ML20070L075
| ML20070L075 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 03/13/1991 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| Shared Package | |
| ML20070L054 | List: |
| References | |
| NUDOCS 9103190283 | |
| Download: ML20070L075 (5) | |
Text
_..
1 i
6 ATTAcilHENT A NIAGARA H0!!AVR POVER CORPORATION LICENSE NO. DPR-69 DOCKET NO. $0-410 Proposed Changes to Technical Specifications The existing pages 6-8 and 6-25 vill be replaced with the attached revised pages.
These pages have been retyped in their entirety with marginal markings to indicate changes to the text.
9103190283 910313 PDR ADOCK 05000410 P
AMINiiTPATIVE CONTROLS 6.5 REVIEW AND AUDIT 6.5.1 STATION OPERATIONS _ REVIEW COMMITTEE FUNCTION 6.5.1.1 The Station Operations Review Committee (SORC) shall function to advise the Plant Manager on all matters related to nuclear safety.
COMPOSITION 6.5.1.2 The 50RC shall be composed of the i
Chairman:
Plant Manager Member:
Manager Operations l
Member:
Manager Maintenance Member:
Manager Technical Support i
Member:
Manager Chemistry Member:
Manager Radiation Protection Member:
General Supervisor Instrument and Control Maintenance Member:
General Supeivisor System Engineering Member:
General Supervisor Operations Member:
Supervisor Reactor Engineering ALTERNATES 6.5.1.3 All alternate members shall be appointed in writing by the SORC Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in 50RC activities at any one time.
MEETING FREQUENCY 6.5.1.4 The 50RC shall meet at least once every calendar month and as convened i
by the 50RC Chairman or a designated alternate.
l OUORUM 6.5.1.5 The quorum of the 50RC necessary for the performance of the SORC responsibility and authority provisions of these Technical Specifications shall l
consist of the Chairman or a designated alternate and five members including alternates.
RESPONSIBILITIES 6.5.1.6 The 50RC shall be responsible for:
a.
Investigation of all violations of the Technical Specifications, including the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Vice President - Nuclear Generation and to the Safety Review and Audit Board; NINE MILE POINT - UNIT 2 6-8 Amendment No. 9, 25 l
ADMINISTR g VE CONTR00 6.12 HIGH RADIATION AREA 6.12.1 in li,tu of the " control device" or " alarm signal" required by 10 CFR 20.203 (c) (2), each high radiation area in which the intensity of radiation is greater than 100 mrem /br* but less than 1000 mrem /hr* shall be barri,:aded and conspicuously posted as a high radiation area, and entrance thereto thall be controlled by requiring issuance of a Radiation Work Permit (RWP)**.
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 levels in the area have been established and personnel have been made knowledgeable of them c.
An individual qualified in radiation protection (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for prmiding positive control over the activities within the area and shall perform pericdic radiation surveillance at the frequency specified by the Manager Radiation Protection or the Manager Radiation Protection designee in the RWP.
6.12,2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in ! hour a dose greater than 1000 mrem
- shall be provided with locked doors :.o prevent unauthorized entry, and the keyed access shall be maintained under the administrative control of the Station Shift Supervisor or the designee on duty and/or the Manager 8.adiation Protection l
or designee. Doors shall remain locked except during perieJ5 of access by pesonnnel under an approved RWP which shall specify the dose ratc levels in the immediate work area and the maximum allowable stay time for individuals in that area.
For individual ar m accessible to personnel with such radiation levels that a major portion of the b(My could receive in I hour a dose in excess of 1000 mrem
- that are located within hrge areas, such as the drywell, where no enclosure exists that can be locked, and no enclosure can be reasonably constructed around the indi\\idual areas, then that area shall be roped off, I
- Measurements made at 18 incies from the sou*ce of radioactivity.
- Health Physics personnel or personnel escorted by health physics personnel shall be exempt from the RWP issuance requirement during the performance of their assi ned radiation pre.,tection duties,.provided they are otherwise 9
following plant radiation protection procedures for entry into high radiation areas.
NINE MILE POINT - UNIT 2 6-25 Amendment No. 17 25
~
. ~ -.
