0R Guidelines or NUREG-0588.
Thereafter, such records should be updated and i
maintained current as equipment is replaced, further tested, or otherwise further qualified.
6.8 Offsite Dose Calculation Manual (ODCM) l A.
The ODCM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid effluent monitoring instrumentation alarm / trip setpoints consistent with the applicable LC0's contained in these Technical Specifications. Methodologies and calculational 6-21 AMENDMENT NO. 105 g-
\\.
i
i DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97, 105 TABLE 6.6.1 SPECIAL REPORTS SPECIFICATION AREA REFERENCE SUBMITTAL DATE a.
Primary Coolant leakage to Drywell (3) 3.6.D Bases 5 years (1) b.
.In-Service Inspection Evaluation (3) 3.6.F Bases 5 years (1) c.
Evaluation.of Economic Generation 3.3.G Bases Upon completion of Control System (EGCS) operation (3)-
initial testing d.
Failed Fuel Detection (3) 3.2 Bases 5 years (1) e.
Main Steam Line Leakage to Steam Tunnel (3) 3.6.D Bases 5 years (1) f.
In service' Inspection Development (3) 3.6.F Bases 5 years (1)
.In-Ser-ice Inspection of Sensitized g.
Stainless Steel Components (2) 4.6.F 4 years (1) h.
Secondary Containment Leak Rate Test (3) 3.7.C.1 within 90 days after completion of each test i.
Radioactive Sourc( Leak Testing (4) 3.8.F Annual Report i
i NOTES:
1.-
The report shall be submitted within the period of time listed based on the commercial service date as the starting point.
2.
Dresden 2 only 3.
Dresden 2 and 3 only.
4.
The report is required only if the tests reveal the presence of 0.005 microcuries or more of removable contamination.
6-22 AMENDMENT NO. 105
A h
DRESDEN II DPR Amendment No. 82, 83, 86, 97, IOi
'6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
procedures acceptable to the Commission are contained in NUREG-0133.
The ODCM shall be submitted to the Commission at the time of proposed Radiological Effluent Technical Specifications and shall be subject to review and approval by the Commission prior to implementation.
'B.
Licensee initiated changes to the ODCM may be made provided the change:
1.
Shall be submitted to the Commission by inclusion in the Monthly Operating Report pursuant to Specification 6.6.A.3.
within 90 days of the date the change (s) was made effective and shall contain:
Sufficiently detailed information to support the 6.
change.
Information submitted should consist of a package of those pages of the ODCM to be changed 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 Documentation of the fact that the change has been c.
reviewed and found acceptable by the On-site Review l
Function.
2.
Shall become effective upon review and acceptance by the On-Site Review Function.
6.9 Process Control Program (PCP)
A.
The PCP shall contain the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is assured.
B.
The PCP shall be approved by the Commission prior to implementation.
Licensee initiated changes may be made to the PCP provided the change:
1.
Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change was made and shall contain:
6-23 AMENDMENT NO. 105 l
DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97, 105 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
L Sufficiently detailed information to support the change; a.
.b.
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and c.
Documentation that the change has been reviewed and found acceptable by the On-site Review Function.
2.
Shall become effective upon review and acceptance by the On-site Review Function.
E.10 Major Changes to Radioactive W6ste Treatment Systems (Liquid, Gaseous, Solid) (See note.below)
A.
Li m tee initiated major changes to the radioactive waste systems may h maae provided.
1.
Ine change is reported in the Monthly Operating Report for the period in which the evaluation was reviewed by the On-site l
Review Function.
The discussion of each change shall contain:
a.
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; t.
Sufficient detailed information to support the reason for the change; c.
A detailed description of the equipment, components, and process invohed and the interfaces with other plant systems; d.
An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents ar.d/or quantity of solid waste that differ from those previously predictM in the license application and amendments; e.
A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes were made; f.
An estimate of the exposure to plant operating personnel as a result of the change; and Note:
Licensee may choose to submit this information as part of the annual FSAR update.
A M EN E.
E 6-24
l l
l l
4 d
l DRESDEN II DPR-19 Amendment No. 82, 83, 86, 97, 105 E.0 ADMINISTRATIVE CONTROLS (Cont'd.)
9 Documentation of the fact that the change was reviewed and found acceptable by the On-site Review Function.
l l
2.
The change shall become effective upon review and acceptance by the On-site Review Function.
l 6-25 AMENDMENT NO. 105 l
},; o.
j[ s.g/ i NUCLEAR REGULATORY COMMISSION h
UNITED STATES 3'
t tNASHINGTON. D C. 20555 t
COMMONWEALTH EDISON COMPANY DOCKET NO. 50-249 EESDENNUCLEARPOWT.RSTATION, UNIT 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 100 License No. DPR-25 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by the Commonwealth Edison Company (the licensee) dated February 17, 1989 and supplemented March 20, 1989 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; E.
The f acility will operate in conformity with the application, the provisions of the Act and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; allo E.
The issuance of this amendirwnt is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is asiended by changes to the Technical Specifications as indicated in the attachment to this license amendment I
and paragraph 3.B. of Facility Operating License No. DPR-25 is hereby amended to read as follows:
I E.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.100, are hereby incorporated in the license.
The licensee sh611 operate the facility ir accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Daniel R. Nuller, Director Project Directorate III-2 Division of Reactor Projects - III, IV, Y and Special Projects
Attachment:
Changes to the Technical Specifications l
Date of Issuance: April 26,1989 i
l l
i ATTACHMENT TO LICENSE AMENDMENT NO 100 FACillTY OPERATING LICENSE DPR-25 l
DOCKET NO. 50-249 Pavise the Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages. The revised pages are identified by the capt1oned acendment number end contain marginal lines indicating the area of change.
REMOVE INSERT vi vi vii vii viii viii 6-1 6-1 6-2 6-2 6-3 (Figure 6.1-1 6-4(Figure 6.1-2})
6-5 6-4 6-6 6-3 6-7 6-5 6-8 6-6 6-9 6-7 6-10 6-8 6-11 6-9 6-12 6-10 6-13 6-11 6-14 6-12 6-15 6-13 6-16 6-14 6-17 6-15 6-18 6-16 6-19 6-17 6-20 6-18 6-21 6-19 6-22 6-20 6-23 6-21 6-24 6-22 6-25 6-23 6-26 6-24, 25 m
e+
no 1
m_
-.a
DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100 (Table c' Cc-tents, Cont'd.)
