ML20127M286
| ML20127M286 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/18/1993 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20127M275 | List: |
| References | |
| NUDOCS 9301280168 | |
| Download: ML20127M286 (37) | |
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i h113TROPOLITAN EDISON COMPANY l
JERSEY CENTRAL POWER AND LIGIIT COMPANY PENNSYLVANIA ELECTRIC CDMPANY GPU NUCLEAR CORPORATION ROCKET NO. 50-320 -
I[llWE MILE ISLAND NUCLEAR STATION. UNIT NO. 2 POSSESSION ONLY LICENSIl License No, DPR-73 1.
The Nuclear Regulatory Commission (the Commission) having found that:
A.
The application for the Possession Only License filed by Metropolitan Edison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company, and GPU Nuclear Corporation (the Licensecs) complies with the.
standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Conunission's niles and regulations set fonh in 10 CFR Chapter I, and all required notifications to other agencies or bodies have been duly made; H.
The facility wiil be maintained in confonnity with the applicati.n, as amended,
-the provisions of the Act; and the rules and regulations of the Conunission; C.
There is reasonable assurance: (i) that the activities authorized by this Possession Only License can be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the niles.
and regulations of the Conunission; D.
GPU Nuclear Corporation is technically qualified to engage in the activities authorized by this Possession Only License in accordance with the niles and regulations of the Conunission; E.
The Licensees are financially qualified to engage in the activities authorized by this Possession Only License in accordance with the rules and regulations of the -
a Conunission; l
P.
The Licensees have satisfied the applicable provisions 10 CFR. Part 140, L
" Financial Pmtection Requirements and Indemnity Agreements," of the L
Commission's regulations; l-L n
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9301280168.930118 -
PDR ADOCK 05000320 P-PDR-j
G.
The issuance of this Possession Only License will not be inimical to the common defense and security or to the health and safety of the public; II.
After weighing the environmental, economic, technical, and other benefits of the facility against environmental, and other costs and considering available alternatives, the issuance of Possession Only License No. DPR-73 subject to the conditions for protection of the environment set fonh herein is in accordance with 10 CFR Part 51 of the Conunission's regulations and all applicable requirements have been satisfied; and L
The possession of byproduct and special nuclear material and receipt, possession, and use of source material as authorized by the license will be in accordance with the Commission's regulations in 10 CFR Pans 30,40, and 70, including 10 CFR Sections 30 33, 40.32, 70.23, and 70.31.
2.
Possession Only License No. DPR-73 dated._
, is hereby issued to Metropolitan Iklison Company, Jersey Central Power and Light Company, Pennsylvania Electric Company, and GPU Nuclear Corporation to read as follows:
A.
This license applies to the Thn e Mile Island Nuclear Station, Unit 2, (the facility) owned by the Metropolitan Iklison Company, Jersey Centnd Power and Light Company, and Pennsylvania Electric Company, and maintained by the GPU Nuclear Corporation.
The facility is located on Three Mile Island!in the Susquehanna River, in Ixndonderry Township, Dauphin County, Pennsylvania, about ten miles southeast of Harrisburg, Prior to entry into Post-Defueling Monitored Storage (PDMS), the facility is described in the Final Safety _ Analysis Repon as supplemented and amended, the various Recoscry System Descriptions and Technical Evaluation Repons, and the Environmental Repon as supplemented and amended. Upon entry into PDMS, the facility is described in the PDMS Safety Analysis Repon as supplemented and amended and the Environmental Report as supplemented and amended.
D.
