ML20036B963
| ML20036B963 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/26/1993 |
| From: | Weiss S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20036B962 | List: |
| References | |
| NUDOCS 9306070287 | |
| Download: ML20036B963 (38) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION n
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GPU NUCLEAR CORPORATION DOCKET NO. 50-320 THREE MILE ISLAND NUCLEAR STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. DPR-73 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment filed by GPU Nuclear Corporation (the licensee), dated March 17, 1992, with revisions dated June 18, 1992, and December 23, 1992, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission 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.
There is reasonable assurance (i) 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 Commission's regulations set forth in 10 CFR Chapter I; 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; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission regulations and all applicable requirements have been satisfied.
9306070287 930526 PDR ADDCK 05000320 P
.s 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-73 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 43, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications and all' Commission Orders issued subsequent to March 28, 1979.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY. COMMISSION DA+d
'Seym r H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Operating Reactors Support Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Appendix A and B Date of Issuance:
May 26, 1993 4
9
s ATTACHMENT TO LICENSE AMENDMENT NO. 43 FACillTY OPERATING LICENSE NO. DPR-73 DOCKET NO. 50-320 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Herove Insert ii 11 iii 111 vi vi ix ix x
x l-6 1-6 3.3-1 3.3-1 3.3-2 3.3-2 3.3-3 3.3-3 B 3/4 3-1 B 3/4 3-1 B 3/4 3-2 B 3/4 3-2 B 3/4 3-3 B 3/4 3-3 5-1 5-1 6-8 6-8 6-10a 6-10a 6-11 6-11 6-12 5-12 6-13 6-13 6-14 6-14 6-15 6-15 6-16 6-16 6-17 6-17 4
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INDEX DEFINITIONS SECTION PAGE 1.0 DEFINITIONS - (Continued) 1.21 CONTAINM ENT IS OLATION............................. 1 l.22 OFFSITE DOSE CALCULATION MANUAL (ODCM) '.............. 1-6 1.23 MEMBER (S) OF THE PUBLIC
...........................1-6'
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1.24 UN R ESTRI CTED A REA................................. 1-6 1.25 SITE BOUNDARY...................................
1-6 FACILITY MODES (TABLE 1.1)................................ 7 FREQUENCY NOTATION (TABLE 1.2)........................... 18
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1 4
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THREE MILE ISLAND - UNIT 2 ii Amendment 43
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INDEX MMITING CONDITIONS FOR OPERATION SECTION PAGE 3.0 A PPLICA BILITY.................................... 3.0-1 3.1 WATER INJECTION COOLING AND REACTIVITY CONTROL SYSTEMS 3.1.1 BORATION CONTROL.............................. 3.1-1 Borated Cooling Water Injection.......................... 3.1-1 Boron Concentration - Reactor Coolant System.................
3.1-2 Boron Concentration - Fuel Transfer Canal...................
3.1-3 Boron Concentration - Spent Fuel Pool "A"...................
3.1-3 3.3 INSTRUMENTATION 3.3.1 NEUTRON MONITORING INSTRUMENTATION.............
3.3-1 Intermediate and Source Range Neutron Flux Monitors............
3.3-1 3.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM IN STRUM ENTATION............................... 3.3-1 3.3.3 MONITORING INSTRUMENTATION.....................
3.3-1 Meteorological Instrumentation..........................
3.3-1 Essential Parameters Monitoring Instrumentation...............
3.3-2 Chlorine Detection Systems............................. 3.3-2 Fire Detection Instrumentation...........................
3.3-2 3.4 REACTOR COOLANT SYSTEM 3.4.1 REACTOR COOLANT LOOPS..........................
3.4-1 3.4.2 REACTOR VESSEL WATER LEVEL MONITORING...........
3.4-1 3.4.9 PRESSURE /TEh 2RATURE LIMITS.....................
3.4-1 Reactor Coolant System
.............................. 3.4-1 3.5 COMMUNICATIONS 3.5.1 CONTROL ROOM................................. 3.5-1 3.6 CONTAINMENT SYSTEMS 3.6.1 PRIM ARY CONTAINMENT...........................
