ML20008E602
| ML20008E602 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 01/22/1981 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20008E603 | List: |
| References | |
| NUDOCS 8103090263 | |
| Download: ML20008E602 (19) | |
Text
o UNITED STATES
'k NUCLEAR REGULATORY COMMISSION wassisciou. o. c. 2osss S
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CONSUMERS POWER COMPANY DOCKET NO. 50-255 PALISADES PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No. 63 License No. DPR-20 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Consumers Power Company (the licensee) dated July 3,1980, complies with the standards and requirements of the Atomic Energ: 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 amenJment can 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 ar-Jmerit 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 Commission's regulations and all applicable requirements have been satisfied.
4103090283
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Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 3.B of Provisional Operating License No. DPR-20 is hereby amended to read as follows:
B.
Technical Specifications The Technical Specifications contained in Appendices A and B (Environmental Protection Plan), as revised through Amendment No. 63, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION i
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Dennis M. Crutchfield, ef Operating Reactors Branch #5 Division of Licensing Attachments:
1.
Changes to the Technical Specifications 2.
Appendix B (Environmental Protection Plan)
Date of Issuance: January 22. 1581 l
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i ATTACHMENT TO LICENSE AMENDMENT NO. 63 i
PR0'JISIONAL OPERATING LICENSE NO. DPR-20 DOCKET NO. 50-255 Revise Appendix A Technical Specifications by removing the following pages and by inserting the enclosed pages. The revised pages contain the captioned amendment number and marginal lines indicating the area of change.
REMOVE INSERT iii iii*
3-50 3-50 3-50a 3-50a 3-51 3-51 3-51a 3-52 3-52 **
3-52a 3-52a 4-47 4-47 4-50 4-50 4-50a, b, c 4-51 through 4-55 4-51 through 4-55 4-55a, b, c, d 4-57 4-57 4-58 4-58 4-58a, b, c 4-59 4-59 6-25a 6-25a 6-25b-6-25b 6-25c S-2 through S-5 S-2 through S-5 S-9 S-9 S-10 through S-13
- This page also reflects the Environmental Qualification Provision issued by NRC Order dated October 24, 1980
- There are no changes to the provisions contained on this page; a typo-graphical error has merely been corrected.
TABLE OF CONTENTS (Contd)
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Section Descri ption Page 4.0 SURVEILLANCE REQUIREMENTS (Contd) 4.12 Augmented Inservice Inspection Program for High Energy Lines Outside of Containment 4-60 4.13 Reactor Internals Vibration Mor.itoring 4-65 4.14 Augmented Inservice Inspection Program for Steam Generators 4-68 4.15 Primary System Flow Measurement 4-70 4.16 Inservice Inspection Program for Shock Suppressors (Snubbers) 4-71 4.17 Fire Protection System 4-75 5.0 DESIGN FEATURES 5-1 5.1 Site 5-1 5.2-Containment Design Features 5-1 5.3 Nuclear Steam Supply System (HSSS) 5-2 5.4 Fuel Storage 5-3 6.0 ADMINISTRATIVE CONTROLS 6-1 6.1 Responsibility 6-1 6.2 Organization 6-1
-6.3 Plant Staff Qualifications 6-1 6.4 Training 6-1 6.5 Review and Audit 6-5 6.6 (Deleted) 6-9 6.7 Safety Limit Violation 6-9 6.8 Procedures 6-10 6.9 Reporting Requirements 6-11 6.10 Record Retention 6-26 6.11 Radiation Protection Program 6-27 6.12 High Radiation Area 6-28 6.13 Fire Protection Inspection 6-33 6.14 Environmental Qualification 6-33 l
5 SPECIAL TECHNICAL SPECIFICATIONS PURSUANT TO AGREEMENT S-1 S-1 (Deleted)
S-2 S-2 Liquid Radwaste System Modification S-5 S-3 through
.S-5 (Deleted) iii Amendment No. 37, 48, 63
3.9 EFFLUENT RELEASE Applicability Applies to the controlled release of radioactive liquids and gases.
Objectives l
To define the conditions for release of radioactive wastes from the l
plant discharge mixing basin and from the plant vent to assure that any radioactive material released is kept as low as practicable and, in any event, is within the limits of 10 CFR 20.
3.9.1 The release rate of radioactive liquid effluents shall be such that at all times under normal operating conditions, radioactive materials in liquid discharges released from v. plant to Lake Michigan shall be reduced to essentailly zero (i.c, lake water background); provided that g
radioactive materials in the laundry waste system discharges, which cannot be treated in the dirty waste system of the modified liquid radwaste system without the possibility of impairing the function of dirty waste system equipment, may be released to Lake Michigan at levels
-8 not exceeding 2.5 x 10 pCi/cc on an annual average basis, as specified in the Special Technical Specifications, Section S-2.