SuSject to the conditions and requirements incorporated herein, the Commission hereby licenses:
(1)
GPU Nuclear Corporation, pursuant to Section 103 of the Act and 10' CFR Pan 50, " Licensing of Production and Utilization Facilities," to
_ possess but not operate the facility; (2)
GPU Nuclear Corporation, Metropolitan Edison Contpany, Jersey Central Power and Light, and Pennsylvania Electric Company to possess the -
facility at the designated location in Dauphin County, Pennsylvania, in accordance with the procedures and limitations set fonh in this license;
(3)
GPU Nuclear Corporation, pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive, possess, and use at any time any scaled sources for i
radiation monitoring equipment calibration; (4)
GPU Nuclear Corporation, pursuant to the Act and 10 CFR Parts 30,40, and 70, to receive, possess, and use in amounts as requinxl any-byproduct, source, or special nuclear material without' restriction to chemical or physical form, for sample analysis or instmment calibration or associated.wius radioactive apparatus or components; and (5)
GPU Nuclear Corponition, pursuant to the Act and 10 CFR Pans 30,40, and 70, to possess, but not separate, such byproduct and special nuclear i
materials which remain at the facility subsequent to the cleanup following.
the March 28,1979, accident.
C.
This license shall be deemed to contain and is subject to the conditions speclSed in the following Commission regulations in 10 CFR Chapter 1, except as i
nxemptions have been granted: Part 20. Section 30.34 of Part 30, Section 40.41 of Pan 40, sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; and is subject to all applicable provisions of the Act and to the mies, regulations, i
and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specined or incorpontted below:
(1)
Technical Specificalletls Prior to and until entry into PDMS, the Recovery Technical SpeciGcations contained in Appendices A and B, as revised through Amendment No. 42, are hereby incorporated in the license. Upon entry into PDMS, the Technical Specifications ~ contained in -PDMS Appendix A Issued as Amendment No. O are incorporated in the license. The Licensee shall maintain the facility in accordance with the Technical Speci0 cations and all Commission Onters issued subsequent to the date of this Possession Only License.
D.
This license is effective as of the date of issuance and shall expire at midnight, April 19, 2014.
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Three hiile Island Nuclear Station, Unit 2 (Tht!-2)
Opemting License No. DPR-73 Docket No. 50-320 PmpanLLkense Amendnirn!
The Licensee requests that the attached changed pages of the proposed Possession Only License (POL) replace the corresponding pages in the proposed License Amendment sutunitted via GPU Nuclear letter C312 91-2080, dated October 9,1991.
DscriplintLOLChalmc The change evaluated here is the inclusion of Facility hiode 3 in the proposed POL.
RunenfrLChange issuance of the Th112 POL does not depend upon entry into Post Defueling hionitored Storage (PDhtS). In fact, after the accident, the Commission suspended GPU Nuclear's authority to operate 'Ih11-2, except in its shutdown condition. Therefore, this request for a POL that is applicable to Facility hiode 3 and PDhtS is consistent with the current licensing basis and facilitates the tmnsition from hinde 3 to PDhtS.
SafelE.lh'aination Justifying Charigo
'fh11-2 is currently in Facility hiode 3, which is defined by the Recovery Technical Specifications as the condition wherein the Thil-2 Reactor Vessel and Reactor Coolant System are defueled to the extent reasonably achievable, the possibility of criticality in the Reactor Building is precluded, and no canisters containing core material are stored on the Thil 2 site.
Th11-2 is not an operating plant; it has been in Afode 3 s'nce April 27,1991. The proposed Possession Only I huse requires adherence to the same ti gulatory requirements as the current Opemting License. Therefore, no reduction in attention to sfoty will occur as a result of this license amendment request.
No Significimt Ha7 anis Considera11on
- 10 CFR 50.92 provides the criteria which the Commission uses to perform a No Significant-Ilazards Consideration. 10 CFR 50.92 states that an amendment to a facility license involves No Significant IIazards if operation of the facility in accordance with the proposed amendment would not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated, or 2.
Create the possibility of a new or different kind of accident from any accident previously evaluated, or l
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Involve a significant reduction in a margin of safety.
The proposed inclusion of Facility Mode 3 in the POL does not involve any physical changes to the facility. This is primarily an administrative change. Based on this, GPU Nuclear concludes that the proposed change does not:
1.