Page 4.' 9 Auxiliary Electrical Systems 3/4.9-1 4.9.A Station Batteries 3/4.9-1 4.9.B
'(N/A)
. 4. 9. C Diesel Fuel 3/4.9-4
' 4. 9. D Diesel Generator Operability 3/4.9-4 4.10.
Refueling 3/4.10-1 4.10.A Refueling Interlocks 3/4.10-1 1
'4.10.B Core Monitoring 3/4.10-1 4.10.C ' Fuel Storage Pool ~ Water Level 3/4.10-2 4.10.D Control Rod Drive and Control Rod Drive Maintenance 3/4.10-3 i
'4.10.E Extended Core Maintenance 3/4.10-4 4.10.F Spent Fuel Cask Handling 3/4.10-5 4.11 High Energy Pip.ing Integrity 3/4.11-1 4.12'. Fire Protection Systems 3/4.12-1 4
4.12.A Fire Detection Instrumentation 3/4.12-1 4.12.8 Fire Suppression Water System 3/4.12-2 4.12.C Sprinkler Systems 3/4.12-5 4.12.D C0 System 3/4.12-7 2
4.12.E Fire Hose Stations 3/4.12-8 4.12.F Penetration Fire Barriers 3/4.12-9
~4.12.G Fire Pump Diesel Engine 3/4.12-10 4.12.H Halen System 3/4.12-13 5.0 Design Features 5-1 5.1 Site 5-1 5.2 Reactor 5-1 5.3 Reactor Vessel 5-1 5.4 Containment 5-1 5.5 Fuel Storage 5-1 5.6 Seismic Design 5-2 6.0 Administrative Controls 6-1
' 6.1
' Organization, Review, Investigation and Audit 6-1 6.2 Plant Operating Procedures 6-13 6.3 Actions to be taken in the Event of A Reportable Occurrence in Plant Operation 6-15 6.4 Action to be taken in the Event a Safety Limit is Exceeded 6-15 6.5 Plant Operating-Records 6-15
- 6. 6 Reporting Requirements 6-17
- 6. 7 -
Environmental Qualification 6-21
- 6. 8 Offsite Dose Calculation Manual (ODCM) 6-21 6.9 Process Control Program (PCP) 6-23 6.10 Major Changes to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) 6-24 yj Amendment ho.100 i
a
ORESDEN III DPR-25 Amendment No. 78, 79, 83, 87, 92, 100 List of Tables Page Table 3.1.1 Reactor Protection System (Scram) 3/4.1-5 Instrumentation Requirements Table 4.1.1 Scram Instrumentation Functional Tests 3/4.1-8 Table C 1.2 Scram Instrumentation Calibration 3/4.1-10 Table 3.2.1 Instrumentation that Initiates Primary Containment Isolation Functions 3/4.2-8 Table 3.2.2 Instrumentation that Initiates or Controls the Core and Containment Cooling System 3/4.2-10 Table 3.2.3 Instrumentation that Initiates Rod Block 3/4.2-12 Table 3.2.4 Radioactive Liquid Effluent Monitoring Instrumentation 3/4.2-14 Table 3.2.5 Radioactive Gaseous Effluent 3/4.2-15 Monitoring Instrumentation Table 3.2.6 Post Accident Monitoring Instrumentation Requirements 3/4.2-17 Table 4.:.:
'"nimum Test and Calibration Frequency for Core and Containment Cooling Systems Instrumentation, Rod Blocks, and Isolations 3/4.2-19 Table 4.2.2 Racicactive Liquid Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2-22 Table 4.2.3 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 3/4.2-24 Table 4.2.4 Post Accident Monitoring Instrumentation Surveillance Requirements 3/4.2-26 Table 4.6.2 Neutron Flux and Sample Withdrawal B 3/4.6-30 Table 3.7.1 Primary Containment Isolation 3/4.7-31 Table 4.8.1 Radioactive Gaseous Waste Sampling and Analysis Program 3/4.8-22 Table 4.8.2 Maximum Permissible Concentration of Dissolved or Entrained Noble Gases Released from the Site to Unrestricted Areas in Liquid Waste 3/4.8-24 Table 4.8.3 Radioactive Liquid Waste Sampling and Analysis Program 3/4.8-25 Table 4.8.4 Radioactive Environmental Monitoring Progr~am 3/4.8-27 Table 4.8.5 Reporting Levels for Radioactivity Concentrations in Environmental Samples 3/4.8-28 Table 4.8.6 Practical Lower Limits of Detection (LLD) for Standard Radiological Environmental Monitoring Program 3/4.8-29 Table 4.11-1 Surveillance Requirements for High Energy Piping Outside Containment 3/4.11-3 Table 3.12-1 Fire Detection Instruments B 3/4.12-17 Table 3.12-2 Sprinkler Systems B 3/4.12-18 Table 3.12-3 CO Systems B 3/4.12-19 2
Table 3.12-4 Fire Hose Stations B 3/4.12-20 & 21 Table 6.1.1 Minimum Shift Manning Chart 6-4 Table 6.6.1 Special Reports 6-22 y4$
Amendment No.100
1 4
DRESDEN III DPR-25 Amendment No. 78, 79, 83,'87, 92, 1
94, 100 List of Figures Page Figure 2.1-3
.APRM Bias Scram-Relationship to Normal Operating Conditions B 1/2.1-17 Figure 4.1.1 Graphical Aid in the Selection of an Adequate Interval Between Tests
-B 3/4.1-18 Figure 4.2.2 Test Interval vs. System Unavailability B 3/4.2 Figure 3.4.1 Standby Liquid Control Solution Requirements 3/4.4-4
' Figure 3.4.2 Sodium Pentaborate Solution Temperature Requirements 3/4.4-5 Figu're 3.5-1 MAPLHGR' Limit =vs Bundle Average Exposure ANF 8x8 Fuel (Sheet 1 of 2) 3/4.5-18 Figure 3.5-1 MAPLHGR Limit vs Bundle Average Exposure ANF 9x9 Fuel (Sheet 2 of 2) 3/4.5-19 Figure 3.5-1A-Steady State Linear Heat Generation Rate vs Nodal Exposure 3/4.5-20 Figure 3.5-1B Transient Linear Heat Generation Rate vs Nodal Exposure 3/4.5-21 Figure 3.5-2
'MCPR LIMIT for Reduced Total Core Flow (Sheet 1 of 3) 3/4.5-25 Figure 3.5-2 8x8 MCPR Operating Limit for Automatic Flow Control (Sheet 2 of 3) 3/4.5-26 Figure 3.5-2 9x9 MCPR Operating Limit for Automatic Flow Control (Sheet 3 of 3) 3/4.5-27 Figure 3.6.1 Minimum Temperature Requirements per Appendix G of 10 CFR 50 3/4.6-23
~
Figure 3.6.2 Thermal Power vs Core Flow Limits for Thermal Hydraulic Stability Surveillance In Single Loop Operation 3/4.6-24 Figure 4.6.1 Minimum Reactor Pressurization Temperature B 3/4.6-29 Figure 4.6.2 Chloride Stress Corrosion Test Results at 500'F B 3/4.6-31 Figure 4.8-1 Owner Controlled / Unrestricted Area Boundary B 3/4.8-38 Figure 4.8-2 Detail of Central Complex B 3/4.8-39 Figure 6.1-1 Offsite Organization - Deleted Figure 6.1-2 Station Organization - Deleted Amendment No.100 v111
l
. ~.