This concentra-tion is 25% of the 1 x 10- pCi/cc limit for unidentified mixtures in 10 CFR 20, Appendix B. Table II, for unrestricted areas. Under abnormal operating conditions, releases shall not exceed, on a quarterly average basis and on an individual isotopic analysis basis, 10% of applicable 10 CFR Part 20 limits, and shall be reduced to
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3-50 Amendment No.lf, 61 e
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EFFLUENT RELEASE (cont 1) essentially zero no later than 60 consecutive days after the com=encement See of such releases resalting form abnormal cperatin; conditions.
Special Technical Spe:ifications, Section S-2, for further details.
3.9.2 During release of rad:.oactive liquids, the MPC, as defined in 10 CFR 20, shall not be exceeded at the point of discharge to the lake.
Prior to release of liquid wastes, a sample shall be taken from the tank 3.9.3 to be discharged and analyzed. The flow rate from the tank and the discharge rate from the mixing basin shall be determined in order to calculate the concentration of radioactive materials in the mixing basin to demonstrate compliance with 3.9.1 and 3.9.2 above.
3.9.4 During the release of liquid radioactive vastes, the following conditions shall be met.
Flow through the mixing basin shall be at least 8,000 gps.
a.
b.
During any release, the discharge monitor shall be in operation with the exception that if it (RlA-1049) is down for maintenance, sampling of the discharge water shall be taken every four hours and each sa=ple analyzed.
j 3.9. 5 Under normal operating conditions, the expected release to the environment from the modified liquid waste system shall be zero af ter integration of the modified and existing liquid radioactive waste system is completed.
All radioactive liquids not meeting Specification 3.9.1 will be recycled or prepared for shipment in accordance with applicable rules, regulations and orders of governmental authorities having jurisdiction and turned over to a carrier or carriers lic.ensed by govern = ental authorities having Under jurisdiction for shipment to an authorized disposal area or areas.
abnormal operating conditions, such as (but not limited to) steam. generator tube leakages, fire, or pipe breakage, liquid radioactive wastes may be discharged to the environment. These discharges shall be performed in
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accordance with the requirements of the Special Technical Specifications, Section S-2.2.
(Deleted) 3 9.6 Chrough 3.9.9 3-50s Amendment No)@% 63
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EFFLUENT RELEASE (contd) 3.9.10 (Deleted)
Gaseous Wastes 3.9.11 The average annual release rates of gaseous and airborne particulate vastes shall be limited in accordance with the following equation:
{(gp 11 (cc/sec)
< 5 x 10 where Q is the annual release rate (uci/sec) of any radioisotope, i, 1
and (MPC)g in the units of pCi/2c is defined in Column 1, Table II, I
of Appendix B to 10 CFR 20.
See Special Technical Specifications, Section S-2.5 for further details.
3.9.12 The average gaseous release rate over any 15-minute period shall not exceed 10 times the yearly average limit.
3.9.13 Following isolation and prior to release of gaseous vastes from the waste gas decay tanks, the contents shall be sampled and analyzed to determine compliance with 3.9.11 and 3.9.12.
3.9.14 For purposes of calculating permissible releases by the above formula, MPC for halogens and particulates with half-lives longer than 8 days will be divided by a factor of 35 from their listed value in 10 CFR
- 20. Appendix B.
3-51 Amenament No$6, 63
EFFLUENT RELEASES (cont'd) 3.9.15 During release of gaseous wastes to the plant vent stack, the following conditions shall be met:
a.
At least one main exhaust fan shall be in operation.
b.
The gaseous radioactivity monitor and the particulate monitor shall be in operation during discharges with the exception that if RIA-1113 is down for maintenance, sampling of the stack effluent shall be taken every four hours and each sample analyzed.
3.9.16 During power operation, whenever the air ejector discharge monitor is inoperable, samples shall be taken from the air ejector discharge and analyzed for grose radioactivity daily.
3.9.17 Gaseous radioactive waste shall have the following minimum holdup times prior to release:
Potentially high-radioactivity gaseous waste collected by the a.
vaste gas surge tank - a minimum of 15 days up to 60 days of holdup if the concentration of xenon-133 exceeds the detection limit of 1 x 10-5 pCi/cc (except as noted in 3.9.17.c).
No holdup requir-i except as prcvided by the piping system itself if the concentration of xenon-133 is less than the limit of 1 x 10-5 pCi/ce.
b.
