ML20215M961
| ML20215M961 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/27/1986 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20215M947 | List: |
| References | |
| NUDOCS 8611040051 | |
| Download: ML20215M961 (8) | |
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4 6.0 ADMINISTRATIVE CONTROLS dministrative Controls are the means by which plant operations are subject to mansgement control. Measures specified in this section provide for the assignment of responsibilities, plant organization, staffing.qualificatione and related requirements, review and audit Each of mechanisms, procedural controls and reporting requirements.
these measures are necessary to ensure safe and efficient facility operation.
f 6.1 RESPONSIBILITY 2
The Resi' dent Manager is responsible for safe operation of the plant.~
During periods when the Resident Manager is unavailable, the Superinten-dent of Power will assume his responsibilities. In the event both are unavailable, the Resident Manager may delegate this responsibility to other qualified supervisory personnel. The Resident Manager reports directly to the Executive Vice President-Nuclear Generation, as shown in Fig. 6.1.1.
6.2 PLANT STAFF ORGANIZATION The plant staff organization is shown graphically in Fig. 6.2.1 and-functions as follows:
- 1. A licensed senior reactor operator shall be on site at all times when there'is fuel in the reactor.
- 2. In addition to item 1 above, a licensed reactor operator shall be in the control room at all times when there is fuel in the reactor.
- 3. In addition to items 1 & 2 above, a licensed reactor operator shall be readily available on site, and a licensed senior reactor operator shall be in the control room whenever.the reactor is in other than cold condition.
- 4. Two licensed reactor operators shall be in the control room during start-ups and scheduled shutdownc~.
- 5. A licensed senior reactor operator shall be responsible for all All movement of new and irradiated fuel within the protected area.
core. alterations shall be directly supervised or manipulated by either a licensed senior reactor operator or senior reactor operator limited to fuel handling, who has no other concurrent responsibilities during this operation.
- 6. Except as specified in paragraph 6.2.5 a licensed reactor operator shall manipulate or directly supervise the manipulation of the controls of all fuel moving equipment except the reactor building J-All fuel movements by the reactor building crane, except new crane.
fuel movements from receipt to dry storage, shall be under the direct a
supervision of a licensed reactor operator.
- 7. All fuel movements within the core shall be directly monitored by the l
Reactor Analyst Supervisor or his designee.
Amendment No. p6, pd, J4I 247 8611040051 861027 L
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. In addition.to items 1, 2 & 3 above, two additional operators shall
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be readily'available on site whenever the reactor is in other than 4;
cold shutdown. During cold shutdown, an additional operator shall be,
-readily available on site.
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An individual qualified in radiation protection procedures shall be on site when fuel is in the reactor.
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In the event of illness or absenteeism up to two (2) hours is allowed to restore the shift crew or. fire brigade to normal complement.
.l' 11.
A Fire Brigade of five (5) or more members shall be maintained-on site at all times. This excludes two (2) members of the minimum
-shift crew necessary for safe shutdown and any personnel required for other essential functions during a fire emergency.
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A Shif t Te'chnical Advisor shall be on site and readily available to
- the control room except during the cold shutdown or refuel mode.
6.3 PLANT STAFF OUALIFICATIONS f
The minimum qualifications with regard to educational background and experience for plant staff positions shown in Fig. 6.2-1 shall meet or.
exceed the minimum qualifications of ANSI NI8.1-1971 for comparable positions;Lexcept for the Radiation and Environmental Services Superintendent who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and the Shift Technical Advisor who shall have a bachelor's degree or equivalent in a scientific or engineering discipline.with specific training in plant design, and response and analysis of the plant for transients and accidents. Any deviations will be justified to the NRC prior to an individual's filling of one of'these i-positions.
i 6.4 RETRAINING'AND REPLACEMENT TRAINING l
A training program shall be maintained under the direction of the Training Coordinator to assure overall proficiency of the plant staff i
organization.
It shall consist of both retraining and replacement training and shall meet or exceed the minimum requirements of Section 5.5 j
of ANSI NI8.1-1971.
'The retraining program shall not exceed periods two years in length with a curriculum designed to meet or exceed the requalification requirements l
In addition fire brigade training shall meet
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'or exceed the requirements of NFPA 27-1975, except for Fire Brigade I
training sessions which shall be held at least quarterly. The effective date for implementati~on of fire brigade training is March 17, 1978.
i 6.5 REVIEW AND AUDIT Two separate groups for plant operations have been constituted. One of these,.the Plant. Operating Review Committee (PORC), is an onsite review group.
