ML20137X963
| ML20137X963 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 11/22/1985 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Philadelphia Electric Co, Public Service Electric & Gas Co, Delmarva Power & Light Co, Atlantic City Electric Co |
| Shared Package | |
| ML20137X969 | List: |
| References | |
| DPR-44-A-114, DPR-56-A-118 NUDOCS 8512100692 | |
| Download: ML20137X963 (26) | |
Text
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UNITED STATES
-8 NUCLEAR REGULATORY COMMISSION o
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E WASHINGTON, D. C. 20555
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PHILADELPHIA ELECTRIC COMPANY
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY C-ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-277 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 2 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.114 License No. OPR-4'4 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et al. (the licensee) dated May 23, 1980, as amended by letters dated August 1, 1980, June 2, 1981, April 4, 1983, May 29, 1984, and April 24, 1985, 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, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (1) that'the activities authorized by this amendment can be conducted without endangering the health and
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safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The. issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and
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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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. OPR-44 is hereby amended to read as follows.
8512100692 851122 PDR ADOCK 05000277 P
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2 Technical Specifications The Technical Specifications contained in Appendices A-A and B, as revised through Amendment No.114, are hereby incorporated in the license.
PEC0 shall operate the facility in accordance with the Technical Specifications.
3.
This license amendaent is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION b
A John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: November 22, 1985 b=
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ATTACHMENT TO LICENSE AMENDMENT NO.114 FACILITY OPERATING LICENSE NO. DPR-44 DOCKET NO. 50-277 S
Replace the following pages of the Appendices "A" and "B" Technicil Specifications with the attached pages. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
Appendix A-Remove Insert 247 247 248 248 248a 248a 249 249 250 250 251 251 252 252 253 253 Appendix B 49 49 50 50 m
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4 PBAPS Meeting Frequency 6.5.1.4 The PORC shall meet at least once per calendar
- month and as convened by the PORC Chairman.
Quorum 6.5.1.5 A quorum of the PORC shall consist of the Chairman and four members or their alternates.
Responsibilities 6.5.1.6 The Plant Operation Review Committee shall be responsible for:
Review of 1) all procedures required by a.
specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by station superintendent to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to the c.
Technical specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the e.
Technical specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the Superintendent, Nuclear Generation Divisicn and the Chairman of the Nuclear Review Board.
f.
Review of facility operations to detect potential safety hazards.
g.
Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Review Board.
T i
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Amendment No. J), 77, 114
-247-
PBAPS 6.5.1.6 Continued h.
Review of the Plant Security Plan and implementing procedures, and shall submit * -
recommended changes to the Plan to the Chairman of the Nuclear Review Board.
i.
Review of the Emergency Plan and implettrenting procedures and shall submit recommended changes to the Plan to the Chairman of the Nuclear Review Board.
i j.
Review of every unplanned release reportable undstr 4
6.9.2.b.(5) of radioactive material to the
- environs; evaluate the. event:.specify remedial action to prevent recurrence; and document the event description, evaluation, and corrective action and the disposition of the corrective action in the plant records.
Authority 6.5.1.7 The Plant Operaticri Review Committee shall
~
Recausend to the Station Superintendent written 4
-a.
approval or disapproval of items considered under C
6.5.1.6(a) through (d) above.
b.
Render determinatiens 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 c.
Superintendent, Nuclear Generation Division, y
I or in his absence, the Superintendent, Nuclear Services, and the Nuclear-Review Board of disagreement bet. ween the PO.RC and the Station Superintendentt however, the Station Superintendent shall have reponsibility for.:
s resolution of such disagreements pursuant to' 6.1.1 above.
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's Amenk.at No. J7, 37, 53.J8f' R4, f248-i
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PBAPS Records S.
6.5.1.8 The Plant Operation Review Committee shall mafntain written minutes of each meeting and copien shall be provided to the Superintendent, Nuclear Generation Division, and Chairman of the Nuclear Review Board.