DRESDEN III DPR-25 Amendment No. 75, 79, 92, 100 l'
6.0 ADMINISTRATIVE CONTROLS E.1 Organization, Review, Investigation and Audit A.
Onsite and offsite organizations shall be established for the unit operation and corporate management, respectively.
The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.
1.
Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through the intermediate levels to and including all operating organization positions.
These relationships shall be documented and updated, as-appropriate, in the form or organization charts, functional descriptions of department responsibilities and relationships, and job descriptions for key personnel positions, or in the equivalent forms of documentation.
The requirements shall be documented in the Quality Assurance Manual or the Management Plan for Nuclear Operations, Section 3 Organizational 4
Authority, Activity; Section 6 Interdepartmental Relationships.
2.
The Station Manager shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of plant.
3.
The Senior Vice President-Nuclear Operations shall have the corporate responsibility for overall plant nuclear safety and shall taka any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.
4.
.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 opera-tional pressures.
~
B.
DELETED C.
The shift manning for the station shall be as shown in Table 6.1.1.
The Operating Assistant Superintendent, Operating Engineers, Shift Engineers, and Shift Foremen shall have a l
Senior Operating License.
The Fuel Handling Foreman shall have a limited Senior Operating License.
The Vice President BWR Operations on the corporate level has responsibility for the Fire Protection Program. An Operating Engineer at the station will be responsible for implementation of the Fire Protection Program.
A fire brigade of at least 5 members shall be main-tained on-site at all times.
This excludes the shift crew necessary for safe shutdown of the plant and any personnel required for essential functions during a fire emergency.
6-1 Amendment No.100
[
DRESDEN III DPR-25 Amendment No. 75, 79, 92, 100 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)-
D.
Qualifications of the station management and operating staff shall meet minimum acceptable levels as described in ANSI N19.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971, with the exception of the Health Physics Services Supervisor who shall meet or exceed the I
qualifications of Radiation Protection Manager of Regulatory Guide 1.8, September 1975, and the Shift Technical Advisor who I
shall have a bachelor's degree or equivalent in a scientific l
or engineering discipline with specific training in plant design and response and analysis of the plant for transients and accidents.
The individual filling the position of Technical Superintendent shall meet the minimum acceptable l
level for " Technical Manager" as described in 4.2.4 of ANSI j
N18.1 - 1971.
E.
Re: ai-ing and replacement training of Station personnel shall be in accordance with ANSI N18.1, " Selection and Training of Nuclear Power Plant Personnel," dated March 8, 1971.
A training program for the fire brigade shall be maintained under the direction of the Operating Engineer and shall meet or exceed the requirements of Section 27 of the NFPA Code -
1975, except for fire brigade training sessions which shall be held at least quarterly.
F.
Retraining shall be conducted at intervals not exceeding two years.
G.
The Review snd Investigative Function and the Audit Function of activities affecting quality during facility operations shall be constituted and have the responsibilities and authorities outlined below:
1.
The Superintendent of the Off-site Review and Investigative Function shall be appointed by the Manager of Quality Assurance /
Nuclear Safety (QA/NS).
The Corporate Audit Function shall be the responsibility of the Manager of QA/NS and shall be independent of operations.
The Manager of QA/NS reports directly to the Chief Executive officer and has the responsibility to set i
Corporate Polby for both the areas of Quality Assurance and Nuclear Safeh Policy is promulgated through a central policy committee directed by the Manager of QA/NS. The Manager of QA/NS has the responsibility for the performance of periodic audits of each nuclear station and corporate department to determine that QA/NS policy is being carried out.
i 6-2 Amendment No.100
i DRESDEN III
'DPR-25 Amendment No. 75, 79, 92, 100 6;C ADMINISTRATIVE CONTROLS (Cont'd.)
a.
Off-site Review and Investigative Function The Superintendent of the Off-site Review and Investigative i
Function shall:
(i) provide directions for the review and investigative function and appoint a senior participant to provide appropriate direction, (ii) select each participant for this function, (iii) select a complement of more than one participant who collectively possess background and qualifications in the subject matter under review to provide comprehensive interdisciplinary review coverage under this function, (iv) independently revien and approve the findings and recommendations
. developed by personnel performing the review and investigative function, (v) approve and report in a timely manner all findings of noncompliance with NRC requirements and provide recommendations.to the Station Manager, Vice President BWR Operations, Manager QA/NS, Assistant Vice President (AVP) Quality Programs and Assessment and the Senior Vice President-Nuclear Operations.
During periods when the Superintendent of the Off site Review and Investigative Function is unavailable, he shall designate this responsibility to an established alternate who satisfies the formal training and experience require-ments for the Superintendent of the Off-site Review and l
Investigative Function.
The responsibilities of the personnel performing this function are stated below.
The Off-site Review and Investigative Function shall review:
l (1) The safety evaluations for 1) changes to pro-cedures, equipment or systems as described in the safety analysis report and 2) tests or experiments i
completed under the provision of 10 CFR 50.59 l
to verify that such actions did not constitute unreviewed safety questions.