Involve a significant increase in the probability or consequences of an accident previously evaluated. The previous accident evaluations would be applicable regardless of whether TMI-2 is governed by an operating license or a POL. No affect on these evaluations results from this proposed license amendment. Therefore, this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
Create the possibility of a new or different kind of accident from any accident previously evaluated. As previously stated, including Facility Mode 3 in the POL does not involve any physical changes to the facility and therefore, the possibility of a new or different j
kind of accident is not created.
1 3.
Involve a significant reduction in a margin of safety during PDMS. The margins of safety currently applicable to TMI-2 Facility Mode 3 apply whether TMI-2 is governed by an operating license or a POL No change to any margin of safety results from this proposed license amendment. Therefore, there will not be a reduction in the margin of l
safety.
Based on the above analysis, it is concluded that the proposed changes involve No Significant Hazards Considerations as defined by 10 CFR 50.92.
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UNITED STATES OF Ah1 ERICA NUCLEAR REGULATORY COMhilSSION IN Tlin MATI11R OF DOCKET NO. 50-320 LICENSB NO. DPR GPU NUCLEAR This is to certify that a copy of this revision to the proposed Possession Only License for Three Mile Island Nuclear Station Unit 2 has been Oled with the U.S. Nuclear Regulatory Conunission and served to the chief executives of 1) Londonderry Township, Dauphin County, Pennsylvanla;
- 2) Dauphin County, Pennsylvania; and 3) the designated ofDelal of the Columonwealth of.
Pennsylvania by deposit in the United States inail, addressed as follows:
Mr. Jay II. Kopp, Chainnan Mr. Russell L. Sheaffer, Chainnan Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, PA 17057 Harrisburg, PA 17120
~ Mr. William Dornsife, Director Bureau of Radiation Protection PA Dept. of Environmental Resources i
P. O. Box 2063
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Ilarrisburg, PA 17120 l
GPU NUCLEAR ny < M e er"
// / ?H-f Director, Corporate Seivicesu
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POST-DEFUELING MONLTORED STORAGE SAFETY ANALYSIS REPORT
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List of Effective Pages L%GP, Ah!ENDMENT 1%QE AMENDMENT Eupplement 1 SI-27 3
I Sl-1 2
S t-28 9
SI-2 3
SI-29 3
S I-3 3
SI-30 3
SI-4 10 SI-31 3
S1-5 6
SI-32 3
SI-6 3
SI-33 3
SI-7 3
SI-34 9
S1-8 13 SI-35 10 Sl 9 3
SI-10 3
EunnkulenL2 SI-ll 3
S2-1 15 SI-12 3
S2-2 11 r
Sl-13 9
. S2-3 7-1 S1-14 9
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S2-15 11 SI-26 9
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EDXt-DEFUELING MONITORED STORAGF SAFETY ANAllSIS REPORT List of Effective Pages EbftB Ah1ENDMENT EAfiB AMENDMENT S c 17 5
SupplemenL1 S2-18 5
S2-19 5
S5-1 12 S5-2 12 S.hG! ring 1L3 S5-3 12
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S5-4 12 S3-2 7
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S5-6 12 S3-4 10 S5-7 4 '.
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S5-9 12 S3-7 10 S5-10 12 S3-8
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S5-13 12 S3-ll 11 S5 44 12 S3-12 11 S5>l5 12 S3-13 9
SS-16 12 S3-14 15 SS-17 12 S5-18 12 Supplement 4 S5-19 12 S4-1 15 SS-20 13 S4-2 10
' SS-21 12 S4-3 11 SS-22 12 S4-4 13 S5-23 12 55-24 12 S5-25 12 AMENDMENT 16 - JANUARY 1993
POST-DEFUE!JNG MONITORED STORAGE SAFl?TY ANALYSIS REPOEI List of Effective Pages
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[%QE AMENDMEBI PAGE AhliiN_D_MERI S5-26 12 S5-27 12 S5-28 12
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S5-31 12 S5-32 12 S5-33 12 S5-34 12 S5-35 12 S5-36 12 S5-37 12 S5-38 12 SS-39 12 S5-40 12 S5-41 12 5
. AMENDMENT 16 - JANUARY 1993
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-TABLE OF CONTENTS -
- 1 IMITING' CONDITIONS FOR'PDMS AND SURVEII. LANCE REOUIREMENTS SECTION IITJJ; 1%CE 3/4.0 APPLICAlllLITY 3/4.C-3/4.1 CONTAINMENT SYSTEMS 3/4.1 1 3/4.1.1 PRIMARY CONTAINMENT.
