ML20055G019
| ML20055G019 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 07/06/1990 |
| From: | Dudley R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20055G018 | List: |
| References | |
| NUDOCS 9007200060 | |
| Download: ML20055G019 (7) | |
Text
_
.' 3 .
g UNITED 8TATEs 8 .A r, NUCLEAR REGULATORY COMMISSION t ,e .wAsHINGTON, D. C. 20886
% . . . . . ,)
OMAHA PUBLIC POWER DISTRICT DOCKFT NO. 50-285 FORT CALHOUN STATION,_ UNIT,NO.,1
_ AMENDMENT TO, FACI,LITY_ 0PERATING. LICENSE Amendment No.132 License No.-DPR-40
- 1. The Nuclear Regulatory Comission (the Comission) has found that:
A. The application for amendment by the Omaha Public Power District -
(thelicensee)datedMarch 19, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this license 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 Comission's regulations and all applicable requirements have been satisfied.
9007200060 900706 PDR ADOCK 05000285 p PDC
- p. .
s
~ '
.g.
) 2. Accordingly, Facility Operating License No. DPR-40 is amended by changes
~
to the Technicr.1 Specifications as indicated.in the. attachment to this license amendrent, and paragraph 3.B. of Facility Operating License No.
DPR-40 is hereby amended to read as follows:
B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.132 , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. The license amendment is effective as of its date of issuance. .
FOR THE NUCLEAR REGULATORY COMMISSION Richard F. Dudley, Acting Director Project Directorate IV-1.
Division of Reactor Projects - III, IV, Y and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes.to the Technical Specifications-Date of Issuance: July 6,1990
i L
' \ _' ' . f _{'e e l o --
.f.
ATTACHMENT TO LICgSE ' AM_ENRENT_NO 3 ,,jg - ,
.q I? FACILITY OPERATING OCENSE NO. DPR-40 i 1.
t DOCKET NO_.. 50. .28.5 i
Revise Appendix "A". Technical Specifications as indicated below. The revised ;
pages are.idantified by amendsent number and cc.itain vertical lines indicating )
the area of change. l h Remove Pages I. n. sert .Pa.ge.s.
5-5 5-5 i 5-8 5 5-19a 5-19a 1 l
1
.1 I-
^1
. I l
1 i i
)
o l
l i
l 1
l i
l
. +
1 go. ,
s 5.0 ADMINISTRATIVE CONTROLS 5.1 Reinonsibility 5.1.1 The Manager - Fort Calhoun Station shall be responsible for overall facility operation and shall delegate in writing the succession to this respor.sibility during his absence.
5.2 Oroanization 5.2.1 Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the.
safety of the nuclear power plant,
- a. Lines of authority, responsibility, and communication shall be a .
established and defined for the highest management levels through-intermediate levels to and incidding all operating organization positions. These relationships shall be documented and updated, as appropriate, in the-form of organizational charts, functional-descriptions of departmental responsibilities and relationships,-
and job descriptions for key personnel positions, or in eqvivalent forms of documentation. These requirements shall be documented in.
- the USAR.
- b. The Manager - Fort Calhoun Station shall be responsible for overall unit safe operation and shall have control over those onsite activities necessary for safe operation and maintenance of the-pl ant,
- c. The Senior Vice President - shall have corporate responsibility l for overall plant nuclear safety and shall take any measures -
needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical . support to the plant to ensure nuclear safety,
- d. The individuals who train the operating staff and those who carry out health physics ano quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.
5.2.2 Plant Staff .
The plant staff organization shall be as described in Chapter 12 of the.
USAR and shall function as follows:
- a. The minimum number and type of licensed and unlicensed operating Table 5.2-1..
5-1 Amendment No. 57,7%,75,JpJ,JJE,JJ9,132
5.0 ADMINISTRATIVE CONTROLS 5.5.1.7 b. Render determinations in writing with regard to whether or not each item considered under 5.5.1.6(a) through (e) above constitutes an unreviewed safety question,
- c. Provide imediate written. notification to the Division Manager
- Nuclear Operations and the Safety Audit and Review Comittee of disagreement between the Plant Review Committee and the Manager - Fort Calhoun Station; however, the Manager - Fort Calhoun Station shall have responsibility for resolution of such disagreements pursuant to 5.1.1 above.