Proposed changes to the Quality Assurance Program description shall be reviewed and approved by the Manager of QA/NS.
(2) Proposed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
l (3) Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
^**"
6-3
DRESDEN !!!
OPR 25 Amenoment No. 75, 79, 92, 100 TABLE 6.1.1 MIN!HJM SHIFT MANNING CHART (1) j i
CONDITION OF NUMBER OF MEN IN EACH POSITION UN:T5 STA or h0h-RAD
{
II)
I3)
WITH FUEL FIRST UNIT SECOND UN]T THIR0 UNIT SRO RO SCRE LIC.
MEN Cold Shutdown Cold Shutdown Cold Shutdown 1
1 0
5 1
ONE Above Cold Shutdown Cold Shutdown Cold Shutdown 2
2 1
5 1
Cold Shutdown Cold Shutdown Cold Shutdown 1
2 0
5 1
1 TW Above Cold Shutdown Cold Shutdown Cold Shutdown 2
3 1
5 1
l Above Above Cold shutdown Cold Shutdown Cold Shutdown 2
3 1
5 1
Cold Shutdown Cold Shutdown Cold Shutdown 1
3 0
5 1
THREE Above I
Cold Shutdown Cold Shutdown Cold Shutdown 2
4 1
5 1
Above Above Cold Shutdown Cold Shutdown Cold Shutdown 2
4 1
5 1
Above Above Above Cold Shutdown Cold Shutdown Cold Shutdown 2
4 1
5 1
- Senior Reactor Operator. At least one SRO must remain in the Control Room at all l
times when one or more units is above cold shutdown. This person may, however, l
leave the Control Room for periods not to exceed 10 minutes, provided another SRO l
acts as relief operator. The SCRE or shift supervisor can fulfill this l
requirement.
R0
- Reactor Operator (For each reactor containing fuel, one RO will be in the Control Room at all times.)
- Station Control Room Engineer (STA with Senior Reactor Operator's License).
NON-LIC.
- Equipment Operators and Equipment Attendants.
RAD MEN
- Radiation Protection Men.
NOTES: (1) - Shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shif t crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.
(2) - Does not include the licensed Senior Reactor Operator or Senior Reactor Operator limited to fuel handling, supervising CORE OPERATIONS.
(3) - Shall not operate units on which they are not licensed.
ADDITIONAL REQUIREMENTS A.
SRO can be R0 at controls.
B.
SRO in Control Room cannot provide relief to SR0/R0 at controls.
C.
SRO in Control Room must be in sight of or audible range of operator at all times or be in audible range of annunciators.
Amendnent No.100 6-4
i.
i l
l l
l l
l DRESDEN III DPR-25 Amendment No. 75, 79, 92, 100 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
(4) Proposed changes in Technical Specifications or l
NRC operating licenses.
(5) Noncompliance with NRC requirements, or of inter-nal procedures or instructions having nuclear safety significance.
(6) Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety as referred to it by the Onsite Review and Investigative Function.
(7) Reportable Events reported under 10 CFR 50.73.
(8) All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems or components.
(9) Review and report findings and recommendations regarding all changes to the Generating Stations Emergency Plan prior to implementation of such changes.
(10) Review and report findings and recommendations regarding all items referred by the Technical l
Staff Supervisor, Station Manager, Vice President I
BWR Operations and AVP Quality Program and Assessment.
b.
Station Audit Function l
The Station Audit Function shall be the responsibility of the AVP Quality Programs and Assessment independent of the Production Department.
Such responsibility is delegated to the Nuclear Quality Programs Manager.
l l
Either of the above, or designated Corporate Staff or Super-vision approved by AVP Quality Programs and Assessment shall l
approve the audit agenda and checklists, the findings and the report of each audit.
Audits shall be performed in accordance with the Company Quality Assurance Program and Procedures.
Audits shall be performed to assure that-safety-related functions are covered within the period designated below.
6-5 Amendment No.100 I
)
i i
DRESDEN III DPR-25 Amendment No. 75, 79, 92, 100
'6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
(1) Audit of the Conformance of facility operation to provisions contained within the Technical Speci-fications and applicable license conditions at least once per. year.
(2) Audit of the adherence to procedures, training and qualification of the station staff at least once per year.
(3) Audit of the results of actions taken to correct deficiencies occurring in facility equipment, structures, systems or methods of operation that affect nuclear safety at least once per.six months.
(4) Audit of the performance of activities required by the Quality Assurance Program to meet the Criteria of Appendix "B", 10 CFR 50.
4 i
(5) Audit of.the Facility Emergency Plan and implementing procedures at least one per i
12 months.
(6) Audit of the Facility Security Plan and implementing procedures at least once per 12 months.
(7) Audit on-site and off-site reviews.
l (8) Audit of Facility Fire Protection Program and implementing procedures at least once per 24 months.
(9) The radiological environmental monitoring program and the results thereof at least once per 12 months.
(10)The ODCM and implementing procedures at least once per 24 months.
(11)The PCP and implementing procedures for solidifi-I cation of radioactive waste at least once per 24 months.
(12) Report all findings of noncompliance with NRC requirements and recommendations and results of i
each audit to the Station Manager, Manager of QA/NS, the Vice president BWR Operations, AVP 6-6 Amendment No.100
DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100 6..
A !GISTRATIVE CONTROLS (Cont'd.)
Quality Programs and Assessment, the Senior Vice President-Nuclear Operations and the Chief Operating Officer.
c.
Authority The Manager of QA/NS reports to the Chief Executive Officer.
The Manager of QA/NS has the authority to order unit shutdown or request any other action which he deems necessary to avoid unsafe plant conditions.
The AVP Quality Programs and Assessment reports to the Senior Vice President-Nuclear Operations.
The AVP Quality Programs and Assessment has the authority to recommend unit shutdown or request any other which he deems necessary to avoid unsafe plant conditions.
All such disagreements shall be reported immediately to the Manager of QA/NS and the Chief Operating Officer.
d.
Records (1) Reviews, audits and recommendations shall be documented and distributed as covered in 6.1.G.I.a and 6.1.G.1.b.
(2) Copies of documentation, reports, and correspondence shall be kept on file at the station.
e.
Procedures Written administrative procedures shall be prepared and maintained for the Off-site Reviews and Investigative Functions described in Specifications 6.1.G.1.a.