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Continued d.
Proposed chan or Licenses. ges in Technical Specifit:ations Violations of applicable statutes, codes, e.
regulations license requ,irements, or of internalorders, Technical Spe procedures or instru i
safety significance,ctions having nuclear f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety, Reportable Event Reports required by 10 CFR g.
50.73.
h.
Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
1.
Reports and meeting minutes of the Plant Operation Review Committee.
Audits 6.5.2.s Audits of facility activities shal1 be performed
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under the cogniz shall encompass:ance of the NRB.
These audits l
The conformance of facility operation to a.
provisions contained within the Technical Specifications and applicable lice conditions at least once per year.nse b.
The performance, training and qualifications of the entire facility staff at least once per 1
year.
i The results of actions taken to correct c.
deficiencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety at least once per six months.
d.
The performance of activities required by the Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix B, at least once per two years.
Amendment Nos. 37. JJ, M,114
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PBAPS 6.5.2.8 Centinued The Facility Emergency Plan and implementing -
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procedures at least once per year.
f.
The Facility Se=urity Plan and implementing procedures at least once per tw years.
The Offsite Dose Calculation Manual and g.
implementing procedures at least once per two years.
h.
The perfermance of activities required by the Ouality Assurance Program regarding the radiological monitoring procram to meet the proviqions of Regulatory Guide 4.1, Revision 1, April 1975, at least once per calendar year.
i.
Any other area of facility operation considered appropriate by the NRB or the Vice President, Electric Production.
l Autherity 6.5.2.9 The NRB shall report to and advise the Vice President, Electric Production, on those areas of responsibility specifi,ed to Section 6.5.2.7 and 6.5.2.8.
Rebrds 5.5.2.10 Records of NRB activities shall be prepared, approved, and distributed as indicated below:
l i
Minutes of each NRB meeting shall be prepared, a.
approved and forwarded to the vice President, l
Electric Production, within 10 working days following each meeting.
b.
Reports of reviews encompassed by Section T
6.5.2.7.e, f g and h above, shall be prepared, app, roved and forwarded to the vice.
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President, Electric Production, within 10 working days following completion of the review.
Amenament No. 72, 37, y J41,.114
-252-7_..._..._.
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PBAPs 6.6 Reportable Event Action 6.6.1 The following actions shall be taken for Re Events:
portable a.
The Commission shall be notified pursuant to the requirements of Section 50.73 to 10 CFR 50 b.
Commission shall be reviewed by the P e
and submitted to the NRB and the Superintendent, Nuclear Generation Divisio 1
6.7 Safety Limit Violation n.
1 6.7.1 Safety Limit is violated:The following actions shall be ta event a a.
The provisions of 10 CFR $0.36 (c) shall be complied with immediately. (1)
(i) b.
The safety Limit Violation shall be report d to the Commission, the e
Generation Division or, Superintendent, Nuclear in his absence, the NRB immediately. Superintendent, Nuclear Serv i
e t
c.
A Safety Limit Violation Report shall be prepared.
This report shall describe (1)The report sh PORC.
violation, (2) applicable circumstances preceding the facility componentseffects of the violation upon
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recurrence. ective a,ction taken to preventsystems or structu and (3) corr d.
The Safety Limit violation Report shall be Superintende'nt, Nuclear Generation D within 10 working days of the violation.
6.8 Procedures 6.8.1 Written procedures and administrative poli i shall be established, implemented and maintained c es that meet the requirements of Sections 5 1 and 5 3 of ANSI N18.7-1972 Regulatory Guide.1.33 (November 1972)and Appendiz "A" of USAEC provided in 6.8.2 and 6.8.3 below.
except as Amendment Nos. M, 77, J/, J M,
114
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In addition to the responsibilities specified in Appendix A to the Operating License, the safety review committees chall have the following' responsibilities concerning the onvironmental impact of the plant.
A.
Plant Operation Review Committee (PORC) 1.
