ML20236R604
| ML20236R604 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/19/1987 |
| From: | PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| Shared Package | |
| ML20236R552 | List: |
| References | |
| NUDOCS 8711230381 | |
| Download: ML20236R604 (22) | |
Text
' rats.a Appendix A w
Page 1 ef 3 MW.L List of Proposed Changes Section Affected Proposed Changes Pya 243 Change the title Manager-Nuclear Plant Paragraph 6.1.1 to Plant Manager.
Page 246 Paragraph 6.5.1.1 Page 247 Paragraph 6.5.1.6.a Page 248 Paragraph 6.5.1.7.a Paragraph 6.5.1.7.c Page 244 Change the Organizational Chart, Figure 6.2-1.
Page 245 Change the Organization Chart,' Figure 6.2-2 l
Page 245a Continue the Organization Chart, Figure 6.2-2 Page 246 Paragraph 6.5.1 Change the title Plant Operation Review Paragraph 6.5.1.1 Comittee to Plant Operations Review Paragraph 6.5.1.2 Comittee.
Page 247 Paragraph 6.5.1.6 Page 248 Paragraph 6.5.1.7 Page 248a Paragraph 6.5.1.8
)
i Page 251 Paragraph 6.5.2.7.i l
Page 246 Paragraph 6.4.1 Change the title Manager-Nuclear i
Plant to Superintendent-Training.
Paragraph 6.5.1.2 Define the composition of the PORC to:
Remove the Manager-Nuclear Plant Outage Planning Engineer, Senior Health Physicist and Senior Chemist. Update the following positions: Shift Superintendent to Shift Manager, and Operations Engineer to Assistant Superintendent-0perations.
'1 Include the Superintendent-Technical, Superintendent-Maintenance / Instrumentation j
and Controls, and Regulatory Engineer.
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Define the PORC chairman to be Superintendent-0perations.
.Page.247 Paragraph 6.5.1.6.e Change the title Superintendent, Page 248 Nuclear Generation Division to Paragraph 6.5.1.7.c Vice President, Peach Bottom Page 248a Atomic Power Station.
Paragraph 6.5.1.8 Page 253 Paragraph 6.6.1.b Paragraph 6.7.1.b Paragraph 6.7.1.d j
l Page 247 i
Paragraph 6.5.1.6.e Replace the Chairman of the Page 248 Nuclear Review Board with the Paragraph 6.5.1.6.h Nuclear Review Board, Paragraph 6.5.1.6.i Page 248a Paragraph 6.5.1.8 Page 247 l
Paragraph 6.5.1.6.e include the Plant Manager as a recipient of reports of investigations of Technical Specification violations.
1 i
Page 248 Paragraph 6.5.1.6.h Change the index from "h" to "i".
Add the Plant Manager as a recipient of recommendations regarding the Plant l
Security Plan.
Paragraph 6.5.1.6.i Change the index from "i" to "j".
i Add the Plant Manager as a recipient of recommendations regarding the Emergency Plan.
l Paragraph 6.5.1.6.j Change the index from "j" to "k".
Replace the reference to Technical Specification Paragraph 6.9.2.b(5) with a reference to 10 CFR 50.72 and 50.73.
Paragraph 6.5.1.7.a Clarify that the PORC makes recommendations for the approval of the Plant Manager.
Paragraph 6.5.1.7.c Change the title Superintendent, Nuclear Services to Senior Vice President-Nuclear.
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p Page 248a-Paragraph 6.5.1.8 Add the Plant Manager as a recipient of PORC meeting minutes.
Page 249 Paragraph 6.5.2.2 Change the title Vice President, Electric Production to Senior Page 252 -
Vice President-Nuclear.
Paragraph 6.5.2.8.i Paragraph 6.5.2.9
. Paragraph 6.5.2.10.a Paragraph 6.5.2.10.b Page 252a Paragraph 6.5.2.10.c Page 252 Paragraph 6.5.2.9 Include the Office of the Chief Executive as recipient of reporting and advisement by the NRB.
