ML20214L173
| ML20214L173 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 08/28/1986 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Kane W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| TAC-62065, NUDOCS 8609090467 | |
| Download: ML20214L173 (2) | |
Text
pyr$- ol W August 28, 1986 Docket No. 50-289 MEMORANDUM FOR: William F. Kane, Director Division of Reactor Projects. Region I FROM:
John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B
SUBJECT:
REVIEW 0F TSCR 151 FOR TMI-1 Enclosed is an amendment request by GPUN for TMI-1 dated July 29, 1986 (as corrected on August 21,1986). The amendment was submitted to revise unit staff organizational responsibilities and titles in the Administrative section of the TS.
Region I is requested to review this amendment request and provide a safety evaluation suitable for use in an amendment and a SALP input. Work for this effort is to be charged to TAC 62065. The requested completion date is November 28, 1986. This date has been tentatively discussed with Randy Blough cf your staff.
If you need additional information concerning this request, please contact the assigned TMI-1 Project Manager, Thierry Ross at 492-8324.
- culoIW*u cIG:a 3r.
Aui 2. sig;e John F. Stolz, Director PWR Project Directorate #6 Division of PWR Licensing-B
Enclosures:
As Stated cc w/ enclosures:
F. Schroeder ll D_ISTRIBUTION (Docket fit _e)
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Regional Resource Detennination If review would benefit from unique regional knowledge or proximity to site, but is not being assigned for regional review, state reason:
APPROVALS NAME INITIALS DATE 1.
Project !!anager N N.S 5 Y'W' 4
- /$M6 2.
Project Director 7, S fo /2-b NM 3.
Review Branch Chief 8 WAVEAC4m A (remove any attached review ge_cf on I i
material and indicate U
assigned reviewer below)
REVIEWER'S NAME RAMS IflITIALS
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= 4.
An Regional Div. Dir.
M MEm 8 /ane i
5.
Other (as required) 6.
Return to originator FROM Mall STOP PH0hE 7 /2.s s A-2/8 J/ 92 -83 AY 0
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ACCESSIDit NDR: 0608040225 DOC.DATE. 86/07/29 NOT AR I ZED: YES DOCKET o FACIL DO 209 Three Mile Island Nuclear Station, Unit 1,
Metropolit 05000289 AU1 H. NAtlE AUTHOR AFFJLIATION HUKILL,H.D.
General Public Utilities Corp. - GPU Servi c e Corp.
REC IP. NAM:
RECIPIEN1 AFFILIATIGN STOL'Z, J. !'
PWR Project Directorate 6 SUD JECl : Forwards application to amend Li c ense DPR-50, c onsi s ti ng of lech Spec Change Request 151, r evi s a ng Tech Sp ec Pag es 6-3 &
6-?1 to ref)ett current staff organization.NSHC &
Certificate of Svc also encl.Fer paid.
DISTRIliU1 ION CODE: AOOID col'IES RECE1VED. LTR ENCL SI ZE:
hh T I1 LE: OR Gubmi ttal: General Distribution NOT ES: R Conte: I c y.
AE OD/ORNSTE IN: icy. LPDR Sc y s.
00000289 RECIPIFNT COPIES RECIPIENT COPIES ID CODE /NAME L1TR ENCL ID CODE /NAME LTTR ENCL
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1 EXlERNAL: EOhG DRUSKE,G 1
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NG 0 6 1986 TOTAL NUMTiER OF COP 3ES REGUIRED: LTTR 36 ENCL 32
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GPU Nuclear Corporation N
f Post Office Box 48c l
Route 441 South Middletown, Pennsylvania 17057-o191 717 944-7621 TELEX 84 2386 July 29, 1986 Writer's Direct Dial Nuniber:
5211-86-2081 Office of Nuclear Reactor Regulation Attn: John F. Stolz, Director PWR Projects Directorate No. 6 U. S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Stolz:
f Three Mile Island Nuclear Station, Unit I, (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.151 Enclosed are three originals and forty conformed copies of Technical Specification Change Request No.151.
Also enclosed is one signed copy of the Certificate of Service for this request to the chief executives of the township and county in which the facility is located, as well as the Bureau of Radiation Protection.