3.6-1 Containment Integrity................................ 3.6-1 Containment Isolation................................ 3.6-4 1
THREE MILE ISLAND - UNIT 2 iii Amendment 43
INDEX Ed.EEE SECTION PAGE 3/4.0 APPLIC ABILITY................................. B 3/4.0-1 3/4.1 WATER INJECTION COOLING AND REACTIVITY CONIROL SYSTEMS 3/4.1.1 BORATION CONTROL AND BORATED COOLING WATER I NJ ECTION................................. B 3/4.1 - 1 3/4.3 INSTRUMENTATION 3/4.3.1 NEUTRON MONITORING INSTRUMENTATION........ B 3/4.3-1 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM. B 3/4.3-1 INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION................ B 3/4.3-1 Meteorological Monitoring Instrumentation.............. B 3/4.3-1 Essential Parameters Monitoring Instrumentation........... B 3/4.3-1 Chlorine Detection Systems........................ B 3/4.3-1 Fire Detection Instrumentation...................... B 3/4.3-2 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 REACTOR COOLANT LOOPS..................... B 3/4.4-1 3/4.4.2 REACTOR VESSEL WATER LEVEL MONITORING B 3/4.4-1 3/4.4.9 PRESSURE! TEMPERATURE LIMITS................ B 3/4.4-1 THREE MILE ISLAND - UNIT 2 vi Amendment 43
INDEX 4DMINISTRATIVE CONTROLS SECTION PAGE 6.0 ADMINISTRATIVE CONTROLS............................
6 6.1 R ES PONSIBIIJT.X.....................................
6-1 P
6.2 ORGANIZATION 6.2.1 G PUNC Organization...............................
6-1 6.2.2 TMl-2 Organization................................
6-1 6.3 UNIT STAFF OUALIFICATIONS
............................6-3
- 6. 4 TR A I NI N G...........................................
6-3 6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL..................
6-3 6.5.1.10 R ecord s........................................
6-5 6.5.1.11 Q u ali fi cation s....................................
6-5 6.5.2 INDEPENDENT SAFETY REVIEW.....................
6-5 6.5.2.1 Function........................................6-5 6.5.2.5 Responsibilities...................................
6 '
6.5.2.7 R ecord s........................................
6-7 6.5.2.8 Qualifications for Independent Safety Reviewers...............
6-7 (Upon Implementation of IOSRG) 6.5.3 A U D ITS.......................................
6-7 6.5.3.2 R ecord s...............................
6-3 6.5.4 SAFETY REVIEW GROUP (SRG) (Until Implementation of IOSRG).
6 6.5.4.1 Fu n c t i on........................................
6-8 6.5.4.2 Organi zation.....................................
6-9 6.5.4.3 Respon sibilities...................................
6-9 6.5.4.6 A u th o ri ty.......................................
6-9 6.5.4.7 Qualifications....................................
6-9 6.5.4.8 R ecord s............................,............
6-10 6.5.5 INDEPENDENT ONSITE SAFETY REVIEW GROUP (IOSRG).... 6-10 6.5.5.1 Fu n cti o n......................................
6-10 6.5.5.2 Organization....................................
6-10 6.5.5.3 Respon sibility...................................
6 10 6.5.5.4 A u th ority......................................
6-10a i
6.5.5.5 Qualifications................................... 6-10a 6.5.5.6 R ecord s.......................................
6-10a THREE MILE ISLAND - UNIT 2 ix Amendment 43
INDEX ADMINISTRATIVE CONTROLS i
SECTION PAGE 6.6 REPORTABLE EVENTS ACTION.......................... 6-10a 6.8 PROCEDURES AND PROGRAMS.......................... 6-10a 6.9 REPORTING REOUIREMENTS 6.9.1 ROUTINE REPORTS AND REPORTABLE OCCURRENCES 6-13 6.9.1.1 Annual Radiological Environmental Operating Report............ 6-13 6.9.1.2 Annual Radioactive Effluent Release Report 6-13 6.9.1.4 Ann ual Reports..................................
6-14 6.9.2 SPECIAL REPORTS..............................
6-15 6.10 R ECO3D RETENTION................................
6-15 6.1 I R ADI ATION PROTECTION PROGR AM...................,.. 6-16 6.12 HIGH R A DI ATION ARE A..............................
6-16 6.13 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-17 THREE MILE ISLAND - UNIT 2 x
Amendment 43
l.0 DEFINITIONS 1.21 CONTAINMENT ISOLATION shall exist when:
a.
Each penetration is:
1.
Closed by an accessible manual valve, a welded or bolted blind flange, or a deactivated automatic valve secured in the closed position to provide isolation of each penetration, or; 2.
Open per an approved procedure but can be closed pursuant to SpeciGcation 1.21.a.l. Controls shall be implemented to minimize the time the penetration is allowed open and to specify the conditions for which the penetration is open.
Penetrations shall be expeditiously closed upon completion of the ccmditions specified in the approved procedures.
b.
The Equipment Hatch is closed and sealed.
c.
Each Containment Airlock is OPERABLE pursuant to Specification 3.6.1.6.
