ML20114C752
| ML20114C752 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 08/21/1992 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20114C754 | List: |
| References | |
| NUDOCS 9209030177 | |
| Download: ML20114C752 (15) | |
Text
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UNITED STATES y
3.n r NUCLEAR REGULATORY COMMISSION
' $A**. "y' j _ g K
WASHINGTON. D. C. 2^555
, *.".. #j CONSUMERS POWER COMPAfd DOCKET NO. 50-255 PALISADES PLA.tJI BiGDMENT TO FACILITY OPERATING LICENSE Amendment No.152 License No. DPR-20 1.
The Nuclear Regulat'ry Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated July 31, 1989, complies with the standards and requiremerts of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission'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 (i) that the activities authorized by this amendment cen be conducted without endangering the health and safety of the public; and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to tne common defense and security or to the health and safety of the public; E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission'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. DPR-20 is hereby amended to read as follows:
Jphnical Specifications and Envircnmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendrnent No.152, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
Additionally, the license is amended by adding a new Section 2.C.(3) to
.page 3 of Facility Operating License No. DPR-20 as follows:'
9209030177 920821 PDR ADOCK 05000255 P
' Amended pages and new pages are attached for conver.ience and for the composite licorJ.3 to reflect this change.
(3) The licensee shall implement and maintain in effect all provisions of the approve < fire protection program as described in the Final Safety Antlysis Report for the facility and as approved in the SERs dated 09/01/78, 03/19/80, 02/10/81, 05/26/83, 07/12/85, 01/29/86, 12/03/87 l
and 05/19/89 and subject to the following provisions:
a.
The licensee may make changes to the approved fire protection program without prior. approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
b.
The licensee may alter specific features of the approved fire protection program provided:
- Such changes do not otherwise involve a change in a license condition or technica'l specification or result in an unreviewed safety question (see 10 CFR 50.59);
- Such changes do not result in failure to complete the fire protection program as approved by the Commission.
The licensee shall maintain in auditable form, a current record of all such changes, including an analysis of the effects of the change on the fire protectica program and shall make such records available to Nuclear Regulatory Commission Inspectors upon request. All changes to the approved program shall be reported annually, along with the FSAR revision; and
- Temporary changes to specific fire proteci. ton features which may be necessary to accomplish meintenance or modifications are acceptable provided interim compensatory measures are implemented.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION N
- b. h 1
~
- edyard B. Marsh, Director L
l Project Directorate III-l u
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation Attachments:
-1. -' Amended pages 3 and 4, and new page 5 to Facility Operating License Number DPR-20 2.
Changes to the Technical l
Specifications
.Date of Issuance:
August 21, 1992 l
1
C.
This license shall be deemed to contain and is subject to the conditions specified in the Comission's regulations set forth in 10 CFR Chapter 1 and is subject to all applicable provisions of the Act and to the rules, regulations and orders or the Comission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:
(1) Maximum Power level The licensee is authorized to operate the facility at steady-state reactor core power levels not in excess of 2530 Megawatts thermal (10u percent rated power) in accordance with the conditions specified herein.
(2) Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
, and the Environmental Protection Plan contained in Appendix B are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
(3)
The licensee shall implement and maintain in effect all provisions of the approved fire protection program as describ;d in the Final Safety Analysis Report for the facility and as approved in the SERs dated 09/01/78, 03/19/80, 02/10/81, 05/26/83, 07/12/85, 01/29/86, 12/03/87
~
and 05/19/89 and subject to the following provisions:
s a.
The licensee may make changes to the approved fire protection program without prior approval of the Comission only if those t
changes would not adversely affect the ability to achieve and 8
maintain safe shutdown in the event of a fire.
is b.
The licensee may alter specific features of the approved fire protection program provided:
- Such changes do not otherwise involve a change in a license
~
condition or technical specification or result in an unreviewed safety question (see 10 CFR 50.59);
[
- Such changes do not result in failure to complete the five protection program as approved by the Comission. The 2
licensee shall maintain in auditable' form, a current record.f all such changes, including an analysis of the effects of the change on the fire protection program and shall make such records available to Nuclear Regulatory Comission Inspectors upon request.
All changes to the approved program shall be reported annually, along with the FSAR revision; and
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aca Temporary changes to specific fire protection features which
.l $
may be necessary to accomplish maintenance or modifications cE are acceptable provided interim compensatory measures are
[
impl emented.
