ML20096G903
| ML20096G903 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/19/1992 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20096G877 | List: |
| References | |
| GL-89-01, GL-89-1, NUDOCS 9205270035 | |
| Download: ML20096G903 (9) | |
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9 METROPOLITAN EDISON COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE-ISLAND NUCLEAR STATION, UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.194 This Technical Specification Change Request is submitted in support of Licensee's request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1.
As a part of this request, proposed replacement pages for Appendix A are also included.
GPU NUCLEAR CORPORATION BY:
Vice Presid(yt and Director, THI-1 Sworn and subscribed to before me-this 19th day of May-
, 1992.
Leh 4
D N6tary Public Twp.
Court /
My Commsson Epres AG 21,1993 Wrrtw, PennsAmrda Assodman d N:sstim
/
9205270035 920519 PDR ADOCK 05000289 P
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET N0. 50-289 GPU NUCLEAR CORPORATION-LICENSE-NO. DPR-50 CERTIFICATE OF SERVICE This is to certify that a copy of Technical Specification Change Request No.
194 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mall, addressed as follows:
Mr. Jay H. Kopp, Chairman Mr. Russell L. Sheaffer, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120
'Mr. William P. Dornsife, Acting Director PA. Dept'. of Environmental Resources Bureau of Radiation Protection P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORPORATION
!M BY:
VicePresidenyandDirector,TMi-1 DATE:
May 19, 1992 l
l
j Three Mile Island Nuclear Plant, Unit 1-(THI-1)
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.194 1.0. PROPOSED TECHNICAL SPECIFICATION CHANGE RE0 VEST (TSCR)
GPUN requests that the following pages of the THI-l Technical Specifications (Tech. Specs.) be replaced as indicated below:
Replace Paaes:
1, v, vi, 1-6, 1-7, 1-8, 3-106, 3-111, 3-118, 3-120, 3-122, 3-125, 3-126, 3-127, 4-107, 4-108, 4-117, 4-118, 4-121, 4-122, 6-11, 6-17, 6-18, 6-19, 6-20, 6-21, 6-22, 6-23, and 6-24.
(Note: Pages 6-17 through 6-24 have been re-paginated.)
Add New Paaes:
1-9, 6-lla, and 6-25 Delete Paaesi 3-121, 3-123, 3-124, 4-119, and 4-120.
2.0. DESCRIPTION OF CHANGES The following changes relocate the Radiological Environmental Monitoring Program (REMP) portion of the Radiological Environmental Tech. Specs.
-(RETS) to the Offsite Dose Calculation Manual (00CH) according to Generic Letter (GL) 89-01.
Pursuant to GL 89-01 and NUREG-1301 guidance (Reference 7.1), Revision 1 of the ODCM is included for reference. The revised ODCM, which includes the REMP, is a combined THI-l and THI-2 document.
Therefore, the sampling frequencies and locations are site based. A TSCR for THI-2 was submitted separateh.
The relocating of procedural details of the RETS to the Process Control Program (PCP), per GL 89-01, allows for concurrent implementation with the proposed TSCR.
-In addition, the REMP portion of the THI-l Tech. Specs. has been revised to be consistent with the current TMI-l radiological monitoring program, and in part with NUREG-0472.
1.
pi The Table of Contents pages have been updated to reflect the v
administrative corrections necessary for title changes, vi deletions, and page numbering changes.
2.
p 1-6 Tech. Spec. Definition 1.14, " Solidification" has been relocated to the Process Control Program (PCP), Reference 7.4.
3.
p 1-6 Tech. Spec. Definition 1.15, "Offsite Dose Calculation Manual (0DCM)" has been revised pursuant to GL 89-01.
4.
p 1-6 Tech. Spec. Definition 1.16, " Process Centrol Program (PCP)"
l has been revised pursuant to GL 89-01.
5.
p 1-7 Tech. Spec. Definition 1.18, " Ventilation Exhaust Treatment l
System" has been moved to this page due to reformatting l
requirements.
6.
p 1-8 Tech. Spec. Definition 1.24, " Operating Core Limits Report" has been moved to this page due to reformatting requirements.
]
l Three Mile Island Nuclear Plant, Unit 1 (THI-1)
Technical Specification Chance Reouest No.194 7.
p 1-9 New page' required due to reformatting.