1.22 The OFFSITE DOSE CALCULATION MANUAL (ODCM) shall contain the methodology
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and parameters used in the calculation of off-site doses resulting from radioactive gases and liquid efnuents, in the calculation of gaseous and liquid ef0uent monitoring Alarm / Trip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Jrograms r,equired by Section 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating Report and the Annual Radioactive EfDuent Release Report required by Specifications 6.9.1.1 and 6.9.1.2, respectively.
1.23 MEMEER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the GPU System, GPU contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries.
1.24 UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes.
1.25 SITE BOUNDARY shall be that line beyond which the land is neither owned, nor leased, nor otherwise controlled by GPU Nuclear.
THREE MILE ISLAND - UNIT 2 1-6 Amendment 43
LI_MITR[G_CQbiDITIONS FOR OPERATION Q
3.3 INSTRUMENTATION 3.3.1 NEUTRON MONITORING INSTRUMENTATION INTERMEDIATE AND SOURCE RANGE NEUTRON FLUX MONITORS 2
3.3.1.1 As a minimum, the intermediate and source range neutron monitoring instrumentation channels of Table 4.3-1 of the RECOVERY OPERATIONS PLAN shall be OPERABLE.
APPLICABILITY: MODE 1 ACTION:
a.
With the number of source range neutron monitoring channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement of Table 4.3-1 of the RECOVERY OPERATIONS PLAN, restore the inoperable channel to OPERABLE status within 30 days.
b.
With no source range neutron monitoring channels OPERABLE, suspend all activities involving CORE ALTERATION, verify compliance with the boron concentration requirements of Specification 3.1.1.2 at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by a mass balance calculation and at least once per 7 days by a chemical analysis and restore at least one source range neutron monitoring channel to OPERABLE status within 7 days.
c.
With no intermediate range neutron monitoring channels OPERABLE, restore at least one-intermediate range channel to OPERABLE status 'vithin 7 days.
3.3.2 ENGINEERED 5AFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Deleted 3.3.3 MONITORING INSTRUMENTATION METEOROLOGLCAL INSTRUMENTATION t
3.3.3.4 The meteorological moni;oring instrumentation channels shown in Table 4.3-5 of the RECOVERY OPERATIONS PLAN shall be OPERABLE.
APPLICABILITY: MODES 1 AND 2 ACTION:
With any of the above required meteorological monitoring channels inoperable, restore the inoperable channel (s) to OPERABLE status within 7 days.
THREE MILE ISLAND - UNIT 2 3.3-1 Amendment 43
LIMITING CONDITIONLFOR OPERAJION ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION r
3.3.3.5 The Essential Parameters Monitoring Instrumentation shall be OPERABLE in accordance with the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN.
APPLICABILITY: MODE 1 ACTION:
For instrumentation not in accordance with the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN, restore the inoperable instrument (s) to the requirements of Table 4.3-7 of the RECOVERY OPERATIONS PLAN within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
CHLORINE DETECTION SYSTEMS 3.3.3.7 Two Chlorine Detection Systems, with their alarm / trip setpoints adjusted to actuate at a chlorine concentration of less than or equal to 5 ppm, shall be OPERABLE:
a.
One at the air intake tunnel, and b.
One at the Control Room air supply duct.
APPLICABILITY: MODE 1 ACTION:
With one or more Chlorine Detection Systems inoperable, within I hour initiate and maintain operation of the Control Room Emergency Ventilation System in the recirculation mode of operation; restore the inoperable detection system to OPERABLE status within 30 days.
ElRE DETEfTION INSTRUMENTATION 3.3.3.8 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 4.3-11 of the RECOVERY OPERATIONS PLAN shall be OPERABLE.
APPLICABILITY: MODES 1,2 and 3 ACTION:
With the number of OPERABLE fire detection instruments less than required by Table 4.3-11 of the RECOVERY OPERATIONS PLAN, insure that an alternate instrument with the same coverage is OPERABLE, or; 1.
Within I hour, establish a fire watch patrol to inspect the zone with the inoperable instrument (s) at least once per hour, and 2.
Restore the inoperable instrument (s) to OPERABLE status within 14 days.
THREE MILE ISLAND - UNIT 2 3.3-2 Amendment 43 l
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THREE MILE ISLAND - UNIT 2 3.3-3 Amendment 43
3/4.3 INSTBJJMENTATION BASFJ 3/4.3.1 NEUTRON MONITORING INSTRUMENTATION The neutron monitoring instrumentation, which was included in the normal Reactor Protection System Instrumentation, provides information regarding the shutdown status of the core and it will be used to monitor changes in neutron generation.
3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATlOH Deleted 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public.
3/4.3.3.5 ESSENTIAL PARAMETERS MONITORING INSTRUMENTATION The OPERABILITY of the Essential Parameters Monitoring Instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables. Reactor Coolant System temperature indication is provided outside the' Control Room in the event that Control Room habitability is lost.