3/4.1-1 CONTAINMENT ISOLATION 3/4.1-1 UNFILTERED LEAK RATE TESTING 3/4.1-2 CONTAINMENT AIR LOCKS 3/4.1-3 3/4.2 REACTOR VESSEL FU:!L 3/4.2-1 3/4.2.1 REACIDR VESSEL FUEL REMOVAL / REARRANGEMENT 3/4.2-1 1
3/4.3 CRANE OPERATIONS 3/4.3 1 q
3/4.4.
ACCIDENT GENERATED WATER 3/4.4-1 1
3/4,5 SEALED SOURCES 3/4.5-1 3/4.5.1 SEALED SOURCE INTEGRITY 3/4.5-1 l
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I lii AMENDMENT 16 i JANUARY 1993 t
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.... - -. -.... ~. -. -,.
e TABLE OF CONTEtQi BASES FOR LIMITING CONDITIONS FOR PDMS AND SURVEILLANCE REOUIREMiiNTS
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.- SECTION.
TITLE 1%fE -
3/4.0 APPLICABILITY B3/4.0-1 3/4.1 CONTAINMENT SYSTEMS
.B3/4.1-1 3/4.1.1 PRIMARY CONTAINMENT B3/4.1 ;
CONTAINMENT ISOLATION
'B3/4.1-1 UNFILTERED LEAK RATE TESTING B3/4.1-1
- CONTAINMENT AIR LOCKS B3/4.1-1 9
3/4.2 REACTOR VESSEL FUEL B3/4.2-1
+
3/4.2,1 REACTOR VESSEL FUEL REMOVAL / REARRANGEMENT
.B3/4.2 -
3/4.3 CRANE OPERATIONS B3/4.3 1 f
3/4.4 ACCIDENT GENERATED WATER B3/4.4-1 f.
?/4.5 SEALED SOURCES B3/4.5-1 3/4.5.'
SEALED SOURCE INTEGRITY B3/4.5-1 l '
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. AMENDMENT 16 - JANUARY 1993 -
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IAllLji OF CONTENTS
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.i ADMINISTRATIVE CONTROL.S -
- SECrlON TIIl2 -
PMiG-6.7 PROCEDURES AND PROGRAMS 6-7 h
6,8 REPORTING REQUIREMEN'IS 6-10 6.8.1 ROUTING REPORTS 6-10
-1 ANNUAL RADIOLOGICAL ENVIRONMENTAL 6-10 OPERATING REPORT ANNUAL RADIOACTIVE EFFLUENT RELEASE 6 10 REPORT i
ANNU AL REPORTS 6-11 DIANNUAL REPORTS 6-11 6.8.2 SPECIAL REPORTS 6-11 6.8.3 NONROUTINE REPORTS
'6-11 PROMPT REPOP.TS -
6-11 THIRTY DAY EVENT REPORTS 6-11 CONTENT OF NONROUTINE REPORTS 6-11 6.9 RECORD RETENTION 6-12 l
6,10 RADIATION PROTECTION PROGRAM 6-14 6.11 filGil RADIATION AREA 6-14 s
6.12 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6-14 6.13 EXCEPTIONAL OCCURRENCES 6-15 6.13.1=
UNUSUAL OR IMPORTANT ENVIRONMENTAL EVENTS
'645
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6.13.2 EXCEEDING LIMITS OF RELEVANT PERMITS 6-15 g
-6.14 STATE AND FEDERAL PERMITS AND CERTIFICATES
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vii AMENDMENT 16 - JANUARY 1993-
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- ' 1.0 DEFINITIONS:
7
~ FREOUENCY NOTATION i
1.8 The FREQUENCY NOTATION specified for the perfonnance of surveillance requirements shall correspond to the intervals defined in Table 1.1.