Page 253 -
Define the reporting time to the.
Paragraph 6.7.1.b Commission as one hour.
Define the internal reporting requirements to the Plant Manager, Vice President, Peach Bottom Atomic Power Station and the NRB within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Page 254 Paragraph 6.8.2 Change the title Station Superintendent to Paragraph 6.8.3.c Plant Manager.
Page 261 Paragraph 6.10.2.k Change the name OSR Comittee Page 266 to NRB.
Paragraph 6.18.2.A.2 Page 267 Paragraph 6.18.2.B.3 Page 262 Paragraph 6.13.1.b Change the title Shift Superintendent to Shift Manager.
1
1 PBAPS l
6.0 ADMINISTRATIVE CONTROLS
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l 6.1 Responsibility The Plant Manager shall be responsible for overall facility operation.
In the absence of t.he Plant Manager, the l
6.1.1 Superintendent - Operations (or any other person that the Plant Manager may designate in writing) shall assume the Manager's responsibility for overall facility operation.
I 6.2 Organization
)
6.2.1 Offsite The offsite organization for facility management and technical I
support shall be as shown on Figure 6.2-1.
1 6.2.2 Facility Staff 1
l The facility organization snall be as shown on Figure 6.2-2 and:
a.
Each on-duty shi f t shall be composed of at least the minimum shift crew composition shown in Figure 6.2-2, except that the shift crew composition may be less than the minimum requirements for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements, least one licensed operator shall be in the control b.
Atroom and assigned to each reactor that contains fuel.
i I
c.
At least two licensed operators, excluding the operator on the second unit, shall be present in the control room during reactor startup, scheduled reactor shutdown and during recovery from reactor trips.
l d.
An individual qualified in radiation protection procedures l
shall be onsite when fuel is in the reactor.
All CORE ALTERATIONS shall be directly supervised by i
e.
either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Bandling who has no other concurrent responsibility during this operation.
l f.
A Fire Brigade of at least 5 members shall be maintained onsite at all times.
The Fire Brigade shall not include r
the minimum shift crew necessary for safe shutdown of the unit (s) (3 members) or any personnel required for other essential functions during a fire emergency.
-243-
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PBAPS 6.3 Facility Staf f Qualifications Each member of the facility staff shall meet or exceed the minimum 6.3.1 qualifications of ANSI N18.1 - 1971 for comparable positions, except for (1) Senior - Health Physicist (radiation protection manager) who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975 and (2) the Shift Technical Advisor who shall have a bachelor's degree or i
i equivalent in a scientific or engineering discipline with specific training in plant design, and response and analysis of the plant for i
transients and accidents.
i 6.4 Trainina A retraining and replacement training program for the f acility staff shall be miintained under the direction of the Superintendent-Training and shall l
6.4.1 meet the requirements of Section 5.5 of ANSI N18.1-1971 and 10 CFR 55, Appendix A.
A training program for the Fire Brigade shall be conducted such that Fire 6.4.2 Brigade members complete an instruction program within a two year period.
Regularly planned meetings will be held every 3 months.
6.5 Review and Audit 6.5.1 Plant Operations Review Committee (PORC) l 6.5.1.1 Function f
The Plant Operations Review Committee shall function to advise the Plant Manager on all matters related to nuclear safety.
6.5.1.2 Composition The Plant Operations Review Committee shall be composed of the:
l Superintendent - Operations (Chairman)
Superintendent - Technical Superintendent - Maintenance / Instrumentation and Controls Superintendent - Plant Services l
Assistant Superintendent - Operations Maintenance Engineer Technical Engineer Regulatory Engineer Shift Manager 6.5.1.3 Alternates Alternate members shall be appointed in writing by the PORC Chairman to serve on a temporary basis; however, no more than two alternate members shall be used to satisfy a PORC quorum (See 6.5.1.5).