3/4.3.3.7 CHLORINE DETECTION SYSTEMS The OPERABILITY of the chlorine detection systems ensures that an accidental chlorine release will be detected promptly and the Control Room Emergency Ventilation System will automatically isolate the Control Room and initiate its operation in the recirculation mode to provide the required protection.
THREE MILE ISLAND - UNIT 2 B 3/4 3-1 Amendment 43
3/4.3 INSTRUMENTATION BASES 3f/_4J.3.8 and 3/4.3.3.9 FIRE DETECTION INSTRUMENTATION OPERABILITY of the Fire Detection Instrumentation ensures that adequate warning capability as required by the TMI-2 Fire Protection Program Evaluation, is available for the prompt detection of fires. The capability is required in order to detect and locate fires in their early stages. Prompt detection of fires is an integral element in the overall facility fire protection program.
In the event that a portion of the Fire Detection Instrumentation is inoperable, the establishment of frequent nre patrols in the affected areas is required to provide detection capability until the inoperable instrumentation is returned to service. For purposes of ALARA considerations, remote mechanisms (e.g., CCTV coverage) may be utilized to perform the fire patrol. However, the inoperabilty of this instrument would not affect the capability to maintain the safe shutdown condition of the plant nor the ability to prevent offsite releases greater than 10 CFR 100 limits.
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THREE MILE ISLAND - UNIT 2 B 3/4 3-2 Amendment 43
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THREE MILE ISLAND - UNIT 2 B 3/4 3-3 Amendment 43 w-
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5.0 DESIGN FEATURES _
i 5.1 SITE EXCLUSION SITE 5.1.1 The exclusion area is shown on Figure 5.1-1.
LOW POPULATION ZONE 5.1.2 The low population zone is shown on Figure 5.1-2.
SITE BOUNDARY FOR GASEOUS EFFLUENTS 5.1.3 The SITE BOUNDARY for gaseous effluents shall be as shown in the ODCM.
SITE BOUNDARY FOR LIOUID EFFLUENTS 5.1.4 The SITE BOUNDARY for liquid effluents shall be as shown in the ODCM.
5.2 CONTAINMENT CONFIGURATION 5.2.1 The reactor containment building is a steel lined, reinforced concrete building of cylindrical shape, with a dome roof and having the following design features:
a.
Nominalinside diameter = 130 feet b.
Nominal inside height = 157 feet c.
Minimum thickness of concrete walls = 4 feet d.
Minimum thickness of concrete roof = 3.5 feet Minimum thickness of concrete floor pad = 13.5 feet e.
f.
Nominal thickness of steel liner = 1/2 inches g.
Net free volume = 2.1 x 106 cubic f,t DESLON PRESSURE AND TEMPERATURE 5.2.2 The reactor containment building is designed and shall be maintained for a maximum internal pressure of 2 psig and a temperature of 286*F.
THREE MILE ISLAND - UNIT 2 5-1 Amendment 43
smagmanoanacamwoae j
d.
During Modes 1,2, and 3, the performance of activities required by the Recovery Quality Assurance Plan to meet the criteria of Appendix "B",10 CFR 50. The audit frequency shall be at least once per 24 months.
During Mode 1, the Emergency Plan and implementing procedures. The audit frequency e.
shall be at least once per 12 months.
f.
Deleted.
g.
During Modes 1,2, and 3, the Radiation Protection Plan and implementing procedures.
The audit frequency shall be at least once per 12 months.
h.
During Modes 1,2, and 3, the Fire Protection Program and implementing procedures. The audit frequency shall be at least once per 24 months.
i.
During Modes 1, 2, and 3, an independent fire protection and loss prevention program inspection and technical audit shall be performed annually utilizing either qualified offsite licensee personnel or an outside fire protection firm.
j.
During Modes 1,2, and 3, an inspection and technical audit of the fire protection and loss prevention program, by an outside qualified fire consultant at intervals no greater than 3 years.
k.
During Modes 1,2, and 3, any other area of unit operation considered appropriate by the SRG (until implementation of IOSRG), the Manager, SRG's immediate supervisor, the IOSRG, other managers reporting directly to the Office of the Director TMI-2, the Office of the Director TMI-2, or the Office of the President - GPUNC. Any other areas required to be audited by QA will be identified to the appropriate QA Management level.
I.
The ODCM and implementing procedures at least once per 24 months.
RECORDS 2
6.5.3.2 Audit reports encompassed by Section 6.5.3.1 shall be forwarded for action to the management positions responsible for the areas audited and either the SRG, (until implementation of IOSRG) or the IOSRG (upon its implementation), within 60 days after completion of the audit.