CONTAINMENT ISOLA 110N l.9 CONTAINMENT ISOLATION shall exist when:
a.
Each penetration is:
1.
Closed by a manual valve, a welded or bolted blind flange, a deactivated automatic valve secured in the closed position or other equivalent mechanical closure to-provide isolation of each penetration, or 2.
Open and the pathway to the environment provided with a HEPA Diter, or -
3.
Open in accordance with approved procedures. 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 conditions specined in the approved procedures, and l:
b.
The Equipment Hatch is closed, and c.
Each Containment Airlock is operable pursuant to Technical Speci6 cation 3.1.1.3.
i-DATCH RELEASE 1.10 A BATCH RELEASE is the discharge of a discrete volume.
CONTINUOUS RELEASli i
L 1.11 A CONTINUOUS RRIRASB is the discharge of a non-discrete volume, e.g., from a-volume or system that has an input flow during the continuous release.
4 OFF-SITE DOSE CALCULATION MANUAL 1.12 The OFF-SITE DOSE CALCULATION MANUAL _ (ODCM)' shall' contain' the l
methodology and parameters used in the calculation'of off-site doses resulting from radioactive gaseous and liquid. effluents, in.the calculation of gaseous' and liquid effluent monitoring L
alann/ trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program.-
L The ODCM shall also contain (1) the programs required by Section 6.-7.4 and (2) descriptions P
of the infonnation that should be included in the Annual Radiological Environmental Operating and Semi-annual Racticactive Effluent Release Reports required by_ Specifications 6.8.1.2 and 6.8.1.3.
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- 1-2 AMENDMENT 16 - JANUARY 1993
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' 3/4 L CONTAINMENT SYEIT41S 3/4.1:1-- PRIM ARY CONTAINMI!JiT -
fGNTAINhlENT ISOLATION
. LIMITING CONDITIONS FOR PDMS 3.1.1.1 Primary CONTAINMENT ISOLATION shall be maintWned.
APPLICABILITY: PDMS ACTION:
With CONTAINMENT ISOLATION not in accordance with requirements, restore -
CONTAINMENT ISOLATION within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SURVEIJ4ANCE REOUIREMENTS 4.1.1.1 Primary CONTAINMENT ISOLATION shall be verified quarterly with the following -.
exceptions:
Isolation valves that are loded closed shall be verified annually on 'a quarterly a.
STAGGERED TEST BASIS. If a valve is found to tw out of position, a check of all-locked closed isolation valves shall be perfonned.
b.-
An independent verification of all isolation valve position changes shall be performed.
- c. -
Bolted or welded blind flanges which form a containment isolation boundary and the
-Equipment Hatch shall be visually inspected for-signs of degradation and/or leakage.
every five years on an annual STAGGERED TEST BASIS. If a problem is discovercd:
with a flange, a check of all bolted or welded blind flanges shall be perfonned.
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3/4,1-1 AMENDMENT 16 - JANUARY-1993
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s 11NELLTERED LEAILRAIlllT; STING JJhtlTING CONDITIONS FOR_PDh1S 3.1.1.2 The unfiltered leak rate from Conuinment with the RB Breather closed shall be less than 1/100 of the rate through the RB Breather.
AIS11 CAB 11JIY: PDMS ACIt0N:
If the tuifiltered leak mte from Containment with the RB Breather closed is greater than 1/100 of the rate through the RB Breather or if the trend indicates that the 1/100 value will be exceeded within one year, then:
- a. Identify the excessive leakage path;
- b. Make necessary repairs and/or adjustments;
- c. Perfonn an additional unfiltered leak rate test; and
- d. Prepare and submit a special report to the Commission pursuant to Specification 6.8.2 within the next 30 days.