Records 5.5.1.8 The Plant Review Committee shall maintain written minutes of each meeting and copies shall be invided to the Division Manager -
Nuclear Operations and Chairman of the Safety Audit and Review Comittee.
5.5.2 Safety Audit and Review Comittee (SARC) ,
' Function 5.5.2.1 The Safety Audit and Review Committee shall function to provide the independent review and audit of designated activities in the areas of:
- a. nuclear power plant operation
- b. nuclear engineering a
- c. chemistr; and radiochemistry
- d.
- metallurw
- e. instrumentation and control
- f. radiological safety
- g. mechanical and electrical engineering
- h. quality assurance Comoosition 5.5.2.2 The Safety Audit and Review Comittee shall be composed of:
Chairman: Division Manager - Nuclear Services Member: Senior Vice President Member: Division Manager - Nuclear Operations Member: Division Manager - Production Engineering Member: Manager - Fort Calhoun Station Member: Manager. - Radiological Services Member: Qualified Consultants as Required and as Determined by SARC Chairman 5-5 Amendment No. SS,JJ,JS,JSJ.JJE,JJ),132
W ,
i
. 5.0 ADMINISTRATIVE CONTROLS 5.5.2.8 e. The Fort Calhoun Station Emergency Plan and implementing procedures at least once every twelve months.
- f. The Site Security Plan and implementing procedures at least once every twelve months.
- g. The Safeguards Contingency Plan and implementing procedures at least once avery twelve months.
1 h. The Radiological Effluent Program including the Radioloflical Environmental Monitoring Program and the results thereo", the Offsite Dose Calculation Manual and implementing procodures, and the Process Control Program for the solidifications of radioactive
> waste at 1, east once per 2 years.
- 1. Any other area of facility operation considered appropriate by the Safety Audit and Review Committee or the Senior Vice President. l Authority 5.5.2.9 The Safety Audit and Review Committee shall report to and advise the Senior Vice President on those areas of responsibility specified in l Sections 5.5.2.7 and 5.5.2.8.
Records 5.5.2.10 Records of Safety Audit and Review Committee activities shall be prepared, approved and distributed as indicated below:
- a. ' Minutes of each Safety Audit and Review Committee meeting shall be prepared, approved and forwarded to the Senior Vice President l within 14 days following each meeting,
- b. Reports of reviews encompassed by Section 5.5.2.7e, f, g, h, and i above shall be prepared, approved and forwarded to the' Senior Vice President within 14 days following completion of the review. I
- c. Audit reports encompassed by Section 5.5.2.8 above shall be forwarded to the Senior Vice President and to the responsible I management positions designated by the Safety Audit and Review Committee within 30 days after completion of the audit.
5-8 Amendment No. SA,5%,5),JpJ.JJ) JJ9,132
5.0 ADMINISTRATIVE CONTROLS
. - 5.1[.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 in 6 20.202(b)(3) of 10 CFR 20) in which the intensity of radiation is 1000 mrenVhr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by required issuance of a Radiation Work Permit.*
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
- a. A radiation monitoring device which continuously indicates the radiation dose-rate in the area,
- b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. 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.
- c. An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
Individual shall be res)onsible for providing positive control over.the activities wit 11n the area and shall perform >eriodic radiation surveillance at the frequency specified' by tie Supervisor-Radiation Protection in the Radiation Work Permit. l-5.11.2 'The requirements of 5.11.1, above, shall also apply to each high radiation area in which the intensity of radiation is greater than-1000 mrem /hr (Very High Radiation Area). In addition, locked doors
- shall be provided to prevent unauthorized enter into such areas and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Supervisor Radiation Protection l with the following exception:
- a. -
In lieu of the above, for accessible localized Very High Radiation areas located in large areas such as containment, where no lockable enclosure exists in the immediate vicinity of the Very High Radiation area to control access to the Very High Radiation area and no such enclnsure can be readily constructed, then the Very High Radiation area shall be:
- 1. roped off such that an individual at the rope boundary is exposed to 1000 mrem /hr or less.
ii. conspicuously posted, and iii. a flashing light shall be activated as a warning device.
- Radiation Protection personnel shall be exempt from the RWP l issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
5-19a Amendment No. JE, %J,132