The SRG, (until implementation of IOSRG) or the IOSRG will review specified audits performed by QA and make corrective action recommendations as appropriate.
fL5.4 SAFETY REVIEW GROUP (SRG)
FUNCTION 6.5.4.1 The SRG shall be a full-time group of engineers, independent of the Site Operations and Engineering staff, and located onsite within the TMI-2 division. (See Organization Plan Figure 1.2.)
APPLICABILITY 6.5.4.1.1 Until implementation of IOSRG.
THREE MILE ISLAND - UNIT 2 6-8 Amendment 43
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' AUTHORITY 6.5.5.4 The IOSRG shall have access to the unit and unit records as necessary to perform its evaluatione and assessments. Based on its reviews, the IOSRG shall provide recommendations to the management positions responsible for the areas reviewed.
OUALIFICATIONS 6.5.5.5 The IOSRG engineers shall have either: (1) a Bachelor's Degree in Engineering or the.
Physical Sciences and three years of professional level experience in the nuclear power field including technical supporting functions, or (2) eight years of appropriate experience in nuclear power plant operations and/or technology. Credit toward experience will be given for advance degrees on a one-to-one basis up to a maximum of two years.
RECORDS 6.5.5.6 Reports of evaluations and assessments encompassed in Section 6.5.5.3 shall be prepared, approved, and transmitted to the Office of the Director, TMI-2, the division vice-president responsible for nuclear safety assessment and the management positions responsible for the areas reviewed.
6.6 REPORTABLE EVENTS ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and/or. a report submitted pursuant to the requirements of Section 50.73 of 10 CFR Part 50, and b.
Until implementation ofIOSRG, each REPORTABLE EVENT shall be' investigated '
and reviewed by the SRG, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence. A report shall be submitted to the Manager, SRG's immediate supervisor and the Office of the Director, TMI-2. Upon impleme.mtion of IOSRG, each REPORTABLE EVENT shall undergo an independent safety review, by a qualified ISR. This review may be performed after the fact.
c.
Deleted.
6.7 SECTION DELETED 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
a.
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Revision 2, February 1978.
b.
Recovery Operations Plan implementation.
Surveillance and test activities of safety-related equipment and radioactive waste c.
management equipment.
THREE MILE ISLAND - UNIT 2 6-10a Amendment 43
w w w w n s ~ m w m m wr-a 6.8.2.1 Each procedure and any change to any procedure prepared pursuant to 6.8.1, shall be prepared, reviewed and approved in accordance with 6.5 and will be reviewed periodically as required by ANSI 18.7 - 1976.
6Property "ANSI code" (as page type) with input value "ANSI 18.7 - 1976.</br></br>6" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..8.2.2 Deleted.
6.8.3.1 Temporary changes to procedures of 6.8.1 may be made provided that:
i l
The intent of the original procedure control is not altered, and a.
b.
(1) For those procedures which affect the operational status of unit systems or equipment, the change is approved by two members of the unit management staff, at least one of whom holds a Senior Reactor Operator's License. (Note: The requirement for a Senior Reactor Operator's License applies during Mode 1 only.)
If one of the two above signatures is not by a supervisory person within the Department having cognizance of the procedure being changed, the signature of that supervisory person within the department will also be required, or
- 2) For those procedures which do not affect the operational status of unit systems or equipment, the change is approved by two members of the responsible organization.
If one of the two above signatures is not by a section manager / director within the Department having cognizance of the procedure being changed, the signature of that section manager / director within the department will also be required, and The change is documented, Independent Safety Review completed, and the required
)
c.
reviews and approvals are obtained within 14 days, and d.
Those changes to procedures required by Specification 3.9.13 are submitted to the NRC for review within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following approval by the management level specified for implementation by Sectic16.5.1.9.
6.8.4 The following programs shall be established, implemented, and maintained:
I a.
Radioactive Efnuent Controls Program A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBER (S) OF THE PUBLIC from radioactive effluents as low as is reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, THREE MILE ISLAND - UNIT 2 6-11 Amendment 43
ppmnsomaocxmgmmen 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2.
3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, 4)
Limitations on the annual and quanerly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid efnuents-released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50,-
5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)
Limitations on the operability and use of the liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARY conforming to the doses associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous efDuents from each unit to areas.beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50, 9)
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from tritium and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I to 10 CFR Part 50.
b.
Radiolofical Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) veriGcation of the accuracy of the ef0uent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix I to 10 CFR Part 50, and (3) include the following:
THREE MILE ISLAND - UNIT 2 6-12 Amendment 43
ADMINIS i k A llVh CON I RUL5 i
1)
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the
- ODCM, 2)
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census, and 3)
Participation in an Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
6.9 REPORTING REOUIREMENTS ROUTINE REll0RTS AND REPORTABLE OCCURRENCES 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted in accordance with 10 CFR 50.4 unless otherwise noted.