SURVEILLANCE REQlMEAIENTS 4.1.1.2 The initial unfiltered leak rate test shall be perfonned two years following entry into PDMS. After the initial urfiltered leak rate test, the test frequency will be determined by comparing the ratios of the unfiltered leak rate to the RB Breather leak rate from previous and current tests. if the test results indicate that the ratio of unfiltered leakage to breather leakage is remaining constant or decreasing, then the next interval shall be five years, 3/4.1-2 AMENDMENT 16 - JANUARY 1993'
1
- SURVEILI.ANCR REOUIREMENTS
- 4.1.1.2_ (con't).
- If the test results indicate that the ratio of unfiltered leakage to breather leakage is increasing, i.e.,
the current ratio is girater than the previous ratio, then the next interval shall be determined by the following equation:
~
yt. y x @'M ^ E )
1 v
-R)
(Re p
the next test intersal, where:
N'
=
the current test interval, N
=
the previous ratio of unfiltered leakage to R,
=
RB Breather leakage the current ratio of unfiltered leakage to
(.
R,
=
RB Breather leakage The initial value of N shall equal two years. N' shall be the truncated integer result from the above equation, in years, but not more than five years nor less than one year,'
-3/4.1-3 AMENDMENT 16 - JANUARY 1993 D
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CONTAINMENT AIR LOCKS 11MITING COEDn'lONS FOR PDMS 3.1.1.3 Each Containment Air Lock shall be OPERABLE with at least one door closed except -
when the air lock is being used for transit entry and exit in accordance with site-approved o
procedures.
APPL 1CABJL{D': PDMS
-I ACJ1QN:
With no Containment Air Lock door OPERABLE, restore at least one door to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
SyRVElI1AELLEOUIREMENTS 4.1.1.3 Each Containment Air Lock shall be demonstrated OPERABLE at least once per three months by perfonning a mechanical operability check of cach Air Ixck Door, including a visual inspection of the components and lubrication if necessary and by visual.ly inspecting the door seals
~
for significant degradation. When both Containment Air Lock doors are opened simultaneously, verify the following conditions:
The capability exists to expeditiously close at least one Air Lock door; a.
L b.
The Air Lock doors and Containment Purge are configured to restrict the outflow.
of air in accordance with site-approved procedures; and I
c.
The Air Lock doors are cycled to ensu:e aechanical operability within seven days -
prior to opening both doors, 3/4.1-4 i
AMENDMENT 16 - JANUARY 1993 -
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3/4.5 SEALED SOURCES Ithk?S 3/4.5.1 SEALEDaSOURCE INTEGRITY The limitation on removable contamination for sources requiring leak testing, including alpha emitters, is based on 10 CFR 70,39(c) limits for plutonium. This limitation will ensure that.
- leakage from bypnxluct, source, and Special Nuclear Material sounes will not exceed allowable intake values.
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. AMENDMENT 16 - JANUARY 1993
m ADMINISTRATIVE CONTROLS I 6.7 PROCEDURES AND PROGRAMS (con't) 1.
Monitoring, sampling, analysis, and reponing 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 momtoring program are made if required by the results of the 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 environmvntal sample matrices are perfonned as =
part of the quality assurance program for environmental monitoring.
6.8 REPORTING REOUIREMENTS ROUTINE REPORTS 6.8.1 In addition to the applicable reponing requirements of Title 10, Code of Federal Regulations, the following reports shall be in accordance with 10 CFR 50.4 unless othenvise-noted. Some of the reporting requirements of Title 10, Code of Federal Regulations are repeated below.
ANNUAL RADIOLOGICAL ENVIRONMENTAI OPERATING REEORT 6.8.1.1 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 R AylOACTIVE EFFiU, ENT RELEASE REPORT
~
6.8.1.2 The Annual Radiological Effluent Release Report covering the operation of the' unit during the previous calendar year shall be submitted within 60' days after Janua y I of each year.
The report shall include a sununary of the quantities of radioactive liquid _ ane 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 Pan 50.