Review proposed on-site tests and experiments and -
i i
significance.results thereof, when such tests have environmental 2.
Reviewproposedchangestotheenvironmentallechnical specifica tions.
i 3.
Review operating instructions as specified in Section 7.3.3.
4.
Review environmental deviations as specified in section 7.2.3.
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B.
Nuclear Review Board (NRB)
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Review proposed changes to the environmental technical specifications.
e 2.
Review proposed changes or modifications to plant systems or equipment which may affect the environmental impact of the plant.
3.
Conduct periodic audits of plant operations.
4.
Review all reported environmental deviations.
t 7.2 Exceeded or if Harmful Effects DetectedAction to be Taken if a Pro 7.2.1 I
deviation shall be considered as defined in section 1.0.For the p 7.2.2 l
immediately to the Superintendent, t'uclear seneration }ivision orAny in his absence, the superintendent, Nuclear Services, an,d committee shall prepare a separate repor't for each environm d viation.
of the deviation, the extent and magnitude of the impact, and *T rccommendations for appropriate action to prevent or reduce the l
pecbability of such a deviation.
Amendment No. JJ, 114
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'7.2.3 Copies of all Duch reports shall be submitted to the Superintendent, Nuclear Generation Division, and to the' Chairman of the Nuclear Review Board for review and approval of any recommendations.
7.2.4 The Superintendent, Nuclear Generation Division NRC as specified in Section 7.4.2. report the circumstances of any environ shall 7.2.5 not considered. in the Final Environmental Statement are de by the monitoring programs, the lico sees 7 sill pnavide to the otaff an analysis of the problem and a plan of action to be taken
to eliminate or significantly reduce the detrimental effects or dtmage.
7.3 Unit Operating Procedures
- 7. 3. 1 for use in the anticipated operation of the plant components systems that could have an impact on the environment.
7.3.2 pecvided for the following: Instructions and appropriate check-off lists shall be A.
Normal start-up, operation, and shutdown of systems and components involving the environmental aspects of the plant.
~~
D.
Actions to be taken to correct specific and foreseen potential malfunctions of systems or components involving the environmental aspsets of the plant.
C.
Surveillance and testing requirements of environmental monitoring equipment associated with the monitoring requirements of Section 3.0 of these RTS.
7.3.3 chtnges thereto, shall be reviewed and aAll instructions described under 7.3.1 Superintendent prior to implementation. pproved by the Plant i
7.3.4 tho intent of the original instruction, may be made provided suc changes are approved by the shift Superintendent and one other asaber of the POR Committee.
cnd subsequently reviewed by the Plant Superintendent.Such changes shall be do
/Wenhent No. 7A 114 -
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UNITED STATES 8
NUCLEAR REGULATORY COMMISSION o
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PHILADELPHIA ELECTRIC COMPANY
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PUBLIC SERVICE ELECTRIC AND GAS COMPANY
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DELMARVA POWER AND LIGHT COMPANY ATLANTIC CITY ELECTRIC COMPANY DOCKET NO. 50-278 PEACH BOTTOM ATOMIC POWER STATION, UNIT NO. 3 AMENDMENT TO FACILITY OPERATING LICENSE Amendnent No.ll8 License No. DPR-56 1.
The Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by Philadelphia Electric Company, et ~
al. (the licensee) dated May 23, 1980, as amended by letters dated August 1, 1980, June 2, 1981, April-4, 1983, May 29, 1984, and April 24, 1985, 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, 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 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, i
and paragraph 2.C.(2) of Facility Operating License No. OPR-56,is hereby amended to read as follows:
L i
s i Technical Specifications
- ~
The Technical Specifications contained in Appendices A and B, as revised through Amendment No.118, are
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hereby incorporated in the license.
PECO shall operate' the facility in accordance with the Technical Specifications.
I 3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t4e C
John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of issuance: November 22, 1985 M
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ATTACHMENT TO LICENSE AMENDMENT NO.118 FACILITY OPERATING LICENSE NO. DPR-56 DOCKET NO. 50-278
- a. -
Replace the following pages of the Appendices "A" and "B" Technical Specifications with the attached pages. The revised pages are identified by Anendment number and contain vertical lines indicating the area of change.
