ML20012D007

Proposed Tech Specs,Making Corrections to Administrative Controls Section

ML20012D007
Person / Time
Site:	Fort Calhoun
Issue date:	03/19/1990
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20012D003	List: ML20012D002 ML20012D006 ML20012D007
References
NUDOCS 9003260283
Download: ML20012D007 (7)

Text

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9003260283 900319 .

. PDR ADOCK 05000283 PDC .

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5.0 ADMINISTRATIVE CONTR0Lji 5.1 Resoonsibility The Manager - Fort Calhoun Station shall be responsible for overall 5.1.1 facility-operation and shall delegate in writing the succession to this responsibility 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 established and defined for the highest management levels through intermediate levels to and including'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 equivalent 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 plant.

L 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 and quality assurance functions may report to

the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating i

pressures.

5.2.2 Plant Staff The plant staff organization shall be as described in Chapter 12 of the l 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. EJ,7%,7E,JpJ,JJE,JJ9

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t 5.0- ADMINISTRATIVE CONTROLS A

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 immediate written notification to the Division Manager

- Nuclear Operations and the Safety Audit and Review Committee 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 provided to the Division Manager -

Nuclear Operations and Chairman of the Safety Audit and Review Committee.

5.5.2 Safety Audit and Review Committee (SARC)

Function l

! 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 I c. chemistry and radiochemistry

d. metallurgy e, instrumentation and control f.- radiological safety

g. mechanical and electrical engineering

h. quality assurance I

Composition 5.5.2.2 The Safety Audit and Review Committee 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. EE,9J,99,JpJ,JJE,JJS L

5.0 -ADMINISTRATIVE CONTROLS j 5.5.2.8 c. 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 every twelve months.

h. The Radiological Effluent-Program including the Radiological Environmental Monitoring Program and the results thereof, the Offsite Dose Calculation Manual and implementing procedures, and the Process Control Program for the solidifications of radioactive waste at least once per 2 years.

1. Any other ares 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 I 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. l

c. Audit reports encompassed by Section 5.5.2.8 above shall be forwarded to the Senior Vice President and to the responsible l management positions designated by the Safety Audit and Review Committee within 30 days after completion of the audit.

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5.0 ADMINISTRATIVE CONTROLS 5.11.l' 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 mrem /hr or less shall be barricaded and conspicuously posted as a l 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 responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the 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 I 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 enclosure can be readily constructed, then the Very High Radiation area shall be:

l i. roped off such that an individual at the rope boundary l 1s 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 l issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved u radiation protection procedures for entry into high radiation

, areas.

l- 5-19a Amendment No. 78, EJ

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Discussion:

This request for Amendment of the Technical Specifications addresses several administrative changes found on pages 5-1, 5-5, 5-8 and 5-19a.

A planned reorganization and partial relocation of the Emergency Planning Department is creating a number of title changes which are reflected in this amendment. In addition, a title was changed, Supervisor-Radiation Protection, but was omitted from page 5-19a in a previous amendment.

9 Justification:

The Commission has provided guidance concerning the application of the standards for determining whether a significant hazards consideration exists by providing certain examples (48 FR 14870) of amendments that are considered not likely to involve significant hazards consideration. Example (i) relates to a purely administrative change to the Technical Specifications: "for example, a change to achieve consistency throughout the Technical Specifications, correction of an error, or change in nomenclature." The proposed changes are similar to Example (1) and are purely administrative changes.

Basis for No Significant Hazards Consideration:

This proposed change does not involve significant hazards consideration because operation of Fort Calhoun Station in accordance with this change would not:

1. Involve.a significant increase in the probability or consequence of an accident previously evaluated. This change contains only adminis-l trative corrections. This change will change-titles and would not L effect previously evaluated accidents.

2. Create the possibility of a new or different kind of accident from any previously evaluated. This change contains only administrative corrections. No new or different modos of operation are proposed for the plant.

3. Involve a significant reduction in the margin of safety. This change contains only administrative corrections and, as such, does not result in a decrease in the margin of safety.

Therefore, based-on the above considerations, Omaha Public Power District has determined that this change does not involve a significant hazards consideration.

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