Low-radioactivity gaseous vaste collected by the gas collection j
header shown on FSAR Figure 11-3.
l No holdup required except as provided by piping system itself.
Gaseous vaste may be discharged from vaste gas surge tank c.
through a high efficiency filter or from a waste gas decay tank with less than 15 days of holdup directly to the stack for a period not to exceed 7 days if the holdup system equipment is not available and the release rates meet Specifications 3.9.11, 3.9.12, and 3.9.14.
3.9.18 It is expected that releases of radioactive materials in effluents shall be kept at small fractions of the limits specified in 20.106 of 10 CFR 20.
At the same time the licensee ~is permitted the flexi-bility of operation, compatible wi:h considerations of health and safety, to assure that the public is provided a dependable source of power even under unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in 20.106 of 10 CFR 20.*
It is expected that in
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See Special Technical Specifications attached.
3-52 Amendment No.Jf', 63
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7 FLUENT RELEASE (cont'd) using this operational flexibility under unusual operating conditions, the licensee shall exert its best efforts to keep levels of radioactive mater'ial in effluents as low as reasonably achievable.
Bases Liquid wastes from radioactive waste disposal system are diluted in the discharge mixing basin prior to release to the lake.( }
A minimum i
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t 3-52a AmendmentNo.pf,63
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4.11 ENVIRONMENTAL MONITORING PROGRAM Applicability Applies to routine testing of plant environs and to an analytical evaluation of the data collected from the environmental monitoring survey carried out.
Obiective To establish a sampling and surveillance schedule which will assure recognition of changes in the environs due to plant operations and assure that effluent releases are kept as low as reasonably achievable ara within Federal and State limits.
Specifications Radiological environ = ental samples (1} shall be taken according to 4.11.1 the following schedule:
Table A.ll.1 Specific Samples and Collection Frequency Amount To Be Collected Sample Class Collection Frequency (Operational)
(a) Air Weekly 12 (b) Lake Water Monthly 2
(c) Well Water Monthly when 3
available (d) Milk Monthly when 4
available (e) Organic Monthly in Season Crops and Fish As Desired (f) Film or TLD Monthly 21 (g) Lake Bottom Twice per Year 4
Sediment 4.11.2 The sensitivities listed below and in Table 4.11.2 shall be used for the samples listed in Table 4.11.1.
Air - An I-131 analysis shall be performed on all air samples. When 3
a gross beta count reveals radioactivity levels in excess of 1 pCi/m,
gamma spectrum analysis shall be performed.
4~47 Amendment No.ssr, 63
ENVIRONMENTAL MONITORING PROGRAM (cont'd) 11.3 Plant equipment shall be used in conjunction with developed operating procedures to maintain surveillance of radioactive gaseous and liquid effluents produced during normal reactor operations and expected
' operational occurrences in an ef' art to maintain radioactive releases to unrestricted areas as reasonably achievable.
4.11.4
_(Deleted) 4.11.5 (Deleted from page 4-50c)
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4-50 Amendment No. )f, 63
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4.11 ENVIRONMENTAL MONITORING PROGRAM (Contd)
Del eted 4#
4-51 through 4-55 Change No, Rf, Amendment No. 63
ENIRONMENTAL MONITORING PROGRAM (cont'd) are far below those resulting in maximum permissible dose (MPD) to msn.
In othtr iterds, levels of radioactivity in water, air or food to be detected shall be far below those resulting in MPD to man. Levels of radioactivity in water, air or food to be detected shall be a small fraction of any effective maximum permissible concentration (NPC) allowed in such a sample. This is sometimes called the absolute contribution approach. On the other hand, there is a level of release to the environ-ment with a resultant corresponding level in food, air and water below which it is absurd to perform any specific isotopic analyses. Consequently, the sensitivities outlined in Table 4.11.2 are a compromise between the precedin3 two requirments. This schedule will insure that changes in the environmental radioactivity can be detected. The materials which first show changes in radioactivity are sampled most frequently. Those which are less affected by transient changes but show long-term accumula-tions are sampled less frequently. After a few years of operation, it is desirable to review the established limits. Data on the actual concentrations in food or other organisms (if any are observed) will
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permit this reevaluation.
k The lake bottom sediment samples taken twice during the summet months will be sufficient to detect any, buildup in Cs-137.
-1 The gross beta limit on 1 x 10 Ci/cc on air samples represents 1%
of the MPC, as given in 10 CFR Part 20, for unknown mixtures of gamma-2 emitting nuclides.