D.
The facility has been granted certain exemptions from the requirements of Section III.G of Appendix R to 10 CFR Part 50, " Fire Protection Program for Nuclear Power Facilities Operating Prior to sanuary 1,1979."
This section relates to fire protection features for ensuring the systems and associated circuits used to achieve and maintain safe shutdown are free of fire dainage.
These exemptions were granted and sent to the licensee in
. letters dated February 8, 1983, July 12, 1985 and July 23, 1985.
In addition, the facility has been grante.d certain exemptions from Appendix J to 10 CFR Part 50, " Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors." This section contains leakage test requirements, schedule and acceptance criteria for tests of the leak-tight integrity of-the primary reactor containment and systems and components which penetrate the containment.
These. exemptions were granted and sent to the licensee in a letter dated December 6, 1989.
These exemptions granted pursuant to 10 CFR 50.12, are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application,- as amended, the provisions of the Act, and the rules and regulations of the Commission.
E.
Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved p5ysical security, guard training and qualification, and safeguards contingency plans, including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 md 10 CFR 50.54(p).
The plans, which contain
-Safeguards Information protected under 10 CFR 73.21 are entitled:
" Palisades Plant Physical Security Plan," through Revisions 25, dated June 4, 1990, approved June 13,1990; " Palisades Plant Suitability Training and Qualification Plan," through Revision 9, dated November 22, 1989,-approved December 18,-1989; and " Palisades Plant Safeguards Contingency Plan," through Revision 2, dated September 3J,1988, approved November 8, 1988.
Changes made in accordance with 10 CFR 73.55 shall be implemented in accordance with the schedule set forth therein.
F.
Except as otherwise provided-in the Technical Specifications or Er.vironmental Protection Plan, the licensee shall report any violations of the. requirements contained in Section 2.C of this license in the following manner:
initial notification shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the NRC
-- ' Operations Center via the Emergency Notification System with written follow-up within 30 days in accordance with the procedures described in 10 CFR 50.73(b), (c), and (e).
G.
The licensee shall have and maintain financial protection of such type and in such amounts as the Commission shall require in accordance with Section 170 of the Atomic Energy Act of 1954, as amended, to cover public liability claims.
H.
This license is effective as of the date of issuance and shall expi;w at midnight on March 14, 2007.
FOR THE NUCLEAR REGULATORY COMMISSION Thomas E. Hurley/ Signed /
Thomas E. Hurley, Director Office of Nuclear Reactor Regulation Attachments:
1.
Appendix A-Technical Specifications 2.
Appendix B-Environmental Protection Plan Date of Issuance:
February'21, 1991 Amendment No 152 August 21, 1992
ATTACHMENT TO LICENSE AMENDMENT NO.162 FACILITY OPERATING LICENSE NO. OPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by the amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT ii 11 iii lii v
v 3-96 3-96 3-97 3-97a 3-98 3-99 3-100 3-101-3-102 4-15 4-15 4-75 4-75 4-76 4-77 4-78 4-79 4 ---
6-2 6-2 6-5 6-5 6-7 6-7
PAllSADES' PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION DESCRIPTION PAGE N0 3.0 LIMITING CONDITIONS FOR OPERATION (Continued) 3.10 CONTROL R0D AND POWER DISTRIBUTION LIMITS 3-58 3.10.1 Shutdown Margin Requirements 3-58 3.10.2 (Deleted) 3-58 3.10.3 Part-Length Contro" Rods 3-58
-3.10.4 Misaligned or Inoperable Control Rod or Part-Length Rod 3-60 3.10.5-Regulating Group Insertion Limits 3 60 3.10.6' Shutdown Rod Limits 3-61 3.10.7f Low Power Physics Testing
.3-61 3.10.8.
Center-Control Rod Misalignment 3-61 Figure.3-6 Control Rod Insertion Limits 3-62
.3.11 POWER DISTRIBUTION INSTRUMENTATION 3-65 3 11.1 Incore Detectors 3-65 Excore Power Distribution Monitoring System 3-66a 3.11.2...
Axial Variation Bounding Condition 3-66d Figure 3.11-1
- 3.12=
MODERATOR. TEMPERATURE COEFFICIENT OF REACTIVITY 3-67 3.13-CONTAINMENT BUILDING AND FUEL STORAGE BUILDING CRANES 3-69 3.14
- CONTROL ROOM VENTILATION 3-70
-3.15 REACTOR PRIMARY SHIELD COOLING SYSTEM 3-70a
(.