Appendix A Remove Insert 247 247 248 248 248a 248a 249 249 250 250 251 251 252 252 253 253 Appendix B 49 49 50 50 t
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PBAPS Meeting Frequency 6.5.1.4 The PORC shall meet at least once per calendapt -
E.
month and as convened by the PORC Chairman.
Quorum 6.5.1.5 A quorum of the PORC shall consist of the Chairman and four members or their alternates.
Responsibilities 6.5.1.6 The Plant Operation Review Committee shall be responsible fora Review of 1) all procedures required by a.
specification 6.8 and changes thereto, 2) any other proposed procedures or changes thereto as determined by station superintendent to affect nuclear safety.
b.
Review of all proposed tests and experiments that affect nuclear safety.
Review of all proposed changes to the c.
Technical specifications.
d.
Review of all proposed changes or modifications to plant systems or equipment that affect nuclear safety.
Investigation of all violations of the e.
Technical specifications and shall prepare and forward a report covering evaluation and recommendations to prevent recurrence to the superintendent, Nuclear Generation Division
~
and the Chairman of the Nuclear Review Board.
f.
Review of facility operations to detect potential safety hazards.
g.
Performance of special reviews and investigations and reports thereon as requested by the Chairman of the Nuclear Review Board.
T Amendment No. JJ, 37,118
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PBAPS 6.5.1.6 Continued Review of the Plant Security Plan and h.
implementing procedures, and shall submit * ~
recommended changes to the Plan to the Chairman of the Nuclear Review Board.
i.
Review of the Emergency Plan and impletanting procedures and shall submit recommended changes to' the Plan to the Chairman of the Nuclear Review Board.
j.
Review of every unplanned release reportable under 6.9.2.b.(5) of radioactive material to the environst evaluate the event specify remedial action to prevent recurrencer and document the event description, evaluatica, and corrective action and the disposition of the corrective action in the plant records.
Aut'hority 6.5.1.7 The Plant Operaticn Review Committee shall Recommend to the Statica Superintendent written a.
approval or disapproval of items-considered under E
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 i
unreviewed safety questica, as defined in 10 CFR i
50.59.
Provide immediate written notification to the c.
Superintendent, Nuclear Generation Division, I
or in his absence, the Superintendent, Nuclear Services, and the Nuclear Review Board of
. disagreement between the PORC and the Station Superintendent; however, the Station Superintendent shall have reponsibility for resolution of such disagreements pursuant to '
6.1.1 above.
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Amendment No. 7jl, J7, pg, 7pp,118
-248-
PBAPS Records.,
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6.5.1.8 The Plant Operation Review Committee shall maintain written minutes of each meeting and copies shall be provided to the Superintendent, Nuclear Generation Division, and Chairman of the Nuclear Review Board.
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Amendment No.
M, 118
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PDAPS 6.5.2 Nuclear Review Board Fun _ction 6.5.2.1 The Nuclear Review Board (NRB) shall function to provide independent review and audit of designated activities in the area of:
4-nuclear power plant operations a,
b.
nuclear engineering chemistry and radiochemistry c.
d.
metallurgy instrumentation and control e.
f.
radiological safety mechanical end electrical engineering g.
h.
quality assurance practices The members of the NRB will be competent in the area of quality assurance practice and cognizant of the Quality Assurance requirements of 10 CFR 50, Appendix B.
Additionally, they will be cognizant of the have the corporate Quality Assurancecorporate Quality Organization available to them.
Oroanization 6.5.2.2 The Chairman, Members and alternate Members of tiie NRB shall be appointed in writing by the Vice President, Electric Production, and shall have an academic degree in an engineering or physical science fieldt and in addition, shall have a minimum of five years technical experience, of which a minimum of three years shall be in one or more areas given in 6.5.2.1.
heendment No. Jp, 77, W, 77, JE, 118
-249-
l PBAPS Alternates 1
6.5.2.3 Each permanent member shall have a designated alternatetoserveinhisabsence,andacurren; list of these alternates shall be maintained in(NRB I
records.