These procedures shall cover the following:
(1) Content and method of submission of presentations to the Superintendent of the Off-site Review and Investigative Function.
(2) Use of committees and consultants.
(3) Review and approval.
(4) Detailed listing of items to be reviewed.
6-7 Amendment No.100 l
DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100 6.0 AD G :57RATIVE CONTROLS (Cont'd.)
(5) Method of (a) appointing personnel, (b) performing reviews, investigations, (c) reporting findings and recommendations of reviews and investigations, (d) approving reports, and (e) distributing reports.
(E) Determining satisfactory completion of action required based on approved findings and recommenda-ions reported by personnel performing the Review and Investigative Function.
f.
Personnel (1) The persons, including consultants, performing the review and investigative function, in addition to the Superintendent of the Off-site l
Review and Investigative Function, shall have expertise in one or more of the following dis-ciplines as appropriate for the subject or subjects being reviewed and investigated.
(a) nuclear power plant technology (b) reactor operations (c) utility. operations (d) power plant design (e) reactor engineering (f) radiological safety (g) reactor safety analysis (h) instrumentation and control (i) metallurgy (j) any other appropriate disciplines required by unique characteristics of the facility.
(2) Individuals performing the Review and Investigative Function shall possess a minimum formal training and experience as listed below for each discipline.
(a) Nuclear Power Plant Technology Engineering graduate or equivalent with 5 years experience in the nuclear power field design and/or operation.
l (b) Reactor Operations Engineering graduate or equivalent with 5 years experience in nuclear power plant operations.
6-8 Amendment No.100
l e
DRESDEN III DPR-25 Amendment No. 75, 79, 92, 100 l
l 6.0 ADINISTGTIVE CONTROLS (Cont'd.)
(c) Utility Operations Engineering graduate or equivalent with at least 5 years of. experience in utility operation and/or engineering.
(d) Power Plant Design Engineering graduate or equivalent with at least 5 years of experience in power plant design and/or operation.
(e) Reactor Engineering Engineering graduate or equivalent.
In addition, at least'5 years of experience in nuclear plant engineering, operation, and/or graduate work in nuclear engineering or equivalent in reactor physics is required.
(f) Radiological Safety Engineering graduate or equivalent with at least 5 years of experience in radiation control and safety.
(g) Safety Analysis 1
Engineering graduate or equivalent with at least 5 years of experience in nuclear engineering.
(h) I_ instrumentation and Control Engineering graduate or equivalent with at least 5 years of experience in instruments-tion and control design and/or operation.
(i) Metallurgy Engineering graduate or equivalent with at least 5 years of experience in the metallurgical field.
(3) The Superintendent of the Off-site Review and l
Investigative Function shall have experience and I
training which satisfy ANSI N18.1 - 1971 i
requirements for plant managers.
l 6-9 Amendment No.100 l
{
i
1 i
DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100 6.0 ACC NISTRATIVE CONTROLS (Cont'd.)
2.
The On-site Review and Investigative Function shall be l
supervised by the Station Manager.
The Station Manager can 4
designate this responsibility to an alternate who satisfies the ANSI N18.1 (March 8, 1971), Experience Requirements for Plant Manager.
a.
On-site Review and Investigative Function The Station Manager (or designee) shall:
(i) provide direction for the Review and Investigative Function and appoint the Technical Staff Supervisor, or other comparably qualified individual as a senior participant to provide appropriate direction; (ii) approve participants for this
)
function; (iii) assure that a complement of more than one participant who collectively possess background and qualifications in the subject matter under review are j
selected to provide comprehensive inter-disciplinary review coverage under this function; (iv) independently review and approve the findings and recommendations developed by personnel performing the Review and Investigative Function; (v) report all findings of noncompliance with NRC require-ments, and provide recommendations and; (vi) submit to the i
Off-site Review and Investigative Function for concurrence in a timely manner, those items described in Specifica-tion 6.1.G.1.a which have been approved by the On-site l
Review and Investigative Function.
The responsibilities of the personnel perfoming this function are stated below:
(1) Review of:
- 1) procedures required by Specifica-tion 6.2 and changes thereto, 2) any other pro-posed procedures or changes thereto as determined by the Station Manager (or designee) to affect nuclear safety.
i (2) R'eview of all proposed tests and experiments that i
affect nuclear safety.
(3) Review of all proposed changes to the Technical Specifications.
(4) Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
(5) Investigation of all noncompliance with NRC requirements and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence.
6-10 Amendment No.100 l
1 DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100 E.: A:t<:td 57RATIVE CONTR0t.S (Cont'c.)
(6) Review of facility operations to detect potential safety hazards.
-(7) Performance of special reviews and investigations and reports thereon as requested by the Super-i intendent of the Off-site Review and Investigative I
Function.
j j
(8) Review the Station Security Plan and shall submit recommended changes to the Director of Corporate Security and the AVP Quality Programs and Assessment in lieu of distribution in accordance with 6.1.G.2.c(1).
(9) Review the Emergency Plan and station implementing procedures and identification of recommended changes.
(
': Review of reportable events and actions taken to prevent recurrence.
(11)
Review of any unplanned on-site release of radioactive' material to the environs including i
the preparation and fowarding of reports covering evaluation recommendations and disposition of the corrective action to prevent recurrence to the Vice President BWR Operations and to the Superintendent of the Off-site Review and Investigative Function.
(12)
Review of changes to the PCP and ODCM and major changes to the radwaste treatment systems.
b.
Authority The Technical Staff Supervisor is responsible to the Station Manager (or designee) and shall make recom-mendations in a timely manner in all areas of review, investigation, and quality control phases of plant maintenance, operation and administrative procedures relating to facility operations.
The Technical Staff Supervisor shall have the authority to request the action necessary to ensure compliance with rules, regulations, and procedures when in his opinion such action is necessary.
The Station Manager (or designee) shall follow such recommendations or select a course of action that is more conservative regarding safe operation of the facility.
All such disagreements shall be reported immediately to the Vice President BWR Operations and the Superintendent of the Off-site Review and Investigative Function.
6-11 Amendment No.100 l
'DRESDEN III DPR-25 l
Amendment No. 75, 77, 79, 92, 100 E.0 ADMINISTRATIVE CONTROLS (Cont'd.)
c.