3.16 ENGINEERED' SAFETY FEATURE 3 SYSTEM INITIATION INSTRUMENTATION SETTINGS 3-71 Table'3.16.1 Engineered Safety. Features System Initiation Instrument Setting Limits 3-75 3.17 INSTRUMENTATION AND CONTROL SYSTEMS 3-76 Table 3.17.1 Instrumentation Operating Requirements for Reactor Protective System-3-78 Table 3.17.2 Instrumentation Operating Requirements for
. Engineered Safety Feature Systems 3-79
-Tab?e 3.17.3 Instrument.0peratiag Conditions-for Isolation Functions-3-80 Table 3.17.4 Instrumentation Operating Requirements for Other Safety Feature Functions 3 3.18 (Deleted) 3-82
-3.19-IODINE REMOVAL SYSTEM 3-84 3.20:
SHOCK SUPPRESSORS-(SNUBBERS) 3-88 g
3.21 MOVEMENTJ0F SHIELDED SHIPPING CASK IN FUEL HANDLING AREAS 3-92 13.22 71RE PROTECTION SYSTEM (Deleted) 3-96 ii i
Amendment No. J7, 5), FS, pl, 55,198, JJp, JJJ, JJS 152
.1
PAllSADES PLANT TECHNICAL. SPECIFICATIONS TABLE OF CONTENTS =-- APPENDIX A SECTION DESCRIPTION PAGE N0 3.0 LIMITING CONDITIONS FOR OPERATION (Continued) 4 3.23 POWER DISTRIBUTION LIMITS 3-103 3.23.1 Linear Heat Rate (LHR) 3 103 Table 3.23.1 Linear Heat Rate Limits 3-107 Table 3.23.2 Radial Peaking Factor Limits, F 3-107 t
Fig. 3.23-1 Allowable LHR as a Function of Peak Power Location 108 Fig. 3.23-2 Allowable LHR as a function of Burnup 3-109 Fig. 3.23-3 Allowable _ LHR as a function _of Peak Power Location for Interior.and Narrow Water. Gap Fuel Rods 3-110 3.23.2 Radial Peaking Factors-3-111 3.23.3
. Quadrant Power Tilt Tg 3-112
-3.24 RADIOLOGICAL EFFLVENT RELEASES 3-114 3.24.1-Radioactive Liquid Effluent Monitoring Instrumentation 3-114 Table 3.24-1 Radioactive Liquid Effluent Monitoring Instrumentation 3-115 Bases for 3.-24. 3 128 3.24.2 Radioactive Gaseous Effluent Monitoring Instrumentation 3-117
-Table 3.24-2 Radioactive Gaseous Effluent Monitoring Instrumentation-3-118 Bases for 3.24.2 3-128 3.24.3.
Liquid Effluents Concentration 3-120 Bases for-3.24.3 3-129 3.24.4:
Liquid Effluent Dose 3-121 Bases for 3.24.4 3-129 3.24.5-Gaseous Effluents-Dose 3-122 Bases for 3.24.5 3-130 3.24.5.1 Dose Rate 3-122 Bases for 3.24.5.1 3-130 3.24.5.2 Noble Gases 3-123 Bases for 3.24.5.2 3-131 3.24.5.3 -
Dose - Iodine-131, Indine-133, Tritium and Radionuclides in Par * :ulate Form 3-124
'4 -
Bases for 3.24.5.3 3-131 s-
-3.24.6
-Gaseous: Waste Treatment System 3-125 Bases for 3.24.6 3-132-3.24.7' Solid Radioactive Waste 3-126 Bases for 3.24.7 3-132
=-
3.24~.8 Total Dose 3-127 Bases'for 3.24.8 3-133 3.25-ALTERNATE SHUTDOWN SYSTEM 3-134 Table 3.25.1-Alternate Shutdown Minimum Equipment 3-135 iii Amendment No. 37, /E, EJ, E/, JE, EE, JSE, ;2J, 152
~.~ -.-.