Each alternate member will serve on a '
continuing basis.
Consultants 6.5.2.4 consultants shall be utilized as determined by the NRB Chairman to provide expert advice to the NRB.
Meeting Frequency 6.5.2.5 The NRB shall meet at least onc'e p#r six months.
1 Quorum 6.5.2.6 A quorum of the NRB shall consist of the chairman or Vice Chairman or their designated alternates and four members or their alternatet>.
No more than a minority of the quorum shall have line i
responsibility for operation of the facility.
Review 6.5.2.7 The NRB sball reviews The safety evaluations for 1) changes to a.
O procedures, equipeent or systems and 2 or esPeriments completed under the prov)ision tests of le CFR 50.59, to verify that such actions did act constitute an unreviewed safety question.
b.
Prop' osed changes to procedures, equipment or systems which involve an unreviewed safety question as defined in 10 CFR 50.59.
Proposed test.s or experiments which involve an c.
unregiewed safety question as defined in 10 CFR.54.59..
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Amendment No.12, A7, $7, J2,118
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PBAPS 6.5.2.7-Continued d.
Proposed cha
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or Licenses.nges in Technical Specifications Violations of applicable statutes, codes e.
regulations license requ,irements, or of internalorders, Technical Sp procedures or instru safety significance.ctions having nuclear f.
Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nuclear safety.
Reportable Event Reports tequired by 10 CFR g.
50.73.
h.
Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or components.
1.
operation Review Committee. Reports and meeting Audits s.5.2.s Audits of facility activities shall be performed under the cogniz shall encompass ance of the NRB.
These audits l
a.
The ~conformance of facility operation to Specifications and applicable licenseprovisions co conditions at least once per year.
m b.
The performance, training and qualifications of the entire facility staff at least once per year.
The results of actions taken to correct c.
deficiencies occurring in. facility equipment structures, systems or method of operation that affect nuclear safety at least once per six months.
d.
The performance of activities required by the Quality Assurance Program to meet the criteria of 10 CFR 50, Appendix B, at least once per two years.
I i
Amendment Nos. 77, 55, JJ),ll8
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PRAPS i
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6.5.2.3 Cc=:inued s.
i The Faellity Emergency Plan and im e.
procedures at least once per year.plementing 5.
The Facility security Plan and implementing procedures at least once per two years.
The Offsite Dose Calculatinzi Manual and g.
implementing procedures at least once per two years.
h.
The perfermance of activities required by the Quality Assurance Procram reearding the radiological acrtitoring procram to meet the proviqions 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 Vice President, Electric Production.
Xutheriev g,3. ;t.,
The NRB shall report to and advise the Vice President, Electric Production, on those areas of
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responsibility.'apecifi,ed to section 6.5.2.7 and 6.5.2.8.
Ree=rds 5.5.2.10 Records of NRB activities shall be prepared, approved, and distributed as indicated belowe l
Minutes of each NRB meeting shall be prepared, a.
approved and forwarded to the Vice President, Electric Production, 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 vice
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President, Electric Production, within 10 working days following completion of the review.
Amenament No.10, 37.,yM, ;;s,118
-152-pq m 26
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PSAPS 6.6 Reportable Event Action
~
6.6.1 The following actions shall be taken for heportable Events:
The commission shall be notified pursuant to a.
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 Superintendent, Nuclear Generation Division 6.7 Sa fety Limit Violation 6.7.1 Safety Limit is violated:The following actions shall be taken The provisions of 10 CFR 50.36 (c) a.
shall be complied with immediately. (1) (i) b.
The safety Limit violation shall be reported to the Commission, the Generation Division or, superintendent, Nuclear in his absence, the NRB immediately. Superintendent, Nuclear Service A Safety Limit Violation Report shall be 4
l c.