Pursuant to 10 CFR 50.91(a)(1), we enclose our analyses, using the standards in 10 CFR 50.92 of significant hazards considerations. As stated above, pursuant to 10 CFR 50.91(a) of the regulations, we have provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant hazards considerations to Thomas Gerusky, the designated representative of the Commonwealth of Pennsylvania.
Pursuant to the provisions of 10 CFR 170.21, enclosed is a check for $150.00 as payment of the fee associated with Technical Specification Change Request No. 151.
Sincerely,
. D.
ukill Vice President & Director, TMI-l HDH/DVH/spb
Enclosures:
- 1) Technical Specification Change Request No.151
- 2) Certificate of Service for Technical Specification Change Request No.151
- 3) Check No. 221952 GI kWb)Llk'O h cc:
J. Thoma ?
v s y v y -- h r R. Conte i
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation l
1
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 LICENSE NO. DPR-50 GPU NUCLEAR CORPORATION f
This is to certify that a copy of Technical Specification Change Request No.151 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 mail, addressed as follows:
Mr. Jay H. Kopp, Chairman Mr. Frederick S. Rice, 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. Thomas Gerusky, Director PA. Dept. of Environmental Resources Bureau of Radiation Protection P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORPORATIO g
BY:
Vic~e PreW: dent & Director, TMI-l l
DATE:
July 29.1986 i
METROPOLITAN EDISON C04PANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 s
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change' Request No.151 This Technical Specification Change Request is submitted in support of LMnsee'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:
)
Vi'ce Prssident & Director, TMI-l
?
Sworn and Subscribed his J N tobeforemel21 i
day of Ou 1986.
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Notary PAblic SI: ARON P. EROWN. WOTARY PUBLIC i
MIDDLETOWN 80RO. DAUPHIN COUNTY MY COMMIS$10N EXPIRES JUNE 12.1989 pl.
.h b @
j NemNr. Pennsyfvania Association of Notaries g/j
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I.
Technical Specification Change Rec;uest No.151 GPUNC requests that the revised pages 6-3, 6-21 and the revised Figure 6-2 replace the existing pages 6-3, 6-21 and Figure 6-2 in the TMI-1 Technical Specifications.
II.
Reascns for Change This TSCR proposes the following changes for the following reasons:
1.
Delete the position of Training Coordinator.
This position was created to coordinate the development of the training programs for the Operations and Maintenance Departments.
These training programs have been fully developed and implemented and the responsibility for continuation of the training programs lies with the individual department managers and the Training Department.
Therefore, the position of Training Coordinator is no longer a(
requi red.
2.
Change the title of the " Radiological Controls Foreman" to " Field i
Operations Supervision". This change is being proposed so as to make this position title in TMI-l consistent with the corporate organizational philosophy of GPUNC in this area. Field Operations Supervision includes the Deputy Field Operations Manager position (when filled) and the Group Radiological Controls Supervisors. The functional duties of the Field Operations Supervision will be consistent with the duties of the Radiological Controls Foreman.
3.
Remove the reference to " Type of License (R0 or SRO)" from the Shif t Supervisor, Shift Foreman and Control Room Operator boxes on Figure 6.2.
This change is proposed so as to remove any confusion caused by these references.
In the past, the reference appearing with the Shif t Foreman box on Figure 6.2 has caused confusion. The reference indicates "R0", however, Technical Specification 6.2.2 (a), Table 6.2-1, indicates that the position can be held only by an individual "...who is either SR0 licensed or R0 licensed and has completed the SR0 training program". Technical Specification 6.2.2 (a), Table 6.2-1, and Technical Specification 6.2.2 (d) will still identify the minimum shif t crew composition and types cf licenses to be held by these individuals.
4.
Change the title of the " Manager, Plant Operations TMI-1" to " Plant Operations Director, TMI-1".
This title change is being proposed to reflect the addition of responsibilities to this office (i.e.,
Plant Chemistry).
It also reflects this individual's promotion I
within the company.
5.
Place the Plant Chemistry Manager, TMI-l under the Plant Operations Director, TMI-1. The Plant Chemistry Manager, TMI-l had been reporting to the Operations and Maintenance Director, TMI-l while the Plant Chemistry Department was being upgraded. This upgrade has been completed and with the return to operation of TMI-1, the TMI-l Plant Chemistry Department is being placed under the control of the Piant Operations Director, TMI-1.
l
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III.