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT' 6.9.1.1 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 2 6.9.1.2 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
/
' A single submittal may be made for a multi-unit station.
A single submittal may be made for a multi-unit station. The submittal should combine those 2
sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
THREE MILE ISLAND - UNIT 2 6-13 Amendment 43
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ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below during the previous calendar year shall be submitted prior to March 1 of each year.
6.9.1.5 Reports required on an annual basis shallinclude:
a.
A tabulation of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated manrem exposure according to work and job functions,2 e.g., reactor operations and surveillance, in-service 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 whole body dose received from external sources shall be assigned to specific major work functions.
b.
The following information on aircraft movements at the Harrisburg International Airport:
1.
The total nuriber of aircraft movements (takeoffs and landings) at the Harrisburg Imernational Airport for the previous twelve-month period.
2.
The total number of movements of aircraft larger than 200,000 pounds, based on a current percentage estimate provided by the airport manager or his designee.
RADIATION SAFETY PROGRAM REPORT 6.9.1.6 Deleted.
REPORTABLE OCCURRENCES 6.9.1.7 Deleted.
PROMPT NOTIFICATION WITH WRITTEN FOLLOWUP 6.9.1.8 Deleted 1 A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common to all units at the station.
2 This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
THREE MILE ISLAND - UNIT 2 6-14 Amendment 43
ADMINi$1RAilVb CON A RULb l
IERTY DAY WRITTEN REPORTS 6.9.1.9 Deleted.
REPORTING REOUIREMENTS FOR INCIDENT WHICH OCCURRED ON MARCH 28.1979 6.9.1.10 Section deleted. All reporting requirements completed.
SJPECIAL REPORTS 6.9.2 Special reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.
6.10 RE_ CORD RETENTION 6.10.1 The following records shall be retained for at least five years:
a.
Records of sealed source and fission detector leak tests and results.
b.
Records of annual physical inventory of all sealed source material of record.
c.
Records of changes made to the procedures required by Specifications 6.8.1.d and e.
6.10.2 The following records shall be retained as long as the Licensee has an NRC license to operate or possess the Three Mile Island Facility.
Records and logs of unit operation covering time interval at each power level, a.
b.
Records and logs of principal maintenance activities, inspection, repair and replacement of principal items of equipment related to nuclear safety and radioactive waste systems.
c.
ALL REPORTABLE EVENTS submitted to the Commission.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
Records of changes made to the procedures required by Specifications 6.8.1.a, b, c.
c, and f.
f.
Radiation Safety Program Reports and Quarterly Recovery Progress Reports on the March 28,1979, incident.
' g.
Records of radioactive shipments.
h.
Records and logs of radioactive waste systems operations.
THREE MILE ISLAND - UNIT 2 6-15 Amendment 43
ADMINISTRATIVE CONTROLS i.
Records and drawing changes reflecting facility design modifications made to systems and equipment described in the Safety Analysis Report, TER, SD, or Safety Evaluation previously submitted to NRC.
j Records of new and irradiated fuel inventory, fuel transfers and assembly burnup histories.
k.
Records of transient or operational cycles for those unit components designed for a limited number of tran.,ients or cycles.
1.
. Records of reactor tests and experiments.
m.
Records of training and qualification for current members of the unit staff.
n.
Records ofin-service inspections performed pursuant to these Technical Specifications.
o.
Records of Quality Assurance activities required by the Operating Quality Assurance Plan.
p.
Records of reviews performed for changes made to procedures or equipment or reviews of tests and experiments pursuant to 10 CFR 50.59.
q.
Records of meetings of the Plant Operation Review Committee (PORC) and the General Review Committee (GRC) and reports of evaluations prepared by the SRG or e
by the IOSRG, if applicable to TMI-2.
r.
Records of the incident which occurred on March 28,1979.
s.
Records of unit radiation and contamination surveys, t.
Records of radiation exposure for all individuals entering radiation control areas.
u.
Records of gaseous and liquid radioactive material released to the environs.
1 v.
Records of reviews performed for changes made to the OFFSITE DOSE' CALCULATION MANUAL.
6.11 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATION AREA P
In lieu of the " control device" or " alarm signal" required by Paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area'shall be controlled as specified in the Radiation Protection Plan.
THREE MILE ISLAND - UNIT 2 6-16 Amendment 43
sammaaoenana,scapmapa (L13 OFFSITE DOSE CALCULATION MANUAL (ODCM)
Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2 v. This documentation shall contain:
1)
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 1
2)
A determination that the change will maintain the level of radioactive effluent
)
control required by 10 CFR 20.106,40 CFR Part 190,10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by GPU Nuclear management.
c.