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prepared.
This report shall describe (1)The report shall PORC.
applicable circumstances preceding the violation, (2)
.-facility components, systems or structures,' effects and (3) corrective action taken to prevent recurrence.
d.
The Safety Limit Violation Report shall be submitted to the Commission, the NRB and the Superintendent, Nuclear Generation Division within 10 working days of the violation.
i 6.8 Procedures 5.8.1 Written procedures and administrative policies shall be established, implemented and maintajned that meet the requirements of Sections 5.1 and 5.3 of ANSI N18.7-1972 l
and Appendiz "A" of USAEC Regulatory Guide 1.33 (November 1972) except'as provided in 6.8.2 and 6.8.3 below.
Amendment Nos. JR, 77, $7, M. 11g
-253-l
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In addition to tha responsibilities specified in Appendix A to the Operating License, the safety review committees chall have the following responsibilities concerning the environmental impact of the plant.
A.
Plant Operation _ Review Committee (PORC) 4 1.
Review proposed on-site tests and experiments ahd-i results thereof, when such tests have environmental significance.
2.
Review proposed changes to the environmental technical specifications.
3.
Review operating instructions as specified in Section i
7.3.3.
4.
Review environmental deviations as specified in B.
Nuclear Review Board DERB)
.l.
Review proposed changes to the environmental technical specifications.
2.
Review proposed changes or modifications to plant systems or equipment which may affect the environmental impact of the plant.
3.
Conduct periodic audits of plant operations.
. 4.
Review all reported environmental deviations.
7.2 Action to be Taken if a Protection Limit or Report Level is Exceeded or. if Harmful Effects Detected 7.2.1 4
For the purpose of this specification an environmental 4
dsviation shall be considered as defined in section 1.0.
7.2.2 Any env!ronmental deviation shall be reported immediatelytto.the $_uperintendent J:uclear 9eneration 31v'ision e
in his absence, the Superintendent, Nuclear Services,or, d.
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pecaptly reviewed by the Plant Operations Review CommittesA"This....
an ccamittee shall prepare a separate repor't for each environmental i
daviation.
cf the deviation, the extent and magnitude of the impact, andThis rep l
rccommendations for appropriate action to prevent or reduce the probability of such a deviation.
Amendment No. 7),118
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7.2.3 Copies of all such reports shall be submitted to the Superintendent, Nuclear Generation Division, and to the Chairman of the Nuclear Review Board for review and approval of any recommendations.
7.2.4 The Superintendent, Nuclear Generation Division,*shall report the circumstances of any environmental deviation to-t'he NRC a3 specified in Section 7.4.2.
7.2.5 not considered in the Final Environmental Statement are detected by the monitoring programs, the licensecs will provjde to the otaff an analysis of the problem and a plan of acEion to be taken to eliminate or significantly reduce the detrimental effects or dEmage.
4 7.3 Unit Operating Procedures 7.3.1 I
The plant personnel shall have available instructions for use in the anticipated operation of the plant components and systems that could have an impact on the environment.
7.3.2 provided for the followinorInstructions and appropriate check-off lists shall be 3.
Normal start-up, operation, and shutdown of systems and components involving the environmental aspects of the plant.
D.
Actions to be.taken to correct specific and foreseen ~
potential malfunctions of systems or components involving the environmental asp 4 cts of the plant.
Surveillance and tec*tr.
- .quirements of environmental C.
monitoring equipment associated with the monitoring requirements of Section 3.0 of these BTS.
7.3.3 changes thereto, shall be reviewed and aAll instructions described under 7.3.1 and l
Superintendent prior to implementation. pproved by,the Plant 7.3.4
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ths, intent of the original instruction, may be made provided suchTem changes are approved by the Shift Superintendent and one other crmber of the POR Committee.
cnd subsequently reviewed by the Plant Superintendent.Such changes shall be docum Amendment No. U,118 '
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