8.
p 3-106 Tech. Spec. 3.22.1.1, " Liquid Effluent - Concentration," Part "b" of the ACTION Statement of this Tech. Spec. has been deleted.
9.
p 3-111 Tech. Spec. 3.22.2.1, " Gaseous Effluent - Dose Rate," Part "b" of the ACTION Statement has been deleted. Also, the Bases reference to infant was revised to child to be technically consistent with NUREG-0472.
10.
p 3-118 Tech. Spec. 3.22.3, " Solid Radioactive Waste" has been deleted and relocated to the Process Control Program. (Reference 7.4)
- 11. p 3-120 Tech. Spec. 3.23.1, " Radiological Environmental Monitoring 3-121 Program" (REMP) and Bases, have been deleted and relocated to the Offsite Dose Calculation Manual (0DCM), as revised.
[See Part I, Section 7]
ROTE RE: ACTION STATEMENT 'b' The ODCM reflects the correction of a mis-reference to Tech.
Spec. Table 3.23-1, as being deleted and relocated to 00CM Table 7.1 as a part of this TSCR. The appropriate reference for the Action Statement is ODCM Table 7.2, which is the current Tech. Spec. Table 3.23-2 also being deleted and relocated to the ODCM by this TSCR.
In addition, the Action Statement equation relocated to the ODCM has been changed by replacing " limit level" with
" reporting Level" in the denominator of the equation; and, the reporting reference to Tech. Spec. 6.9.1.13 in the Action Statement has been deleted and replaced in the 00CM with a requirement to submit a Special Report, which is consistent with the information requirements of Tech. Spec. 6.9.1.13.
- 12. p 3-122 Tech. Spec. Table 3.23-1 has been deleted and relocated to the 3-123 00CM as Table 7.1 " Sample Collection and Analysis 3-124 Requirements,"with the following additional changes:
The frequencies of sampling and analysis have been changed from a specified number of days to a calendar period (e.g., 7 days has been changed to weekly). A definition'of these frequencies has been added to the OOCH that allows the 25% surveillance extension consistent with Section 1.0 of the THI-l Tech. Specs.
The number of sample locations for " Direct F lation" was changed from 38 to 40.
In addition, the sat,.e locations for Waterborne (Surface and Drinking), Fish, and Food Product pathways have been revised to provide further detail about the types and locations of samples.
13.
p 3-125 Tech. Spec. 3.23.2, " Land Use Census" has been relocated to the ODCM and has been revised to be consistent with the proposed l
TSCR for TMI-2 Tech. Specs., and in part with NUREG-0472.
[See i
Part I, Section 7].
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Three Mile Island Nuclear Plant, Unit 1 (THI-1)
Technical Specification Chanae' Reauest No.194
- 14. p 3-126 Tech. Spec. Table 3.
2 has been deleted and relocated to the 00CM as Table 7.2 " Reporting Levels for Radioactivity Concentrations in Environmental Samples," with the following minor revision: (pCi/Dg) was changed to (pCi/Kg) under the column " food Products."
- 15. p 3-127 Tech. Spec. 3.23.3, "Interlaboratory Comparison," has been relocated to the ODCH.
Additionally, a sentence was added that states "only those samples and analyses which are required by Table 7.1 shall be performed."
[See Part I, Sectis.i 7].
- 16. p 4-107 Tech. Spec. 4.22.3, " Solid Radioactive Was
' has been deleted and relocated to the Process Control Program. (Reference 7.4)
- 17. p 4-108 Tech. Spec. 4.22.4, " Total Dose" Calculation, has been revised to reflect the methodology for 40 CFP 190 compliance.
- 18. p 4-117 Tech. Spec. 4.23.1, REMP " Surveillance Requirements," has been deleted and relocated to the ODCM, as revised.
[See Part I, Section 7].
- 19. p 4-118 Tech. Spec. Table 4.23-1 was deleted and relocated to the ODCM 4-119 as Table 7.3 with its title changed to " Detection Capabilities 4-120 for Environmental Sampling Analysis - Lower Limit of Detection (LLD)."
In addition, the ODCM Table Notation was revised in the last part of note
'c' by the addition of a paragraph consistent with NUREG-0472.