Records-(1) Reports, reviews, investigations, and recommendations prepared and performed for Specification 6.1.G.2.a shall-be documented with copies-to the Vice President BWR Operations, the Superintendent of the Off site Review and Investigative Function and the AVP Quality Programs and Assessment.
(2) Copies of all records and documentation shall'be kept on' file at the station.
d.
Procedures Written administrative procedures shall be prepared and maintained for conduct of the On-site Review and l
Investigative Function.- These procedures shall include.the following:
(1) Content and method of submission and presentation
~
to the Station Manager (or designee), Vice President BWR Operations and the Superintendent of the Off-site Review and Investigative Function.
(2) Use of committees.
I (3) Review and approval.
(4) Detailed listing of items to be reviewed.
(5) Procedures for administration of.the quality j
control activities.
J (6) Assignment of responsibilities.
e.
Personnel (1) The personnel performing the On-site Review and l
3 Investigative Function, in addition to the Station Manager (or designee),'shall consist of persons having expertise in:
(a) nuclear power plant technology (b) reactor operations (c) reactor engineering (d) radiological safety (e) chemistry (f) instrumentation and control (g) mechanical and electric systems.
l 6-12 Amendrnent No.100
____--___-__---_-___ ___c _ _ _ _-_____ -
1 I~
L DRESDEN III DPR-25 L
Amendment No. 75, 79, 92, 100 l-
- 6.. ADMIN: 5TRATIVE CONTROL 5' (Cont'd.)
l 1.
l (2) Personnel performing the On-site Review and l
Investigative Function shall meet minimum acceptable levels as described in ANSI N18.1-1971, Sections 4.2 and 4.4.
H.
Fire Protection 1.
An independent fire protection and loss prevention program l
inspection and audit shall be performed at least once per i
12 months utilizing either qualified off-site licensee personnel or an outside fire protection firm.
2.
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.
l 6.2 Plant Operatine Procedures f
A.
Detailed written procedures including applicable checkoff lists covering items listed below shall be prepared, approved, and adhered to:
1.
Normal startup, operation, and shutdown of the reactor and other systems and components involving nuclear safety of the facility.
2.
Refueling operations.
- 3.. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components including responses to alarms, suspected primary system leaks, and abnormal reactivity changes.
4.
Emergency conditions involving potential or actual release of radioactivity
" Generating Stations Emergency Plan"
)
and station emergency and abnormal procedures.
5.
Instrumentation operation which could have an effect on the safety of the facility.
6.
Preventive and corrective maintenance operations which could have an effect on the safety of the facility.
7.
Surveillance and testing requirements.
8.
Tests and experiments.
}
9.
Procedure to ensure safe shutdown of the plant.
6-13 Amendment No.100
DRESDEN III.
DPR-25 Amendment No. 75, 77, 79, 92, 100 6.:
ADMINISTRATIVE CONTROLS (Cont'd.)
- 10. Station Security Plan and implementing procedures.
- 11. Fire Protection Program implementation.
- 12. ODCM implementation.
- 13. PCP implementation.
- 14. Working hours of the Shift Engineer, Station Control Room 1
Engineer, Shif t Foreman, Nuclear Station Operator job classifications such that the heavy use of overtime is not routinely required.
i B.
Radiation control procedures shall be maintained, made available to all station personnel and adhered to.
These i
procedures shall show permissible radiation exposure and shall be consistent with the requirements of 10 CFR 20.
This radiation protection program shall be organized to meet the requirements of 10 CFR 20.
C.
1.
Procedures for items identified in Specification 6.2.A and any changes to such procedures shall be reviewed and approved by the Operating Engineer and the Technical Staff Supervisor in the areas of operation, fuel handling, or instrument maintenance, and by the Maintenance Assistant l
Superintendent and Technical Staff Supervisor in the areas of plant maintenance and plant inspection.
Procedures for items identified in Specification 6.2.B and any changes to such procedures shall be reviewed and approved by the Health Physics Services Supervisor.
At least one person g
approving each of the above procedures shall hold a valid senior operator's license.
In addition, these procedures and changes thereto must have authorization by the Station Manager (or designee) before being implemented.
2.
Work and instruction type procedures which implement app oved maintenance or modification procedures shall be approved and authorized by the Maintenance Assistant Superintendent where the written authority has been provided by the Production Superintendent.
The " Maintenance /
Modification Procedure" utilized for safety related work shall be so approved only if procedures referenced in the
" Maintenance / Modification Procedure" have been approved as required by 6.2.A.
Procedures which do not fall-within l
the requirements of 6.2. A or 6.2.B may be approved by the Department Heads.
l I
6-14 Amendment No.100 j
A
(
DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100 E.0 ADMhlSTRATI\\E GNTROLS (Cont'd.)
0, Temocrary changes to procedures 6.2.A and 6.2.B above may be made provicea:
1.
The intent of the original procedure is not altered.
2.
The cnange 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.
3.
The change is documented, reviewed by the On-site Review and Investigative Function and approved by the Station Manager (or designee) within 14 days of implementation.
E.
Drills of the emergency procedures described in Specification 6.2.A.4 shall be conducted at the frequency specified in the Generating Station Emergency Plan.
These drills will be plannec s: that during the course of the year, communication links are tested and outside agencies are contacted.
6.3 Action to be Taken in the Event of a Reportable Event in Plant Operation Any reportable event shall be promptly reported to the Vice President BWR Operations or his designated alternate.
The incident shall be promptly reviewed pursuant to Specification 6.1.G.2.a(5) and a separate report for each reportable event shall be prepared in accordance with the requirements of Specification 6.6.B.
6.4 Action to be Taken in the Event a Safety Limit is Exceeded If a safety limit is exceeded, the reactor shall be shut down immediately and reactor operation shall not be resumed until authorized by the NRC.
The conditions of shutdown shall be promptly reported to the Vice President BWR Operations or his designated alternate.
The incident shall be reviewed pursuant to Specification 6.1.G.I.a and 6.1.G 2.a and a separate report for each event sh*all be prepared in accordance with Specification 6.6.B.
6.5 Plant Operating Records A.
Records and/or logs relative to the following items shall be kept in a manner convenient for review and shall be retained
)
for at least five years.
1.
Records of normal plant operation, including power levels and periods of operation at each power level.
6-15 l
o
{'
o.
ORESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100
'6. 0 ADMINISTRATIVE CONTROLS (Cont'd.)