~
. -. ~ - - -. -. -. -
r i
q f
ATTACHMENT B i
NIAGARA M0HAVK POWER CORPORATION
~
l i
LICENSE NO. NPF-69 DOCKET No. 50-410 t
i Suonorting Infor ntipp and No Significant Hazards Consideration A[utlysis j
The proposed Technical Specification changes to Administrative Contr @ Sections l
6.5 and 6.12 result from reorganization within Niagara Mohawk's Nueb
- Division,
[
vhich establishes a Manager Radiation. Protection Sr each unit, g;Mng i
accountability for program implementation through the Plant Managers. Under the current organization the Manager Radiation Protection reports within the Site Services organization. Under the organization proposed herein, a Manager Radiation Protection for each unit vill replace the Manager Health Physics'in each unit and report directly to each respective unit Plant Manager. The position j
entitled Manager Radiation Protection currently reporting within the site Services organization vill be replaced by the General Supervisor Radiological Support-to maintain site-vide radiological support services. The General Supervisor Radiological Support vill assume responsibility for activities related to respiratory protection, dosimetry, and radioactive shipping for shared radiological facilities currently under the cognizance of the Manager Radiation Protection.
l The composition of SORC in Saction 6.5.1.2 is being proposed for change to delete t
I the title of Manager Health Physics. All functional responsibilities of the Manager Health Physics vill be assumed by the Manager Radiation Protection.
This change establishes a more direct line of authority and responsibility under a unitized organization. The qualifications and responsibility of the Manager Radiation Protection remain consistent with the requirements of Technical Specification 6.3 Staff Qualifications.
The Manager Radiation Protection vill work under the direction of the Plant i
Manager to develop, implement and administer the Radiation Protection and ALARA Programs. The Manager Radiation Protection vill mainthin his current j
responsibilities for the technical quality and implementation of the AliAA and Radiation Protection Programs defined by. Nuclear Division Directives. 'this individual vill continue to act as the Radiation Protection Manager specified in NRC Regulatory Guide 1.8 for the assigned unit.
As such, the Manager Radiation Protection vill have authority to require plant shutdown if unsafe. radiological i
conditions exist.
Additionally, the Manager Radiation Protection shall have direct access to responsible corporate management such that resolution of radiation protection concerns can be accomplished.
Section 6.12, "High Radiation Area", is being proposed for change such that the administrative functions of the Manager Health Physics vill nov be performed by s
-the Manager Radiation Protection. This change is consistent vith the revised functional responsibilities of the Nuclear Division reorganization.
I l
l
. ~.
The changes in the Radiation Protection management organization for the Nuclear Division are the result of Niagara Mohawk's determination to provide the highest level of management expertise in the operation of the Corporation's nuclear facilities and to assure that the goals of improved performance are achieved.
This change is designed to reduce the span of control for the Manager Radiation Protection in order to streamline and improve the communication within the Radiation Protection organization.
The new organization establishes clearer functional lines of responsibility and reduces situations where work performed by one group must be forvarded to another group which reports to a different part of the organization.
The reorganization reflects Niagara Mohawk's effort to establish distinct lines of authority and responsibility for Nine Mile Point Units 1 and 2 in order to unitize operations.
These changes are also intended to provide consistency with the Administrative Controls Section of the Nine Mile Point Unit 1 Technicel Specifications.
10 CFR 50.91 requires that at the time a licensee requests an amendment, it must provide to the Commission its analysis, using the standards in Section 50.92 about the issue of no significant hazards consideration.
Therefore, in accordance with 10 CFR 50.91 and 10 CFR 50.92, the following analysis has been performed:
The operation of Nine Mile Point Unit 2. in accordance with the proposed amendment, vill not involve a significant increase in the probability ot conseauences of an accident previousiv evaluated.
The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed changes enhance the Radiation Protection management capability and performance of Nine Mile Point Unit 2.
The proposed change does not decrease staffing levels or decrease levels of expertise and enhances the line of authority of the Plant Manager over the Radiation Protection Program.
The operation of Nine Mile Point Unit 2. in accordance with the proposed amendment, vill not create the nossibility of a new or different kind of accid,gni from any accident oreviousiv evaluated.
The proposed amendment does not create the possibility of a new or different kind of accident than previously evaluated because the proposed changes are administrative in nature and no physical alterations of plant configuration or changes to setpoints or operating parameters are proposed.
The operation of Nine Mile Point Unit 2. in accordance with the oronosed amendment, vilt not involve a sienificant reduction in a margin of safety.
The proposed amendment vill not cause existing Technical Specification operational limits or system performant criteria to be exceeded.
The change enhances organizational effectiveness and maintains only qualified personnel in positions of responsibility.
Therefore, the proposed administrative changes to the Technical Specifications vill not affect the margin of safety.