The~other is an independent review and audit group, the offsite Safety Review Committee (SRC).
AmendmentNo.[.[.[,[
248 l
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ea FIGURE 6.2-1 r
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A.
FITZPATRICK NUCLEAR POWER PLANT PLANT STAFF ORGANIZATION y
VICE PRESIDENT QUALITY ASSURANCE RESIDENT MANAGER f
AND STAFF l
PLANT OPERATING
'y REVIEW COMMITTEE SUPERINTENDENT OF POWER AND STAFF l
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I MAINTENANCE OPERATIONS INST. & CONT.
TECHNICAL TRAINING' SUPT.
GA SUPT.
SUPT. & STAFF SUPT. (SRO)
SUPT. & STAFF SERVICES AND STAFF
& STAFF AND STAFP SUPT. & STAFF I
- SECURITY / SAFETY 5
REACTOR o
ANALYST RADIOLOGICAL &
SHIFT OFFICE FIRE PROTECTION SHIFT ENVIRONMENTAL TECHNICAL MANAGER SUPT. & STAFF SUPERVISOR (SRO)
SERVICES SUPT.
ADVISOR AND STAFF l
ASSISTANT SHIFT SUPERVISOR (SRO)
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SENIOR NUCLEAR
- Responsibility for performance and monitoring OPERATOR (RO) of the fire protection program 4
i NUCLEAR CONTROL OPERATOR (RO) i i
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(SRO) - Senior Reactor Operator i
AUXILIARY OPERATOR NUCLEAR OPERATOR (RO) - Reactor Operator l
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- ATTACHMENT II TO JPN-86-48 SAFETY EVALUATION FOR THE PROPOSED CHANGE-TO'THE TECHNICAL SPECIFICATIONS REGARDING SHIFT MANNING
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.3 NEW YORK POWER AUTHORITY JAMES A.
FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 DPR-59 l
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' Description of the Proposed Changes The proposed changes are limited to Section 6.2 " Plant Staff Organization" on.pages 247, 247a, and 248 and Figure.6.2-1 on.
page 260.
The changes are:
Pace Section Chance 247 6.2.3 Insert "and a licensed senior reactor operator shall be in the control room."
247 6.2.5 Replace entire paragraph 5 with the effective paragraph 5 currently on page 247a.
Within this paragraph replace " site boundary" with
" protected area" and replace " fuel movement as defined by Technical Specification section 1.B.
' Core Alterations '" with " core alterations."
Also insert "or manipulated" into the second sentence.
247 6.2.6 Add a new paragraph to read.
"Except as specified in paragraph 6.2.5 a licensed reactor operator shall manipulate or directly supervise the manipulation of the controls of all fuel moving equipment except the reactor building crane.
All fuel movements by the reactor building crane, except new fuel movements from receipt to dry storage, shall be under the direct supervision of a licensed reactor operator."
247 6.2.7 Add a new paragraph to read, "All fuel movements within the core shall be directly monitored by the Reactor Analyst Supervisor or his designee."
247 Remove reference to footnote.
247a Delete the entire page.
The specification currently on this page is incorporated into the new Section 6.2.5.
248 6.2.8-12 The existing paragraphs 6-10 are unchanged except to be renumbered 8-12 respectively.
260 Figure 6.2-1 Insert the position " Assistant Shift Supervisor (SRO)" beneath the Shift Supervisor.
-I I.
Putpose of the Proposed Chance NUREG-0737 Item I.A.1.3 (Reference 2) states, "Any time a licensed nuclear unit is being-operated in... modes 1-3 for a BWR....
the minimum shift crew shall include two licensed senior reactor operators (SRO), one of whom shall be designated as the shift supervisor..." and, "A licensed senior reactor operator (SRO) shall, at all times, be in the control room from which a reactor is being operated."
The changes to the
O FitzPatrick Technical Specifications incorporates previous
-Authority commitments regarding these NUREG-0737 requirements into the Operating License.
The other changes to the Technical Specifications are to clarify the personnel responsibilities and-supervisory control during refueling activities.
The change specifies the license qualifications of personnel permitted to supervise fuel moves and manipulate fuel handling equipment.