-246-
1 PBAPS-3 Meeting Frecuency The PORC shall meet at least once per calendar month' 6.5.1.4 and as convened by the PORC Chairman or his designated alternate (s).
Quorum A quorum of the PORC necessary for the performance of-6.5.1.5 the PORC responsibilities and authority provisions of.
these Technical Specifications shall consist.of the l
Chairme.n or hic designated alternate (s) and four t
membern or their alternates.
Responsibilities j
6.5.1.6 The Plant Operations Review Committee shall be responsible for:
a.
Review.of'l) all procedures required by Specification 6.8 and changes thereto, 2) any other proposed procedures or changes.thereto as determined by Plant Manager to affect nuclear-safety.
b.
Review of all proposed tests and experiments.
that affect nuclear safety.
Review-of all proposed changes to the Technical' I
c.
Specifications.
d.
Review of all proposed changes or modifications l
to plant' systems or equipment that' affect l
l nuclear safety.
\\
l Investigation of all-violations of the Technical l
e.
Specifications and shall prepare and, forward a report covering evaluation and recommendations-l to prevent recurrence to the Plant Manager, the=
Vice President, Peach Bottom Atomic Power Station, and the Nuclear Review Board.
f.-
Review of facility operations'to detect potential safety hazards.
Performance of special reviews and g.
i investigations and reports thereon as requested by the Chairman of the Nuclear Review Board.
h.
Review of all reportable events required by 10 l
CFR 50.73.
i
-247-j
.6.5.1.6 Continued
'i.
Review of.the Plant Security Plan and-implementing l
procedures, and~shall-submit recommended changes to the Plan to the Plant' Manager and the Nuclear Review Board.
l j.
Review of the Emergency Plan.and implementing l
procedures, and shall submit recommended changes to the l
Plan to the' Plant Manager and the Nuclear Review Board.
k.
Review of every unplanned release reportable under 10CFR-50.72 and 50.73, of radioactive material to the environs; evaluate the event; specify remedial action to recurrence; and document the event description, prevent evaluation, and corrective action and the~ disposition of the corrective action in the plant records.
Authority 6.5.1.7 The Plant Operations Review Committee shall:
I Recommend in writing, to the Plant. Manager, for his
[
a.
approval or disapproval of items considered under 6.5.1.6(a) through (d) above.
b.
Render determinations-in writing with regard to whether or not each item considered.under 6.5.1.6(a)-through (e) above constitutes an unreviewed safety question, as defined in 10 CFR 50.59.
Provide immediate written notification to the Vice c.
President, Peach Bottom Atomic Power Station, or in his absence, the Senior Vice. President - Nuclear andithe Nuclear Review Board of disagreement between the PORC and the Plant Manager; however, the Plant Manager shall l.
have responsibility for resolution of such disagreements pursuant to'6.1.1 above.
l l
I
-248-
.i PBAPS Records 6.5.1.8 The Plant Operations Review Committee shall maintain l
written minutes of each meeting and copies shall be provided to the Plant Manager; Vice President, Peach Bottom Atomic Power Station, and the Nuclear Review Board.
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l 1
-248a-l i
i 1
PBAPS 6.5.2 Nuclear Review Board Function i
6.5.2.1-The Nuclear Review Board (NRB) shall function to 4
provide independent review and audit of designated I
J activities in the area of-l a.
nuclear power plant operations i
b.
nuclear engineering chemistry and radiochemistry c.
d.
metallurgy I
instrumentation and control e.
f.
radiological safety mechanical and electrical engineering g.
h.
qua]ity assurance practices l
The members of the NRB will be competent in the area of quality assurance practice and cognizant of the Quality Assurance requirements of 10 CPR l
50, Appendix B.