6-10 AMENDMENT 16 - JANUARY 1993 p
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ADMINISTRATIVE Cf)NTROLS -
6.8 RIIPORTING REOUIREMENTS (con't)
ANNUAL REPORTF 6.8.1.3-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.
Reports required on an annual basis shall include:
+
a.
A tabulation of the number of station, utility and other personnel (including contractors) -
~
receiving exposures greater than 100 mremlyr and their associated person rem exposure 2
according to work and job functions, e.g., surveillance, routine maintenance, special maintenance (the dose assignment to various duty functions may be estimates based on-pocket dosimeter, TLD, or film badge measurements).- Small exposures totaling 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.
t BIANNUAL REPOATA 6.8.1.4 Biannual repons (i.e., once every two years) covering the activities of the unit as described below during the previous two calendar years shall be submitted prior to March 1:of every other year.
Reports required on a biannual basis shall include:
- a.
All changes made to the PDMS SAR during the previous two calendar years, b.
All changes, tests, or experiments meeting the requirements of 10 CFR 50.59.
EPECIAL REPORTS 6.8.2 Special reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.
6.8.31 NONROUTINE BEPORTS A report shall be submitted in the event that an Exception! Occurrence as specified in Section 6.13 occurs. The report shall be submitted'under one of the report schedules described below.
1 A single submittal may be made for a miittiple unit station. -The submittal should combine those.
sections that are commoa to all units at the station.
2 This tabulation supplements the requirements of Anicle 20.407 of 10 CFR 20.
6-1l' AMENDMENT 16 - JANUARY = 1993 -
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ADMINISTRATIVE CONTRQJJ 6.8 REPORTING REOUIREMENTS (con't)-
ERDhll#T REPORTS 6.8,3.1 Those events speciGed 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.
THIRTY DAY EVENT REPORTS 6.8.3.2 Nonroutine events not requiring a prompt recoA as described in Subsection 6.8.3.1, shall -
be reported to the NRC cither within 30 days of their occurrence or within the time limit specified by the reporting requirement of the corresponding certification or permit issued pursuant to Sections 401 or 402 of PL 92-500, the Federal Water Pollution Control Act -(FWPCA)
Amendment of 1972, whichever time duration following the nonroutine event shall result in the earlier submittal.
CONTENT OF NONE(MJTINR.IEPORTS 6.8.3.3 Written 30-da., 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 the impact, (b) describe the cause of the occurrence, and O) indicate the corrective -
action (including any significant changes made in procedures) taken to preclude repetition of the occurrence and to prevent similar occurrences invnMng smilar components or systems.
6.9 RECORD RET 9NTION 6.9.1 The following records shall be retained for at least five years:
a.
Records of scaled source and Ossion detection leak tests and results.
b.
Records of annual physical inventory of all. sealed cource material of record.
6.9.2 The following records shall be retained as long as the Licensee has an NRC license to operate or possess the Three Mile Island facility, a.
Records and logs of unit operation covering time interval at each power level, b.
Records and logs of principal mainanance activities, inspections, repair and replacement of principal items of :quipment related to nuclear safety and-radioactive waste systems, c.
ALL REPORTABLE EVIINTS submitted to the Commission.
d.
Records of surveillance activities, inspections and calibrations required 'by these -
Technical Speci0 cations.
6-12 AMENDMENT 16 - JANUARY 1993
ADMINISTRATIVy CONTROLS 6.9 RECORD RETENTION (Con't)
Records of changes made to the procedures required by Recovery Technical e.
Specification 6.8.1 and PDMS Technical Specincation 6.7.1.
f.
Radiation Safety Pn.3 ram Reports and Quanerly Recovery Progress Reports on the March 28,1979 incident.
g.
Records of mdioactive shipments.
h.
Records and logs of radioactive waste systems operations.
i.
Records and drawing changes reflecting facility design modincations 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 irmaiated 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 transients or cycles.
I 1.
Records of reactor tests and experiments.
~
t m.
Records of training and qualification for current members of the unit stsff.
n.