2.
Records of principal maintenance activities, including inspection ana repair, regarding principal items of equipment pertaining to nuclear safety.
3.
. Records and reports of reportable and safety limit events.
1 4.
Records and periodic checks, inspection and/or calibrations performed to verify the Surveillance
~
Requirements (See Section 4 of these Specifications) are being met.
All equipment failing to meet surveillance requirements and the corrective action taken shall be recorded.
5.
Records of changes made to the equipment or reviews of tests and experiments to comply with 10 CFR 50.59.
6.
Records cf radioactive shipments.
7.
Records of physic tests and other tests pertaining to nuclear safety.
8.
Records of changes to operating procedures.
9.
Shift Engineers Logs.
- 10. By product material inventory records and source leak test results.
B.
Records and/or logs relative to the following items shall be recorded in a manner convenient for review and shall be retained for the life of the plant.
i 1.
Substitution or replacement of principal items of equipment pertaining to nuclear safety.
2.
Changes made to the plant as it is described in the Safety
-Analysis. Report.
3.
Records of new and spent fuel inventory and assembly histories.
4.
(Deleted) 5.
Updated, corrected, and as-built drawings of the plant.
6.
Records of plant radiation and contamination surveys.
l l
7.
Records of off-site environmental monitoring surveys.
6-16 Amendment No.100 l l
.i
.c DRESDEN III DPR-25 Amendment No. 75, 79, 92, 100 6,; CMINISTRATIVE CONTROLS (Cont'd.)
S.
Records of radiation exposure for all plant personnel, including all contractors and visitors to the plant in accordance with 10 CFR 20, 9.
Records of_ radioactivity.in liquid and gaseous wastes i
released to the environment.
-10. Records of transient or operational cycling for those components that have been designed to operate safely for a limited number of transient or operational cycles.
- 11. Re:ords of. individual staff members indicating i
qualifications, experience, training and retraining.
- 12. ' Inservice inspections of the reactor coolant system.
I? Minutes of meetings and results of reviews performed by
- ne Off-site and On-site Review Functions.
- 14. Recoras for Environmental Qualification which are covered under the provisions of paragraph 6.7.
6.6 REPORTING REQUIREMENTS In addition to the applicable reporting requirements of Title 10,
- l Code of Federal Regulations, the following identified reports shall be submitted to the Regional Administrator of the appropriate Regional Office of the NRC unless.otherwise noted.
A. -Routine Reports 1.
Startup Report 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. The report shall address each of the tests identified in the FSAR and shall in general include a description of the measured values of i
the operating conditions or characteristics obtained I
during the test program and a comparison of these values with design predictions and specifications.
Any corrective actions that were required to obtain satisf actory operation shall also be described.
Any 6-17 Amendment No.100 l
e a
DRESDEN III DPR-25 Amendment No. 75, 79, 92, 100 f.: AD O :!':ATIVE CONTROLS (Cont'd.)
additional specific details required in license conditions based on other commitments shall be included in this report.
Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 deys following resumption or commencement of commercial po er operation, or (3) 9 months following initial criticality, whichever is earliest.
If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or t
commencement of commercial power operation), supplementary a
reports shall be submitted at least every three months until all three events have been completed.
2.
A tabulation shall be submitted on an annual basis of the n.:-ter of. station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man rem exposure according to work and job functions, (See note); e.g., reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
3.
Monthly Operating Report Routine reports of operating statistics and shutdown experiences shall be submitted on a monthly basis to the United States Nuclear Regulatory Co mission, Washington, DC 20555, with a copy to tfie appropriate Regional Administrator, to arrive no later than the 15th of each month following the calendar month covered by the report.
B.
Reportable Events Reportable events will be submitted as required by 10 CFR 50.73.
Note:
This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
6-18 Amendment No.100 l
w_-__-_--_-
a l
l DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100 1
E.0 AZ:NISTRATIVE CONTROLS (Cont'd.)
C.
Unioue Reportino Requirements 1.
Radioactive Effluent Release Report (Semi-Annual)
A report shall be submitted to the Commission within 60 days after January I and July 1 of each year specifying the quantity of each of the principal radionuclides released to unrestricted areas in liquid and gaseous effluents during the previous 6 months.
The format and content of the report shall be in accordance with Regulatory Guide 1.21 (Revision 1) dated June 1974.
Any changes to the PCP shall be included in this report.
a.
Standard Radiological Monitoring Program (1) Non-Routine Report (a) If a confirmed measured radionuclides concentration in an environmental sampling medium averaged over any calendar quarter sampling period exceeds the reporting level given in Table 4.8-1 and if the radioactivity is attributable to plant operation, a written report shall be submitted to the Regional i
Administrator of the NRC Regional Office, with a copy to the Director,.0ffice of Nuclear Reactor Regulation, within 30 days from the end of the quarter. When more than one of the radionuclides in Table 4.8-1 are detected in the medium, the reporting level shall have been exceeded if IC /(RL)$ is equal to or greater than 1 g
th where C is the concentration of the i radionuclides in the medium and RL is the reporting level of radionuclides i.
(b) If radionuclides other than those in Table 4.8-1 are detected and are due to plant effluents, a reporting level is exceeded if the potential annual dose to an individual is equal to or greater than the design objective doses of 10 CFR 50, Appendix 1.
i Amendment No.100 g 6-19
-__-______________D
l DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100 l
E..
AD"!M STRATIVE CONTROLS (Cont'd.)
2.
Environmental Radioactivity Data (Annual Report)
(c) This report shall include an evaluation of any release conditions, environmental factors, or
,i other aspects necessary to explain the anomalous effect.
(2) Annual Operating Report An annual report containing the data taken in the standard radiological monitoring program (Table 4.8-1) shall be submitted by March 31 of the next year.
The content of the report shall include:
(a) Results of environmental sampling summarized on a quarterly basis following the format of Regulatory Guide 4.8 Table 1 (December 1975);
(individual sample results will be retained at the station);
In the event that some results are not available for inclusion witn the report, the report shall be submitted noting and explaining the reasons for the missing results.
Summaries, interpretations, and analysis of trends of the results are to be provided.
(b) An assessment of the monitoring results and radiation dose via the principal pathways of exposure resulting from plant 3 missions of radioactivity including the maximum noble gas gamma and beta air doses in the unrestricted area.