- 20. p 4-121 Tech. Spec. 4.23.2, Land Use " Surveillance Requirements," this specification has been deleted and relocated to the ODCM; and, a sentence was-added requiring that the result of the Land Use Census be included in the Annual Radiological Environmental
- 0perating Report. [See Part I, Section 7).
- 21. p 4-122 Tech. Spec. 4.23.3, Interlaboratory Comparison " Surveillance Requirements," has been deleted and relocated to the ODCM.
[See Part I, Section 7).
- 22. p 6-11 Tech. Spec. 6.8.1.1, " Procedures," the reference to " Regulatory l
Guide 4.15," has been revised to " Regulatory Guide 4.15, l
Revision 1".
t
- 23. p 6-lla NEW Tech. Spec. 6.8.4, " Radiological Environmental Monitoring Program," has been added pursuant to GL 89-01.
.N_ot q:
Radioactive Effluent Controls remain in the Tech. Specs. and l
are not being deleted or relocated pursuant to the allowance i
in GL 89-01.
- 24. p 6-17 Tech. Spec. 6.9.3, " Annual Radiological Environmental Operating Report," has been revised pursuant to GL 89-01, and the current specification has been relocated to the ODCM. [See Part III -
" Reporting Requirements"]. - - -
Three Mile Island Nuclear Plant, Unit 1 (TMI-1)
Technical Specification Chance Reauest No.194 25.
P 6-18 Tech. Spec. 6.9.4, " Semiannual Radioactive Effluent Release Report," has been revised pursuant to GL 89-01, and the current specification has been relocated to the ODCH.
[See Part III -
" Reporting Requirements").
26, p 6-19 Tech. Spec. 6.10 has been moved to page 6-20, and 6-20 Tech. Spec. 6.9.5 is now found in total on page 6-19, 27.
p 6-21 NEW Tech. Spec. 6.10.3, " Record Retention," has been added pursuant to GL 89-01.
28.
p 6-22 These pages have been reformatted and re-paginated for clarity.
thru p 6-25 3.0. REASONS FOR CHANGE 3.1. Changes 2-4
- T.S.
Definitions 1.14, 1.15, and 1.16; Changes 10 Tech. Specs. 3.22.3; 3.23.1,.2 and.3; j
Tech. Specs, 4.22.3 and.4; i
Tech. Specs. 4.23.1,.2, and.3 i
Changes 23 Tech. Specs. 6.8.4; 6.9.3 and.4; Chanae 27
- Tech. Soec. 6,10.3.
These changes are consistent with GL 89-01 and, for the most part, NUREG-0472, Revision 3.
Variances from NUREG-0472 reflect current monitoring practices,' unique to TMI, and are described in detail in References 7.2 and 7.3.
3.2. Chanaes 8 and 9 - Tech. Specs. 3 22.1 and.2 These changes are consistent with NUREG-0472 and Reference 7.1.
The requirement to shutdown the plant, if releases of liquid or gaseous effluent cannot be immediately restored to within Tech. Spec. limits, is deleted.
3.3. Chanae 22 - Tech. Spec. 6.8.1.i Tnis change corrects an administrative discrepancy concerning the reference to Regulatory Guide 4.15 in Tech. Spec. Section 6.0.
3.4 Chanaes 1. 5-7. 26. and 28 - Administrative These changes are administrative in nature and are required for editorial corrections, reformatting, and repagination..
I
Three Mile Island Nuclear Plant, Unit 1 (TMI-1)
Technical Specification Chanae Reouest No. 194 4.0 SAFETY EVALUATION JUSTIFYING CHANGE 4.1 Changes 2-4
- T.S.
Definitions 1.14, 1.15, and 1.16; Changes 10 Tech. Specs. 3.22.3; 3.23.1,.2 and.3; Tech. Specs 4.22.3, and 4; Tech. Specs 4.23.1,.2 and.3; Changes 23 Tech. Specs. 6.8.4; f..'.3 and.4;
[hanae '27
- Tech. Sp_qc. 6.10.3.
These changes relocate a portion of the THI-1 RETS to either the ODCM or the PCP. This change request is consistent with the guidance contained in NRC GL 89-01, dated January 31, 1989 and incorporates line-item improvements in Tech. Specs.
Additionally, the proposed changes are, for the most part, consistent with NUREG-0472. Justification for variances from this NUREG is provided in References 7.2 and 7.3.