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l 4-57 Amendment No. 36, 63 l
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4.11 ENVIRONMENTAL MONITORING PROGRAM (cont'd) l (Intentionally Blank) 4-58 Amendment No. M,63
4.11 ENVIRONMENTAL MONITORING PROGRAM (Contd)
Deleted References (i) FSAR, Section 2.5.
4-59 Change No. 10, Amendment No. 63
1 3.
Significant Levels of Radioactivity If samples or measurements averaged over appropriate data base indicate statistically significant levels of radio-activity above estt*lished or concurrent backgrounds, the following information shall be provided:
i The type.of analysis performed, e.g., alpha, beta, a.
gamma and/or isotopic.
b.
The minimum sensitivity of the monitoring system.
The measured radiation level of sample concentration.
c.
d.
The specific times when samples were taken and measurements were made.
An estimate of the likely resultant exposures to the e,
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public.,
4.
If levels of radioactiva materials in environmental media i
due to plant origin indicate the likelihood of puotic exposure in excess of 5% of those that would result from continuous exposure to the concentration values listed in Appendix B, Table II of 10 CFR 20, estimates shall be
, presented of the,likely resultant exposure to individuals and to population groups and assumptions on which t.=timates are made.
C. (deleted) e 6-25a Amendment No. JMC 63
D.
Deleted 6.9.3.2 Nonroutine Reports A report shall be submitted in the event that (a) the radiological monitoring programs are not substantially conducted as described in Section 4.11; or (b) an unusual or important event occurs from plant operation that causes a significant environmental impact or affects a potential environmental impact. Reports shall be submitted within 30 days.
6-25b Amendment No. 74, 63
Ho cuch other requirements of the Technical Specifications shall be effective to pernit the licensee to fail to co= ply with any requirement of the following special technical specifications. However, the licensee shall not be required to co= ply with the following special technical specifications during the time and to the extent that the licensee is relieved of obligation to ec= ply there-with in accordance with their terms.
As used in these special technical cpecifications the ter= " Palisades Plant" means and refers to a single-unit nuclear electric generating plant and shall not be deemed to include any additional electric generating units that
-. may nereafter be installed at the Palisades Plant site.
SECTION S-1 (Deleted)
S-2 Amendment No. 63
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i AmendmentNo.63b S-3 to S-4 b
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SECTION S LIQUID RAIMASTE SYSTEM MODIFICATION IS-2.1 Consumers Power shall modify the liquid radwaste watem now installed in the Palisades Plant in the manner provided in these special tech-nical specifications. The liquid radwaste system as so modified (and in these special technical specifications called the " modified liquid radwaste system")
shall be so designed, constructed, operated and maintained that at all times under normal operating conditions, radicactive materials in liquid dircharges from the Palisades Plant to Lake Michigan are reduced to essentially zero; provided, however, that radioactive materials in laundry waste system discharges which cannot be treated in the dirty waste system of the modified liquid rad-waste system without the possibility of impairing the function of dirty waste cystem equipment may be released to Lake Michigan at levels which shall in no
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event exceed 25 picoeuries per liter (2 5 x 10 microcuries/cc)onanannual average basis; and provided further, that " essentially zero," as used herein, shall not be construed
- o preclude liquid discharges to Lake Michigan containing radioactive materials at levels, as sampled at the recycle monitor tank before dilution, equivalent to or below then-current Lake Michigan background radio-activity levels, as monitored offshore from the Palisades Plant prior to such S-5 Amendment No. 63
systcm; provided that radioactive materials in liquid discharges to Lake Michigan shall be at levels which are at all times as low as practicable and which do not exceed, on a quarterly average basis and on an individual isotopic analysis basis, and based on the assumptions used in Section 11 of Consumers Power's Final Safety Analysis Report to the AEC for the Palisades Plant as amended to December 1,1970,(1) under normal or abnormal operating conditions as defined in SS-2.1 hereof and assuming no failed fuel, two percent (2%) of applicable 10 CFR Part 20 limits in effect as of December 1, 1970; and (ii) under normal or abnormal operating conditions as defined in 13-2.1 hereof and assu=ing some failed fuel, ten percent (10%) of applicable 10 CFR Part 20 limits in effect as of December 1, 1970.
SS-2.5 In line 8 of subsection 3 9 13 of Section 3 9, " EFFLUENT RELEASE" of the Technical Specifications, add the following after "10 CFR 20":
"for gaseous releases, and within the limits for liquid releases specified in the special technical specifications included herein at the request of the licensee pursuant to a settlement agreement dated in March, 1971."
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r-o Amendment No. 63 1