Additionally, they will be cognizant of the corporate Quality Assurance j
Program and will have the corporate Quality j
Assurance organization available to them.
i Organization 6.5.2.2 Tne Chairman, members and alternate members of the NRB shall be appcinted in writing by the Senior Vice President - Nuclear, and shall have an academic degree I
in an engineering or physical science field and in eddition, snail have a minimum of five years technical experience, cf wnich a minimum of three years shall be in one or mere areas given in 6.5.2.1.
i l
-249-u
PBAPS 6.5.2.7 Continued d.
Proposed changes.in Technical. Specifications or Licenses.
e.
Violations of' applicable statutes, codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having. nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal and expected.
performance of plant equipment that affect nuclear safety.
g.
Reportable Event Reports required by 10 CFR 50.73.
h.
Any indication of an unanticipated deficiency in some aspect of' design or operation of safety related structures, systems, or l
components.
i.
Reports and meeting minutes of.the Plant Operations Review Committee.
l Audit 6.5.2.8 Audits of facility activities shall be performed under the cognizance of the NRB.
These audits shall encompass:
a.
The conformance of. facility operation to provisions contained within the Technical.
Specifications'and applicable license conditions at least once per year..
b.
The performance, training and qualifications of the entire facility staff at.least once per
- year, c.
The results of' actions taken to correct deficiencies occurring in facility equipment',
structures, systems or method of operation that affect nuclear safety 1at least onct per six months, d.
The performance of activities required by the Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix 3,.at.least once per-two years.
-251-
PBAPS 6.5.2.8 Continued The Facility Emergency Plan and implementing e.
procedures at least once per year.
f.
The Facility Security Plan and implementing procedures at least once per two years.
The Offsite Dose Calculation Manual and g.
implementing procedures at least once per two years.
h..
The performance of activities required by the Quality Assurance Program regarding the radiological monitoring program to meet the provisions of Regulatory Guide 4.1, Revision 1, April 1975, at least once per calendar year.
1 1.
Any other area of facility operation considered appropriate by the NRB or the Senior Vice i
President - Nuclear.
Authority 6.5.2.9 The NRB shall report to and advise the Senior Vice President - Nuclear and Office of the Chief Executive, on those areas of responsibility specified in Section 6.5.2.7 and 6.5.2.8.
Records 6.5.2.10 Records of NRB activities shall be prepared, approved and distributed as indicated below:
Minutes of each NRB meeting shall be prepared, a.
approved and forwarded to the Senior Vice President - Nuclear within 10 working days following each meeting, b.
Reports of reviews encompassed by Section 6.5.2.7.e, f, g and h above shall be prepared, approved and forwarded to the Senior Vice l
President - Nuclear, within 10 working days following completion of the review.
-252-g
PBAPS shall be Audit reports encompassed by Section 6.5.2.8 above,- Nuclear, and to the l
forwarded to the Senior Vice President c.
manacement positions responsible for the areas audited within 30 days after completion of the audit.
1 I
l i
4
-252a-
3 PBAPS 6.6~
Reportable Event Action 6.6.1 The following actions shall be tr. ken for Reportable Events:
a.
The Commission shall be notified pursuant to the requirements of Section 50.73 to 10 CFR 50.
b.
Each Reportable Event Report submitted to the Commission shall be reviewed by the PORC and submitted to the NRB and the Vice President, Peach Bottom Atomic Power Station.
6.7 Safety Limit Violation 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:
The provisions of 10 CFR 50.36(c)(1)(i) shall~
a.
be complied with immediately, b.
The NRC Operations Center shall be notified by telephone as soon as possible and in'all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
The Vice President, Peach Bottom Atomic Power Station, Plant Manager, and the NRB shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
c.
A Safety Limit Violation Report shall be prepared.
The report shall be reviewed by the PORC. -This report shall describe (1) l applicable circumstances preceding the I
violation, (2) effects of the violation'upon facility components, systems or structures, and (3) corrective action'taken to prevent-recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Vice President, Peach Bottom Atomi'c Power Station within 10 working days of the violation.