The assessment of radiation doses shall be performed in accordanci. with the ODCM.
(c) Results of the census to determine the locations of animals producing milk for human consumption, and the pasture season feeding practices at dairies in the monitoring program.
(d) The reason for the omission if the nearest dairy to the station is not in the monitoring program.
(Table 4.8-5)
(e) An annual summary of meteorological conditions concurrent with the releases of gaseous effluents in the form of joint frequency distributions of wind speed, wind direction, and atmospheric stability.
6-20 Amendment No.100 l
t o
)
i l
DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100
- 6. 0 AD'."r FTn': s E CONTROLS (Cont'd.)
(f)'The results of the interlaboratory comparison program described in Section 3.8.E.7.
l (g) The results of the 40 CFR 190 uranium fuel cycle dose analysis for each calendar year.
(h) A summary of the monitoring program, including maps showing sampling locations and tables giving distance and direction of sampling locations from the station.
3.
Special Reports Special reports shall be submitted as indicated in Table 6.6.1.
6.7 E.'renmen W ;. edification A.
By no later than June 30, 1982 all safety related electrical equipment in the facility shall be qualified in accordance with the provisions of Division of Operating Reactors " Guidelines for Evaluating Environmental Qualification of Class IE Electrical Equipment in Operating Reactors" (DOR Guidelines); or NUREG-0588
" Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment", December 1979.
Copies of these documents are attached to Order for Modification of License DPR-25 dated October 24, 1980.
B.
By no later than December 1, 1980, complete and auditable records must be available and maintained at a central location which describe the environmental qualification method used for all safety-related electrical equipment in sufficient detail to document the degree of compliance with the DOR Guidelines or NUREG-0588. Jhereafter, such records should be updated and maintained current as equipment is replaced, further tested, or otherwise further qualified.
6.8.0ffsite Dose Calculation Manual (ODCM)
A.
The ODCM shall describe the methodology and parameters to be used in the calculation of offsite doses due to radioactive gaseous and liquid effluents and in the calculation of gaseous and liquid ef fluents monitoring instrumentation alarm / trip setpoints consistent with the applicable LCO's contained in these Technical Specifications.
Methodologies and calculational procedures acceptable to the Commission are contained in NUREG-0133, i
1
\\
w
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~n
DRESDEN III DPR-25 Amendment No. 75,177, 79, 92, 100 TABLE 6.6.1
.5PECIAL REPORTS SPECIFICATION AREA REFERENCE SUBMITTAL DATE Primary Coolant leakage to Drywell (3) 3.6.D Bases 5 years (1) a.
b.
In-Service Inspection Evaluation (3) 3.6.F Bases 5 years (1) c.
Evaluation of Economic Generation 3.3.G Bases Upon completion Control System (EGCS) operation (3) of initial testing d.
Failed fuel Detection (3) 3.2 Bases 5 years (1)
Main Steam Line Leakage to Steam e.
T u n r.e. JJ 3.6.D Bases 5 years (1) f.
In-service Inspection Development (3) 3.6.F Bases 5 years (1) g.
In-Service Inspection of Sensitized Stainless Steel Components (2) 4.6.F 4 years (1) h.
Secondary Containment Leak Rate Test (3) 3.7.C.1 within 90 days after comple-tion of each test i.
Radioactive Source Leak Testing (4) 3.8.F Annual Report NOTES:
1.
The report shall be submitted within the period of time listed based on the commercial service date as the starting point.
2.
Dresden 2.only 3.
Dresden 2 and 3 only.
4.
The report is required only if the tests re.tal the presence of 0.005 microcuries or more of removable contamination.
1 6-22 AmendmentNo.Id0
DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92 6.; ADMIN: 5TRATIVE CONTROLS (Cont'd.)
The ODCM shall be submitted to the Commission at the time of perpese: Radiological Effluent Technical Specifications and shall be subject to review and approval by the Commission prior to i d erentation.
B.
Licensee initiated changes to the ODCM may be made provided the cnan;c:
1.
Sr.all be submitted to the Commission by inclusion in the Monthly Operating Report pursuant to Specification 6.6.A.3.
within 90 days of the date the change (s) was made effective and shall contain:
a.
Sufficiently detailed information to support the change.
Information submitted should consist of a package of those pages of the ODCM to be changed together with appropriate analyses or evaluations l
justifying the change (s);
c.
A determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations; and Documentation of the fact that the change has been c.
reviewed and found acceptable by the On-site Review l
Function.
2.
Shall become effective upon review and acceptance by the On-site Review Function.
6.9 Process Control Program (PCP)
A.
The PCP shall contain the sampling, analysis, and formulation determination by which solidification of radioactive wastes from liquid systems is assured.
I B.
The PCP shall'be approved by the Commission prior to implementation.
l C.
Licensee initiated changes may be made to the PCP provided the change:
1.
Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change was made and shall contain-a.
Sufficiently detailed information to support the change; I
Amendment No.100 6-23 a
o 1
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DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100
-6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
b.
A determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for.. solid wastes; and Documentation that the change has been reviewed and found c.
acceptable by the On-site Review Function.
2.
Shall become effective upon review and acceptance by the i
On-site Review Function.
I E.10 Major Chsnges to Radioactive Waste Treatment Systems (Liquid, Gaseous, Solid) (see note below)
A.
Licensee initiated major changes to the radioactive. waste systems may be made provided:
L TM change is reported in tne Monthly Operating Report for the period in which the evaluation was reviewed by the On-site Resiew Function.
The discussion of each change shall contain:
a.
A summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR 50.59; b.
Sufficient detailed information to support the reason for the change; c.
A detailed description of the equipment, components, and process involved and the interfaces ~with other plant systems; d.
An evaluation of the change which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments;
~
l e.
A comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes were made; f.
An estimate of the exposure to plant operating personnel as a result of the change; and Note:
Licensee may choose to submit this information as part of the annual FSAR update.
l Amendment No.100 6G 1
l l
l
DRESDEN III DPR-25 Amendment No. 75, 77, 79, 92, 100 6.0 ADMINISTRATIVE CONTROLS (Cont'd.)
9 Documentation of tne fact that the change was reviewed and found acceptable by the On-site Review Function.
l 2.
The change shall become effective upon review and acceptance by the On site Review Function.
i i
6-25 Amendment No.100 l
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