4 Pall 5ADES PLANT TECHNICAL SPECIFICATIONS TABLE OF CONTENTS - APPENDIX A SECTION.
DESCRIPTION-PAGE N0 4.0
-SURVEILLANCE RE0VIREMENTS (Continued)
Table 4.11-3 Detection Capabilities for Environmental Sample Analysis 4-57 4.11.1 Bases 'or. Monitoring Program 4-59a 4.11.3 Bases for Land Use Census 4-59a 4.11.5 Bases for Interlaboratory Comparison Program 4-59a
-4.12 AUGMENTfD INSERVICE INSPECTION PROGRAM FOR HIGH-ENERGY LINES OUTSIDE OF CONTAINMENT 4-60 Fig. 4.12 A Augmented Inservice Inspection Program - Main Steam Welds 4-63 F_ig. 4.12 B
.Augrsented Inservice inspection Program - Feedwater Line Welds 4-64 4.13 REACTOR INTERNALS VlBRATION MONITORING (DELETED) 4-65 4.14 AUGMENTED INSERVICE INSPECTION PROGRAM FOR STEAM GENERATORS 4-66 L Table 4.14.ll Minimum Number of Steam Generators to be Inspected i
During inservice Inspection 4-69a
-Table-4.14.2 Steam Generator Tube Inspection 4-69b.
4.15 PRIMARY SYSTEM-FLOW MEASUREMENT 4-70
-4.16 INSERVICE INSPECTION-PROGRAM FOR SH0CK SUPPRESSORS (SNVBBERS) 4-71
-4.17 FIRE PROTECTION SYSTEM (Deleted) 4-75 4.18 POWER DISTRIBUTION INSThJMENTATION 4-81 4.13.1 Incore Detectors 4-81 4.18.2 Excore Monitoring System 4-82 4.19-POWER DISTRIBUTION LIMITS 4-83 4.19,1 Linear _ Heat Rate-4-83 4.19.2-Radial Peaking Factors 4-84
'4.20 MODERATOR TEMPERATURE COEFFECIENT-(MTC) 4-85
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4.21 ALTERNATE SHUTDOWN SYSTEM 4-86 Table 4.21.1. Alternate Shutdown System Montoring Instrumentation Surveillance Requirements 4 4. 2 2.-
(Deleted) 4.23 (Deleted) 4.24 RADIOLOGICAL ' FLUENT RELEASES 4 90 4.24.1 Radiciogica.
luid Effluent Monitoring lInstrumect.,
4-90
/
f4.24.2-Radiological :.aseous Effluent Monitoring.
Instrumentation 4-90 4.24.3 Liquid: Effluent Concentration 4-90 4.24.4 Liquid Effluent Dose 4-90 l4.24.5 Gaseous Effluent Dose -
4-90 v
Amendment No. 37, AE, EE, E7, EE, EE, JEE, JJE, Ill, 152
3.22 flRE PROTECTION SYSTIM (Deleted)
Next Page is 3 103 3 96 Amendment No y,
- 59. 152
l l
t er i e L, LZ Mirii" F '92 K" cit' ' C'rla "I"ent l etti f%AR lection Test f reader'C Y 8 ef erenc e 1.
Control Rods Drop times of ALL Full-tech tefueling 7.4.1.3 Length Rods shutdowa 2.
Contret tods Pertial Movenent cf At t fiery two Weels 7.4.1.3 Rods (Minirruti of 6 in) 3.
Pretsuriger safety let Point One t och Pef ueling 7.3.7 Valves
$Nt bn 4.
Main $ team $af ety let Point Five fach Refuetthg 4.3.4 Valves
$hutdown 5.
tefveling systte funetioning 5rior to Refveting 9.11.3 Interlocks Operations 6.
Service Water f unc t ioning Ecth Gefueling 9.1.2 System _ Valve Operation Actuation ($15 Cep) 7.
Primary $ystem tvaluate Latty 4
Leekage Anerd 15, Ques 4.3.7 8.
Dieset Fuel Supply fuel Inventory coity 8.4.1 9 Criticat Headers 150 Psig Hrdro-Every 9.1.2 service Water System static fest Five Years 4 15 Anerdent ho 17, II,133, 152
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4.17 FIRE PROTECTION SYSTEM (Deleted) l t
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I Next Page is 4 81 l
4 75 Amendment No-37.69.152 1
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ADMINISTRATIVE CONTROLS 6.2.2 PLANT STAFF a.
Each on-outy shift shall be composed of at least the minimum shif t crew composition shown in Table 6.21.
b.