6.8 Procedures 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained that meet the requirements of Sections 5.1 and 5.3 of ANSI N18.7-1972 and Appendix "A" of USAEC Regulatory Guide 1.33 (November 1972) except as provided in 6.8.2 and 6.8.3 below.
-253-
PBAPS 6.8.2 Each procedure and administrative policy of 6.8.1 above, and changes thereto, shall be reviewed-by: the PORC and approved by the Plant Manager or his designated-l*
alternate per Specification 6.1.1 prior to implementation and reviewed periodically as set forth in administrative procedures.
6.8.3 Temporary changes to procedures of 6.8.1 above may be made, provided:
The intent of the original procedure is not a.
altered.
b.
The change is approved by two members of the: plant management staff, at least one of'whom holds a Senior Reactor Operator's License on the unit affected.
c.
The change is documented, reviewed by the PORC and approved by the Plant Manager within 14 days of
(
implementation.
6.8.4 Written procedures shall be established, implemented and maintained covering the activities of the radiological effluent technical specifications as referenced below:
I Offsite Dose Calculation Manual a.
i b.
Quality Assurance Program for the environmental monitoring using the guidance in Regulatory Guide 4.1, Revision 2, April 1975'.
6.9 Reportinc Requirements 1
In addition to the applicable reporting requirements of j
Title 10, Code of Federal Regulations, the following
~
identified reports shall be_ submitted to the administrator of the appropriate Regional Office unless otherwise noted.
i
-254-i a
t.
s o.
PBAPS 6.10.2 Continued Records of radiation exposure 1for all-individuals d.
entering radiation control areas.
Records of gaseous'and liquid. radioactive e.
material released to the environs.
Records of transient or operational cycles..for f.
those facility components designed for a limited number of transients.or cycles, Records of training and qualification for' current g.
members of the plant staff.
Records of in-service inspections performed h.
to these Technical Specifications.
pursuant Records of Quality Assurance activities. required 1.
l by the QA Manual, except as described in 6.10.1 l
- above, l
Records of reviews performed for' changes made to j.
procedures or equipment or. reviews of tests and experiments pursuant to 10 CFR 50.59.
Records of meetings of the PORC and the NR3.
l k.
l Records for Environmental Qualification which are 1
l.
covered under the provisions of paragraph 6.16.
Records of analyses required by the radiological m.
environmental monitoring program that would-
)
permit evaluation of the accuracy of the analvsis at a later date.
This should include procedures effective at specified times and OA. records showing that these. procedures were followed.
l l
i l
-261-l
e PBAPS 6.13 Hich' Radiation Area In lieu of the " control-device" or " alarm-signal" 6.13.1 of 10'CFR 20:
required by paragraph 20.203(c)(2)
Each High Radiation Area'in which the intensity of.
less than a.
radiation is greater than 100 mrem /hr'but 1000 mrem /hr shall be barricaded and conspicuously posted as a High Radiation Area and entrance l
thereto shall be controlled by issuance of a f
Any individual or. group of i
Radiation Work Permit.
individuals permitted to enter such areas shall be
]
provided with'or accompanied by-one or more of the following:
A radiation monitoring device which 1.
continuously indicates the radiation dose rate in the area.
A radiation monitoring device whicn 2.
i 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 tne dose rate levels in the area have after been established and personnel have been made-knowledgeable of them.
3.
An individual qualified in radiation protection procedures who is equipped with.a radiation dose rate monitoring device.
This individual shall be responsible for providing l
positive contrcl over' activities uithin the l
area and shall perform periodic radiation surveillance at the frequency specified by the plant health physicist or his designee on the Radiation Work Permit, Eacn High Radiation Area in which the intensity of b.
radiation is greater than 1000 mren/hr shall be j
subject to the provisions of 6.13.1 (a).above.