Safety Evaluation Justifying Changes The changes proposed in this TSCR are administrative in nature. They are intended to make the TMI-l unit staff organization more consistent with the GPUN corporate organizational philosophy. The proposed cisanges contained herein do not alter the functional duties of the TMIL1 unit staff.
These changes, therefore, do not reduce the margin of safety provided by the Technical Specifications.
IV.
No Significant Hazards Considerations These proposed changes are similar to Example i of " Amendments Not Likely to Involve Significant Hazards Considerations", Federal Register Volume 48, No. 67 at 14870, dated April 6,1983.
The proposed Amendment is administrative in nature, does not affect plant design or operation, and does not involve modifications to plant' equipment or changes that would affect plant safety analyses. This TSCR constitutes a minor change to the organizational structure.
Therefore, the proposed Amendment involves no significant hazards considerations in that it does not:
1.
The proposed changes do not affect plant equipment or systems and therefore will not involve a significant increase in the probability or consequences of an accident previously evaluated or 2.
The proposed changes do not affect plant equipment or systems and therefore will not create the possibility of a new or different kind of accident from any accident previously evaluated or 3.
The proposed changes do not alter functional duties and therefore will not involve a significant reduction in a margin of safety.
V.
Implementation l
It is requested that the Amendment authorizing this change become effective upon issuance.
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A Site Fire Brigade ## of at least 5 members shall be maintained onsite at all times. The Site Fire Brigade shall not include members of the minimum shif t crew necessary for safe shutdown of the unit and any personnel required for other essential functions during a fire emergency.
h.
The Shif t Technical Advisor shall serve in an advisory capacity to the Shif t Supervisor on matters p.ertaining to the engineering aspects assuring safe operation of the unit.
6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI /ANS 3.1 of 1978 for comparable positions unless otherwise noted in the Technical Specifications. Licensed operators shall meet the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
[-
Individuals who do not meet ANSI /ANS 3.1 of 1978, Section 4.5, are not.
considered technicians or maintenance personnel for purposes of determining qualifications but are permitted to perform work for which qualification has been demonstrated.
6.3.2 The Manager-Radiological Controls or the Deputy shall meet or exceed the qualifications of Regulatory Guide 1.8 of 1977.
Each Radiological Controls Technician / Supervisor shall meet or exceed the qualifications of ANSI-N 18.1-1971, paragraph 4.5.2/4.3.2, or be formally qualified through an NRC approved TMI-l Radiation Controls training program. All Radiological Controls Technicians will be qualified through training and examination in each area or specific task related to their radiological controls functions prior to their performance of those tasks.
6.3.3 The Shif t Technical Advisors shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in unit design, response and analysis of transients and acci de nts.
6.4 TRAINING l
l 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Manager, Plant Training - TMI and shall meet or exceed the requirements and recommendations of Regulatory Guide 1.8 of 1977 and Appendix "A" of 10 CFR Part 55 except that Radiological Controls training may be under the direction of the Vice President - Radiological and Environmental Controls. Licensed operators shall meet the supplemental requirement specified in Section A and C of Enclosure 1 of the March 28, 1980 NRC letter to all licensees.
6.4.2 A training program for the Fire Brigade shall be maintained under the direction of the Manager, Plant Training - TMI and shall meet or exceed the requirements of Section 27 of the NFPA Code - 1976.
6.5 REVIEW AND AUDIT 6.5.1 TECHNICAL REVIEW AND CONTROL 6-3 Amendment Nos. 77,37,53,//,$2
m.
Records of the service lives of all safety related hydraulic snubbers including the date at which the service life commences and associated installation and maintenance records.
n.
Records for Environmental Qualification which are covered under the provision at paragraph 6.15.
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 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR 20:
a.
Each High Radiation Area as defined by paragraph 20.202 (b) (3) shall be barricaded and conspicuously posted as a High Radiation
- (
Area, and personnel desiring entrance shall obtain a Radiation Worli Permit (RWP). Any individual or group of individuals entering a High Radiation Area shall (a) ::se a continuously indicating dose rate monitoring device or (b) use a radiation dose rate integrating device which alarms at a pre-set dose level (entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made knowledgeable of them), or (c) assure that a radiological control technician provides positive control over activities within the area and periodic radiation surveillance with a dose rate monitoring instrument.
b.