Records of in-service inspections previously required by. the Technical L
Specifications.
l Records of Quality Assurance activities required by the Operating, Recovery, or o.
PDMS Quality Assurance Plans, 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 Generation Review Committee (GRC), and reports of evaluations prepared 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.
6-13 AMENDMENT 16 - JANUARY '1993
6
- ADMINISTRATIYLCDOMIBDOLS s
- 6.9 - RECORD RETENTION (Con't) u.
Records of gaseous and liquid radioactive material released to the environs.
v.
Records of reviews perfomied for changes made to the OFFSITE DOSE -
CALCULATION MANUAL.
6.10 RADIATION PROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements -
of 10 CFR Past 20 and shall be appmved, maintained, and adhered to for all operations involving -
personnel radiation exposure.
(ElI HIGH RADIATION ARPA In lieu of the " control device" or "alann 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.
6.12 OFFSITE DOSE CALCULATION MANUAL (ODCM)
SUBSTANTIVE CHANGES to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.9.2 v. This documentation shall contain:
1.
Sufficient infonnation te support the change together with the appropriate analyses or evaluations justifying the change (s) and 2.
A determination that the change:will maintain the level of radioactive-effluent control requimd by 10 CFR 20.106,40 CFR Pan 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.
Shall be submitted to the Commission in the form of a complete, legible copy of c.
the entire ODCM as a pan of or concurrent with the Semiarianal Radioactive--
Effluent Release Report fot the per od of the report in which any' change to the i
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.
]
6-14 AMENDMENT 16 - JANUARY 1993
' ADMIMSTRATIVII CONTROLS _
fdLU1CELTIONAL OCCHRRENCES UNl!SUALJllGMPORTANT_IINVEDjiMENTAL EVJINTS 6.13.1 Any occurrence of an unusual or imponant event that causes or could potentially cause significant environmental impact causally related with station operation shall be recorded and reported to the NRC per Subsection 6.8.3.1.
The following are examples of such events:
excessive bird impaction events on cooling tower structures or meteorological towers (i.e., more than 100 in any one day); onsite plant or animal disease outbreaks; unusual monally of any species protected by the Endangered Species Act of 1973; Gsh kills near or downstream of the site.
IllClillDING I,IMITS OF RIiLEVANT PERAUIS 6.13.2 Any occurrence of exceeding the limits specified in relevant pennits and cenincates issued by other Federal and State agencies which are reponable to the agency which issued the pennit shall be reported to the NRC in accordance with the provisions of Subsection 6.8.3.2.
This requirement sball apply only to topics of National Env.ironmental Protection Act (NEPA) concern within the requirements of the pennits and certiGeates noted in Section 6.15.
fnM STATEANQEIIDERAI,_PERMIIS_AND Cli[LTLFICATES Section 401 of PL 92-$00 requires any applicant for a Federal license or pennit 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 INVPCA. Section 401 of PL 92-500 further requires that any cenification provided under this section shall set forth any efGuent limitations and other limitations, and monitoring requirements necessary to assure that any applicant for a Feder;d license or pennit will comply with the applicable limitations. CertiGcations provided in accordance with Section 401 set fonh conditions on the Federal license or pennit for which the certification is provided. Accordingly, the licensee shall comply with the requirements set forth in the 401 cenification 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, tnat the licensee comply with effluent limitations stipulated in the NPDES PERMIT.
6-15 AMENDMENT 16 - JANUARY 1993
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'. ADhUNISTRATIVE CONTROLS E
_6.14 STATE AND FEDERAL PERMITS AND_CILRTIFICATES (con't)
Changes or addition to the required Federal and State pennits and certificates for the protection
~
of the environment noted in this subsection shall be reported to the NRC within 30 daysc -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 pennit issued parsuant to Sections 401 and 402 of PL 92-500,'NRC shall be notified concurrently with the authorizing j
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, the NRC will consult with the authorizing-agency to detennine the appropriate action to be taken.
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6-16 i
AMENDMENT.16 - JANUARY 1993
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