These additional controls on fuel movements will ensure a greater. degree of safety.
Additional control of fuel movements within the reactor core is added by requiring the Reactor Analyst Supervisor or-his designee to directly monitor such activities.
III. Impact of the Proposed Chance The requirement that two Senior Reactor Operators (SROs) be on site with one of the SROs in-the control room when the reactor is in other than cold condition, assures the availability of a SRO in the control room without affecting the freedom of the shift supervisor to move about the plant as needed.
The assistant shift supervisor supplements the level of knowledge and experience available in the control room.
This position affords a licensed SRO an opportunity to obtain additional supervisory and plant experience prior to achieving the position of shift supervisor.
This will increase the qualifications of the shift supervisors.
The work load of the shift supervisor is reduced by transferring some of his duties to the assistant shift supervisor.
The additional controls on the supervision of fuel movements and the manipulation of fuel handling equipment reduce the probability of personnel error involving nuclear fuel handling.
Requiring the Reactor Analyst Supervisor or his designee to monitor all in-core fuel movements will reduce the probability of a mispositioned or misoriented fuel bundle.
Changing the area in which an SRO is directly responsible for fuel movement from the site boundary to the protected area corrects an error in the original issue of the Operating License.
It was never the intention of this Technical Specification for an SRO to be responsible for fuel in transit, i
either on the plant access roads, railroad tracks, or in the parking lots.
Once inside the security perimeter fence, or protected area, the SRO will maintain full responsibility for the fuel.
The. proposed amendment to the Technical Specifications will have little impact on the current operation of FitzPatrick.
All of the proposed changes have previously been implemented via approved plant procedures.
The amendment will incorporate the Authority commitments as a condition of the operating license.
y IV..
Evaluation of Sionificant Hazards Consideration
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Operation of the Fitzpatrick plant in accordance with the proposed amendment would not involve a significant. hazard consideration as defined in 10 CFR 50.92 since it would not:
1) involve a significant increase in~the probability or consequences of an accident previously evaluated.
An increase in the number and qualifications of the minimum shift complement cannot increase the probability or consequences of an accident previously evaluated.
Requiring a second Senior Reactor Operator in the control room whenever the reactor is in other than cold condition will-increase the-level of experience and expertise available to mitigate-the consequences' operational transients or accidents.
Additional administrative control of fuel handling activities-will reduce the probability of fuel handling j
accidents and mispositioned or misoriented fuel bundles remaining in the reactor core.
2) create the possibility of a new or different kind of accident from any accident previously evaluated.
As stated above, the proposed amendment does not involve l
physical changes to the facility.
New or different kinds of accidents'cannot be created by adding a second Senior Reactor Operator (SRO) to'the staff, nor by increasing the administrative control of fuel movement activities.
I 3) involve a significant reduction in the margin of safety.
A second SRO will help to mitigate consequences of l
postulate transients and accidents.
Additional administrative controls of fuel handling activities reduce the probability of fuel handling errors.
These changes will increase the margin of safety of the FitzPatrick plant.
In the April 6, 1983 Federal Register (48FR14870), the NRC published examples of license amendments that are not'likely to involve a significant hazards consideration.
Example no. (ii) of that list is applicable to this proposed amendment and states:
9 "A change that constitutes an additional limitation, restriction, or control not presently included in the technical specifications."
f The second SRO requirement is an additional limitation and the more stringent requirements for fuel handling activities are i
additional controls not presently included in the FitzPatrick Technical Specifications.
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,.V.'
Implementation of the Proposed Chance The proposed change will not adversely impact the ALARA, Security or Fire Protection programs at the FitzPatrick plant, nor will it impact the environment.
VI.
Conclusion The change, as proposed, does not constitute an unreviewed
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safety question as defined in 10 CFR 50.59, that is, it:
(a) will not increase the probability or the-consequences of an accident or malfunction of equipment important to safety as evaluated previously in the safety analysis
-report; (b) will not increase the possibility of an accident or malfunction of a different type than any evaluated previously in the safety analysis report:
(c) will not reduce the margin of safety as defined in the bases for any technical specification; (d) does not constitute an unreviewed safety question; and (e) involves no significant hazards considerations, as defined in 10 CFR 50.92.
VII. References 1)
James A. FitzPatrick FSAR and SER 2)
NRC NUREG-0737, " Post TMI-Requirements", dated October 31, 1980.
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