Shall be sutunitted to the Commission in the form of a complete, legible copy of the entire ODCM a!. a part d or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made..
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month / year) the change was implemented.
1 THREE MILE ISLAND - UNIT 2 6-17 Amendment 43
ellTACHMENT TO LICENSE AMENDMENT NO. 43 FACILITY OPERATING LICENSE NO. DPR-73 QQCKET NO.' 50-320 Replace the following pages of the Appendix B Technical Specificat ns with the attachea pages.
The revised pages are identified by amendment number.and contain vertical lines indicating the area of change.
Remove Insert i
i ii ii 1-1 1-1 1-2 1-3 1-4 2-1 2-1 2-2 2-3 2-4 2-5 2-6 2 2-8 2-9 2-10 2-10a 2-10b i
2-10c 2-10d 2-11 2-12 2-13 2-14 2-15 2-15a 2-15b 2-15c 2-16 3-1 3-1 3.2-1 3.2-2 3.2-3 3.2-4 3.2-5 3.2-6 3.2-7 3.2-8 3.2-9 3.2-10 3.2-11 3.2-12 5-3 5-3 5-4 5-4 5-5 5-5 5-6 5-6 5-7 5-7 5-8 5-8 5-9 5-9 l
l
_______u ENVIRONMENTAL TECHNICAL SPECIFICATIONS TABLE OF CONTENTS SECTION PAGE 1.0 DEFINITI ONS....................................
1 - 1 2.0 LIMITING CONDITIONS FOR OPERATION................
2-1 3.0 ENVIRONMENTAL MONITORING......................
3-1 4.0 SPECIAL STUDES AND REQUIREMENTS
................4-1 4.1 RESIDUAL CHLORINE STUDY PROGRAM................
4-1 4.2 THERM AL PLUME MAPPING.........................
4-3 i
4.3 HYDRAULIC EFFECTS
.............................4-4 l
4.4 EROSION CONTROL INSPECTION......................
4-5 l
4.5 HERBICIDE APPLICATIONS..........................
4-6 4.6 EXCEPTIONAL OCCURRENCES.......................
4-7 4.6.1 UNUSUAL OR IMPORTANT ENVIRONMENTAL EVENTS 4-7 4.6.2 EXCEEDING LIMITS OF OTHER RELEVANT PERMITS......... 4-7 5.0 ADMINISTRATIVE CONTROLS........................
5-1 5.1 RESPONSIBILITY 5.1 5.2 O R G A NI Z ATI ON..................................
5-1 l
5.3 REVIEW A ND A U DIT..............................
5-1 5.3.1 INDEPENDENT REVIEW............................
5-1 5.3.2 AUDIT RESPONSIBILITY............................
5-3 5.4 STATE AND FEDERAL PERMITS AND CERTIFICATES......... 5-3 5.5 PROCEDURES 5-3 5.6,
STATION REPORTING REQUIREMENTS..................
5-6 5.6.1 ROUTINE REPORTS...............................
5-6 5.6.2 NONROUTINE REPORTS............................
5-7 THREE MILE ISLAND - UNIT 2 i
AMENDMENT NO. 43
JC7eUJGE10)E1C10)CD Dh'0C ~ '
SECTION PAGE 5.6.2.a PROM PT REPORT................................. 5-7 5.6.2.b THIRTY D AY REPORT.............................. 5-7 5.6.2.c CONTENT OF NONROUTINE REPORTS.................. 5-7 5.7 CHANGES IN ENVIRONMENTAL TECHNICAL SPECIFICATIONS AhT PERMITS................................. 5-8 5.7.1 CHANGE IN ENVIRONMENTAL TECHNICAL SPECIFICATIONS..
5-8 5.7.2 CHANGES IN PERMITS AND CERTIFICATIONS.............
5-8 5.8 RECORDS RETENTION............................. 5-8 THREE MILE ISLAND - UNIT 2 ii AMENDMENT NO. 43
1.0 DEFINITIONS NPDES Permit: NPDES Permit is the National Pollutant Discharge Elimination System Permit No. PA0009920 issued by the Environmental Protection Agency to Metropolitan Edison Company. This permit authorized Metropolitan Edison Company to discharge from TMINS, controlled waste water into the waters of the Commonwealth of Pennsylvania.