In addition, locked docrs shall be provided to prevent unauthorized entry into such. areas and the keys l
shall be maintained under the administrative contrcl of the Shift Manager ~, the Shift Supervisor
.l l
or the Senior Health Physicist.
-262-l l
1
_w
s#
PBAPS l
A.
Licer.see initiated changes:
- 1) Licensee initiated changes shall be reported l
to the Commission as part of the Modification Report required by 10 CFR 50.59.
The discussion of each change shall contain:
A summary cf the evaluation that led to a.
the determination that the change could De made in accordance with 10 CFR Part 50.59; b.
Sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information; A detailed description of the equipment, c.
components and processes involved and the interfaces with other plant systems; 6.
A comparison of the predicted releases of J
radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;
]
e.
An estimate of the exposure to plant operating personnel as a result of the change; and I
f.
Documentation of the fact that the change was reviewed and found acceptable by the j
? ORC.
- 2) Tne change shall beccme effective upon review and acceptance by both the PORC and NRB.
]
l
-266-L----
r*
PBAPS B.
Commission initiated changes:
1)
The applicability of the change to the facility shall be determined by the PORC after consideration of the facility design.
2)
The licensee shall provide the Commission with written notification of its determination of applicability including any necessary revisions to
)
i reflect facility design.
3)
The change shall be reviewed by the NRS at its next l
regularly scheduled meeting.
4)
The change shall become effective on a date proposed by the licensee and confirmed by the Commission.
6.18.3
" Major Changes" to radioactive waste systems shall include the following:
A)
Changes in process eculpment, components, structures and effluent monitoring instrumentation from those described in the Final Safety Analysis Report (PSAR) and evaluated in the staff's Safety Evaluation Report (SER);
3)
Changes in tne design cf radwaste treatment systems that significantly alter the characteristics and/or cuantities cf effluents released from those previously consideref in the TSAR and SER; CJ Cnanges in system design which invalidate the accident analysis as described in the SER; and D)
Changes in system design that result in a significant increase in occupational exposure of operating personnel.
-267-i o____.__-._.....___.___________.___..__________._____..__.____________________
- q c
PBAPS B.'
Commission initiated changes:
1)
The applicability of the change to the. facility shall be determined by the PORC after consideration of the facility. design.
2)
The licensee shall provide the Commissioniwith q
written notification of its determination of 1
applicability including any necessary revisions to i
reflect facility design.
3)
The change shall be reviewed by the NRS ut its next
- l regularly scheduled meeting.
l i
4)
The change.shall become effective on a date
{
proposed by the licensee and confirmed bysthe Commission.
6.18.3
" Major Changes" to radioactive waste systems.shall
.l include the following l
A)
Changes in process' equipment, components',.
l structures and effloent monitoring instrumentation 1
from those described in the Final Safety Analysis Report (PSAR) and evaluated in the staff's Safety Evaluation Report (SER);
q S)
Changes in :ne design of.radwaste treatment systems
)
that significantly alter the characteristics and/o i
quantities cf effluents released from those l
previously considered in the PSAR and SER; C)
Cninges in system design which invalidate the accident analysis as described in the SER; and D)
Changes.in system design that result in.a significant increase in occupational exposurefof operating personne1~.
l l
)
-267-i i
..is Certificate of Service I hereby certify that copies of the foregoing Application were served on the following by deposit in the United States mail, first-class postage prepaid, on this 19th day of November, 1987.
Regional Administrator U.S. Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, PA 19406 T. P. Johnson, Resident Inspector U.S. Nuclear Regulatory Commission Peach Bottom Atomic Power Station P.O. Box 399 Delta, PA 17314 Mr. Thomas Gerusky, Director Bureau of Radiation Protection Department of Environmental Resources Fulton Bank Building, 5th Floor Third 4 Locust Streets Harrisburg, PA 17120 i
,]'
l? %
l
?
,V Il t.//
Eugen4 J. ptadley
/
Attorney for Philadelphia Electric Company l
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