At least one licensed Senior Reactor Operator shall be in the control room at all times during conditions other than cold shutdown or refueling. In addition to this Senior Reactor Operator, at least one licensed Reactor Operator or Senior Reactor Operator shall be present at the controls at all times when fuel is in the reactor.
c.
A Radiation Safety Technician shall be on site when fuel is in the reactor.*
d.
All core alterations, after the initial fuel loading, shall either be performed under the direct supervision of a licensed Senior Reactor Operator or Senior Operator holding a license limited to fuel handling.
During this time, no other responsibilities shall be assigned to this individual.
e.
(Deleted) l f.
Administcative procedures shall limit the working hours of Plant staff who perform safety-related functions.
In the event that overtime is used, the following guidelines shall be followed:
A.-
An individuat shall not b'. permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight (excluding shift turnover time).
B.
An individual shall not be permitted to work mere than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24-hours in any.
48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any seven-day period (all excluding shift turnover time).
C.
A break of at least eight hours shall be allowed between work periods (including shift turnover time).
- The Radiation Safety Technician may be absent for a period of time not to exceed two hours in order to accommodate unexpected absence provided immediate action is taken to restore the minimum requirements.
6-2 Amendment No. 37,J5,JPE,JJ9,152
ADMINISTRATIVE CONTROLS 6.4 TRAINING 6.4.1 A retraining and replacement training program for the plant staff l
shall be maintained and shall meet or exceed the requirements and reconmendations of Section 5.5 of ANSI N18.1 1971 and Appendix "A" of 10 CFR Part 55, l
6.4.2 (Deleted) 6.5 REVIEW AND AUDIT 6.5.1 PLANT REVIEW COMMITTEE (PRC) 6.5.1.1 TVNCTION The Plant Review Committee (PRC) shall function to advise the Plant General Manager on all matters related to nuclear safety.
6.5.1.2 (QMPOSITION The PRC is composed of nine regular members from either the Palisades staff or the Nuclear Engineering-and Construction Organization (NECO) staff.
The qualification level for PRC members shall be at least equivalent to those described in Section 4.4 of ANSI N18.1 1971. The PRC shall include representatives from the Operations, Radiological Services, Maintenance and Engineering Departments.
The members shall be designated in administrative procedures by the Plant General Manager.
The Plant General Manager shall also designate the Chairman and alternates in writing.
6.5.1.3 ALTERNATES Alternate members of the PRC shall be appointed in writing by the PRC Chairman to serve on a temporary basis.
No more than two alternates shall participate as voting members at any one time in PRC activities.
6-5 Amendment No. JE,fE,7E,JpB,J27,JJ9,JfE,152
1 lf O D @ d}/M. M CONTROLS r.
,4.1 E[yl LW (Continued) c.
Proposed tests or experiments which involve an unreviewed safety question as defined in 10 CFR 50.59.
d.
Proposed changes to Technical Specifications or the Operating License.
e.
Violations of codes, regulations, orders, Technical l
Specifications, license requirements, or of internal procedures or instruc'. ions having nuclear safety significance.
f.
Significant operating abnormalities or deviations from normal-and exoected performance of unit equipment that affects nuclear safety.
g, All reportable events having nuclear safety signifi 2
h.
All recognized ina, cations of an unanticipated deficiency in some aspect of design or operation of structures, systems, or components that could affect nuclear safety.
i.
Reports and meeting minutes of the Plant Review Committee.
j.
Fire Protection Program and Implementing Procedure Changes.
l 6.5.2.4.2 AUDITS Audits of operational nuclear safety related facility activities shall be performed by the NPAD staff under.the cognizance of the Nuclear Performance Specialists.
These audits shall encompass:
a.
The conformance of plant' operation to provisions contained within the Technical Specifications and applicable license L
conditions at least once per 12 months.
L b.
The performance, training and qualifications of the entire l
facility staff at least once per 12 months.
I c.
The performance of activities required by the Quality Assurance Program Dest.'iption for Operational Nuclear Power Plants (CPC 2A) to meet the criteria of 10 CFR 50, Appendix B at least once per 24 months, d.
The Site Emergency Plan and implen.enting procedures at least once per 12 months.
e.
The Site Security Plan and implementing-procedures (as required by the Site Security Plan) at least once per 12 months.
6-7 Amendment No. 2A, /E, JpE, J/J, J/E,152
.