o e
THREE MILE ISLAND - UNIT 2 1-1 AMENDMENT NO. 43
e g,
2.0 LIMITING CONDITIONS FOR OPERATION Deleted
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us 3.0 ENVIRONMENTAL MONITORING W
Deleted 4
THREE MILE ISLAND UNIT 2 3-1 AMENDMENT NO, 43
5.3.2 AUDIT RESPONSIBILITY D
Deleted 5.4 STATE AND FEDERAL PERMITS AND CERTIFICATES Section 401 of PL 92-500, the Federal Water Pollution Control Act Amendment of 1972 requires any applicant for a Federal license or permit to conduct any activity which may result in any discharge into navigable waters to provide the licensing agency a certification from the State having jurisdiction that the discharge will comply with applicable provisions of Sections 301 302 306 and 307 of the FWPCA. Section 401 of PL 92-500 further requires than any certi6 cation provided under this section shall set forth any efnuent limitations and other limitations, and monitoring requirements necessary to assure that any applicant for a Federallicense or permit will comply with the applicable limitations.
Certifications provided in accordance with Section 401 set forth conditions on the Federal license or permit for which the certification is provided. Accordingly, the licensee shall comply with the requirements set forth in the 401 certi6 cation dated November 9,1977 or its currently applicable revision, issued to the licensee by the Pennsylvania Department of Environmental Resources, which requires, among other things, that the licensee comply with efnuent limitations stipulated in NPDES permit PA-0009920, effective January 30, 1975.
Subsequent revisions to the permits and/or certi6 cations will be accommodated in accordance with the provisions of Subsection 5.7.2.
5.5 PROCEDURES Deleted 5.6 STATION REPORTING REOUIREMENTS 5.6.1 ROUTINE REPQRTS Deleted 5.6.2 NONROUTINE REPORTS A report shall be submitted in the event that an Exceptional Occurrence as specified in Section 4.6 Report shall be submitted under one of the report schedules described below.
occurs.
5.6.2.a PROMPT REPORT Those events specified as prompt report occurrences shall be reported within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmission to the NRC followed by a written report to the NRC within 30 days.
THREE MILE ISLAND - UNIT 2 5-3 AMENDMENT NO. 43
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I i
5.6.2.b IlllRTY DAY EVENT Nonroutine events not requiring a prompt report as described in Subsection 5,6.2.a, shall be reported to the NRC either within 30 days of their occurrence or within the time limit specified by the reponing requirement of the corresponding certification or permit issued pursuant to Sections 401 or 402 of PL 92-500, whichever time duration following the nonroutine event shall result in the earlier submittal.
5.6.2.c CONTENT OF NONROUTINE REPORTS Written 30-day reports and, to the extent possible, the preliminary telephone, telegraph, or facsimile.
reports shall (a) describe, analyze, and evaluate the occurrence, including extent and magnitude of l'
the impact, (b) describe the cause of the occurrence, and (c) indicate the corrective action (including.
any significant changes made in procedures) taken to' preclude repetition of the occurrence and to prevent simihr occurrences involving similar components or systems.
5.7 CHANGES IN ENVIRONMENTAL TECHNICAL SPECIFICATIONS AND PERMITS 5.7.1 CHANGE IN ENVIRONMENTAL TECHNICAL SPECIFICATIONS.
Request for changes in environmental technical specifications shall be submitted to the NRC for review and authorization per 10 'CFR 50.90. The request shall include an evaluation of the environmentalimpact of the proposed change and a supportingjustification. Implementation of such requested changes in ETS shall not commence prior to incorporation by the NRC of the new specifications in the license.
5.7.2 CHANGES IN PERMITS AND CERTIFICATIONS Changes or addition to required Federal, State, local, and regional authority permits and certificates for the protection of the environment that pertain to the requirements of these ETS shall be reponed to the NRC within 30 days. In the event that the licensee initiates or becomes aware of a request for changes to any of the water quality requirements, limits or values stipulated in any certification or permit issued pursuant to Sections 401 and 402 of PL 92-500 which is also the subject of an ETS reporting requirement, NRC shall be notified concurrently with.the authorizing agency. The-notification to the NRC shall include an evaluation of the environmental impact of the revised requirement, limit or value being sought.
If, during NRC's review of the proposed change, it is determined that a potentially severe environmental impact could result from the change, that NRC will consult with the authorizing agency to determine the appropriate action to be taken.
THREE MILE ISLAND - UNIT 2 5-4 AMENDMENT NO. 43
)
.i i
5.8 REDRDS RETENTION Records and logs relative to the following areas shall be made and retained throughout the term of the operating license. These records and logs shall be made available to NRC on request, a.
Records and drawing changes detailing station and unit design changes made to system and equipment which could potentially affect the environment.
b.
Records of all data from environmental monitoring, surveillance and study activities required by these environmental technical specifications.
t b
b
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TIIREE MILE ISLAND - UNIT 2 5-5 AMENDMENT NO. 43
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