For example, since the REMP is a site program, monitoring for Sr-90 (i.e., a TMI-2 accident generated isotope) is performed.
4.2 -Chanaes 8 and 9 - Tech. Specs. 3.22.1. and.2 The proposed change is consistent with NUREG-0472 and Reference 7.1, in that, the provisions for plant shutdown required by THI-l Tech. Spec.
3.0.1 do not apply. Operation of the plant during a liquid or gaseous effluent release would not adversely affect public health and safety since a filtered pathway and continuous effluent monitoring would be maintained.
4.3 Chanae 22 - Tech. Snec. 6.8.1.1 This change is administrative in nature to correct a discrepancy between i
Section 6.5.3.1.j and Section 6.8.1.1, which requires that the REMP procedures satisfy Regulatory Guide (RG) 4.15.
When lach. Spec. 6.8.1.i was added via License Amendment 77 (dated April 28, 1982), Revision 1 of RG 4.15 was in effect. This is still the current revision of the Guide.
The TMI REMP was developed in accordance with Revision 1; and, therefore, the annual audit of the REMP is conducted using Revision 1.
l '..
4 Three Mile Island Nuclear Plant, Unit 3 (TMI-1)
Technical Sagg.ificatjon Chanae R_gguest No.194 5.0.N0 SIGNIFICANT HAZARDS CONSIDERATIONS GPUN has determined that this Technical Specification Change Request involves no significant hazards consideration as defined by NRC in 10 CFR 50.92.
5.1 Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability of occurrence or the consequences of an accident previously evaluated.
The proposed amendment tilows relocation of portions of the RETS to either the ODCM or PCP according to the guidance contained in GL 89-01. This proposal simplifies the RETS, meets the regulatory requirements for radioactive effluent and radiological environmental monitoring, and is provided as a line-item improvement of the Tech. Specs. Variances in the RETS from NUREG-0472 have been reviewed and approved by the NRC (Reference 7.3).
Thus, this change does not increase the probability of occurrence or consequences of an accident previously evaluated.
5.2 Operation of the facility in accordance with the proposed amendment-would not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposal relocates procedural details, currently included in the Tech. Spec. Amendment, on radioactive effluent, solid radioactive wastes, environmental monitoring, and associated reporting requirements to the ODCM or PCP as appropriate.
Future changes to these procedural details in the ODCM and the PCP will be
. handled under the administrative controls for changes to these documents.
Therefore, this change has no effect on the possibility of creating a new or different kind of accident from any accident previously evaluated.
5.3.0peration of the facility in accordance with the proposed amendment would not involve a significant reduction in a sargin of safety.
The procedural details being relocated to the ODCM or the PCP are consistent with the guidance provided in GL 89-01 and NUREG-0472.
Therefore, it is concluded that operation of the facility in accordance with the proposed amendment does not involve a significant reduction in a margin of safety.
The Commission has provided guidelines on the application of the l
three standards by listing specific examples in 45 FR 14870. The proposed amendment is considered to be in the same category as example (vi) of amendments that are considered not likely to involve significant hazards consideration in that tne proposed change conforms to changes provided in NRC Generic Letter 89-01.
Three Mile Island Nuclear! Plant, Unit.1 (TMI-1)
- Technical Soecification Chance Reauest No. :194 15.3 L(Continued)
Implementation of the proposed amendment according to the: guidance contained in NRC Generic-Letter 89-01' incorporates a line-item improvement in Technical Specifications. Thus, operation of the facilityLin accordance with the proposed amendment involves no significant hazards considerations.
6.0 IMPLEMENTATION-It'is requested that-the amendment authorizing this change become effective within-60 days upon issuance to allow time for implementation of affected procedure changes.
7.0 REFERENCES
-7.1 NUREG-1301, "Offsite Dose Calculation Manual Guidance: Standard-Radiological Effluent Controls for Pressurized Water Reactors."
7.2-GPU Nuclear letter 4410-86-L-0Gordated May 16, 1986, " Technical--
Specification Change: Request..c 52."
7.3 NRC letter dated March 17, 1988, " Issuance of Amendment No. 29 to FacilityL0perating License No. DPR-73 for Three Mile Island Nuclear Station, Unit 2."
7.4 TMI-1OperatingProcedure1104-281," Waste l Solidification' Process Control Program."- :---------- --L--
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