Any area accessible to personnel where a major portion of the body could receive in any one hour a dose in excess of one thousand mrem shall be locked or guarded to prevent unauthorized entry.
The keys l
to these locked barricades shall be maintained under the administrative control of the Group Radiological Controls Supervisor on duty.
The Radiation Work Permit is not required by Radiological Controls personnel during the performance of their assigned radiation protection duties provided they are following radiological control procedures for entry into High Radiation Areas, j
6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 GPU Nuclear Corporation initiated changes to the PCP:
1.
Shall be submitted to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the changes were made. This submittal shall contain:
a.
sufficiently detailed information to justify the changes without benefit of additional or supplemental information; b.
a determination that the changes did not reduce the overall conformance of the solidified waste product to existing l
criteria for solid wastes; and 6-21 Amendment Nos. JJ, ilS, 72, 77, J@$, J@7
w GPU Nuclear Corporation t:
D,. (uclear
- =',,o"a's:48o 8
Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number:
August 21, 1986 5211-86-2138 Office of Nuclear Reactor Regulation Attn:
J. F. Stolz, Director PWR Projects Directorate No. 6 U.S. Nuclear Regulatory Commission a(
Washington, DC 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station, Unit 1 Operating License No. DPR-50 Docket No. 50-289 (Jp da t'eTo'fTe hf00 c a pp e,cif,1 c at f odfCha nge.. Re q u e s t iNonT5YY On July 29, 1986, GPU Nuclear (GPUN) submitted Technical Specification Change Request No.151, letter number 5211-86-2081.
Enclosed is a revised page 6-21 which should replace page 6-21 from the original request.
It was the intent of GPUN to revise the title of " Radiological Controls Foreman" to the " respective Radiological Controls Supervisor" as the person responsible for control of keys to high radiation areas. However, the original submittal referred to this person as the " Group Radiological Controls Superv i so r. " The enclosed page corrects this item.
The attached page with this revision should be supplemented for the original i
l page 6-21 in all copies of Technical Specification Change Request No.151.
l I
Sincerely, l
.D.,
kill Vice President & Director, TMI-l HDH/DVH/spb:0642A 9
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cc R. Con C
l Attachment GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
a o
m.
Records of the service liees of all safety related hydraulic snubbers including the date at which the service life commences and associated installation and maintenance records.
n.
Records for Environmental Qualification which are covered under the provision at paragraph 6.15.
6.11 RADI ATION 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 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203 (c) (2) of 10 CFR 20:
Each High Radiation Area as defined by paragraph 20.202 (b) (3) a.
shall be barricaded and conspicuously posted as a High Radiation Area, and personre,1 desiring entrance shall obtain a Radiation Work Permi t (RWP). Any individual or group of individuals entering a High Radiation Area shall (a) use a continuously indicating dose rate monitoring device or (b) use a radiation dose rate integrating device which alarms at a pre-set dose level (entry into such areas with this monitoring device may be made af ter the dose rate level in the area has been established and personnel have been made knowledgeable of them), or (c) assure that a radiological control technician provides positive control over activities within the area and periodic radiation surveillance with a dose rate monitoring instrument.
b.
Any area accessible to personnel where a major portion of the body could receive in any one hour a dose in excess of one thousand mrem shall be locked or guarded to prevent unauthorized entry.
The keys to these locked barricades shall be maintained under the administrative control of the respective Radiological Controls Supervisor on duty.
The Radiation Work Permit is not required by Radiological Controls personnel during the performance of their assigned radiation protection duties provided they are following radiological control procedures for entry into High Radiation Areas.
6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
6.13.2 GPU Nuclear Corporation initiated changes to the PCP:
1.
Shall be submitted to the NRC in the Semiannual Radioactive Effluent Release Report for the period in which the changes were made. This submittal shall contain:
a.
sufficiently detailed information to justify the changes without benefit of additional or supplemental information; b.
a determination that the changes did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes; and C
o I n# L tS) 6-21 wvv
.- sm 7
Amendment Nos. JJ, 35, 77, 77, 106, 107