ML19345A287
| ML19345A287 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 05/23/1973 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19345A284 | List: |
| References | |
| NUDOCS 8011180562 | |
| Download: ML19345A287 (9) | |
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YANKEE ATOMIC ~ POWER COMPANY ATTACHMENTA CHANGE NO. 101 TO THE TECHNICAL SPECIFICATIONS LICENSE NO. DPR-3 The following new section is to be added:
E.
PLANT REPORTING REQUIREMENTS.
The following information shall be submitted to the USAEC in addition to the reports required by Title 10, Code of Federal Regulations.
Semiannual Operating Report A report ecvering a six-month period shall be submitted in writing to the Director of Licensing, USAEC, Washington, D. C.
20545 within 60 days after January 1 and July 1 of each year and shall include the following:
a.
Operaticas Surnary A su==ary of operating experience occurring during the reporting period that relates to safe operation of the facility, including a summary of:
1.
changes in facility design, 2.
perfor=ance characteristics (e.g., equipment and fuel performance),
3.
changes in operating methods which were necessitated by 1 and 2 or which otherwise were required to improve tue safety of facility operations, 4.
results of surveillance tests and inspection required by these technical specifications, 5.
the results of any periodic containment leak rate tests performed during tha reporting period, 8011180
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, 6.
a brief su= nary of those changes, tests, and experi=en:s requiring authorizatica from the Conmission pursuant to 10 CFR Part 50, Section 50.59(a), and 7.
changes in the plan operating staff for thosa posizions which are designated as key supervisory or technical personnel on Figure 1.
b.
?cwer Generation A su==ary of. power generated during the reporting period, including:
1.
gross :hermal power generi:ad (in MWh),
2.
gross electrical pcwar generated (in MRS),
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3.
na: electrical power generated (in MWh),
4.
nu=ber of hours the reactor was critical, 5.
number of_ hours the generator was on-lina, and 6.
histogram of charsal power vs time.
c.
Shutdowns Descriptive material covering all outages occurring during the reporting period. For each outage, infor:ation shall be prc-vided on:
l.
tha cause of the outage, 2.
the method of shu: ing devn the reactor; e.g.,
trip, au:o-catic rundown, or manually controlled delibera:e shutdcun, 3.
duration of the outage (in hours),
4.
unit s:stus during the outagg e.g., cold shu:down or ho shutdown, and 5.
correceiv, ccuica c kan to prevent rapacicion, if cpprc-prista.
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d.
Maintenance A discussion of corrective maintenance (excluding preventative maintenance) performed during the reporting period on safety related systems and components [ Safety related is defined in ANSI 18.7-1972 (ANS-3.2, Nov. 2, 1972)i and on systems and components that reduce or-prevent the release'of radioactive material to the environs. For any malfunctions for which-corrective maintenance was required, information-shall be pro-viced on:
1.
the system or component involved, 2.
the cause of the malfunction, 3.
the results and effect on safe operation, 4.
corrective action taken to prevent repetition, and 5.
special p'recautions taken to provide for reactor safety during repair.
e.
Changes, Tests, and Experiments A brief description and the su= mary of the safety evaluatien for those changes, tests, and experiments which were carried out without prior Commission approval, pursuant to the require-ments of 10 CFR Part 50, Section 50.59(b) of the Conmission's
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regulations.
s f.
Radioactive Effluent Releases A statement of the quantitias of radioactive affluents released from the plant with data su==arized on a monthly basis following 4
the format of USAEC Regulatory Guide 1.21.
1.
Gaseous Effluents (a)
Gross Radioactivity Releases (1) Total 3ross radioactivity (in curies), primarily nobla and cctivation gases.
(2) Maximum gross radioactivity release rate during any one-hour period.
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9 P (3)
Total gross. radioactivity (in curies) by nuclide released based on representative isotopic analyses performed.
(4) Percent of technical specification limit.
(b)
Iodine Releases (1) Total iodine radioactivity (in curies) by nuclide released based on representative isotopic analyses performed.
(2) Percent of technical specification 11=it for I-131 released.
(c)
Particulate Releases (1) Total gross radioactivity (3,y) released (in curies) excluding background radioactivity.
(2)
Gross alpha radioactivity released (in curies)
^
excluding background radioactivity.
(3)
Total gross radioactivity (in curies) of nuclides with half-lives greater than eight days.
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(4)
Percent of techr.ieal specification li=1: for particulate radioactivity with half-lives greater than eight days.
s 2.
Liquid Effluents (a)
Total gross radioactivity (3,y) released (in curies) xcluding tritius and average ccacentration released a the unrestricted area.
(b)
The maximum concentration of gross radioactivity
'3,y) released to the unrestricted area (averaged
/er the period of release).
(ch Total tritiun cnd total alpha radioactivity (in curies) eleascd and avarage concentra:ica released to the unres:ricted crea.
(d) Total dissolved gas radioactivity (in curies) and average concentracien released to the unrestricted area.
-S-(e)
Total volume (in l'iters) of liquid waste released.
(f) Total volume (in liters) of dilution water used prior to release from the restricted area.
(g) Total gross radioactivity (in curies) by nuclide released based on representative isotopic analyses performed.
(h) Percent of technical specification limit for total radioactivity. '
g.
Solid Waste 1.
The total amount of solid waste shipped (in cubic feet).
2.
The total estimated radioactivity (in curies) involved.
3.
Disposition including date and destination.
h.
Environmental Monitoring 1.
For each medium sa= pled during the reporting period, e.g.,
air, baybottom, surface water, soil, fish, include:
(a) Nu=ber of sampling locations, (b) Total number of samples.
(c)' Nu=ber of locations at which levels are found to be significantly above local backgrounds, and (d) Highest, Icwest, and the average concentrations or levels of radiation for the sampling point with the highest average and description of the location of that point with respect to the site.
2.
If levels of radioactive materials in environmental media as determined by an environmental monitoring program indi-cate the likelihood of public intakes in excess of 1% of those that could result from continuous exposure to the concentration valuaa listed in Appendix 2, Table II, Part 20, estimates of the likely resultant exposure to individuals and to population groups, and assumptions upon which estimates are based shall be provided.
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3.
If statistically significant variations of offsite environ-mental concentrations with time are observed, correlation of these results with effluent release shall be provided.
1.
Occupational Personnel Radiation Exposure Tabulate the number of personnel exposures for facility operations personnel (permanen: and temporary) in the following exposure increments for the reporting period:
less than 100 = Rem, 100 - 500 mrem, 500 - 1250 maan 1250 - 2500 mrem, above 2500 mrem.
Tabulate the nu=ber of personnel receiving more than 500 Rem exposure in the reporting period according to duty function, i.e., routine plant surveillance and inspection (regular duty),
routine plant maintenance,'special plant =ain:enance (describe naintenance), routine refueling operations, special refueling operations (describe operation), and other job related exposures.
Annually tabulate the number of personnel receiving more :han 2500 mRen and report major cause(s).
2.
Non-Routine Reports a.
Abnormal Occurrence Reports 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 /> by telephone and telegraphk to the Director of the Regional Regulatory Operations Office (cc to the Director of Licensing) foll:wed by a written report within 10 days to the Director of Licensing (ce to the Director of the Regional Regulatory Operations Office) in the avant of the abnormal occurrences as defined in Section E.4 The written report on these abnormal occurrences, and to the extent possible, the preliminary telephone and telegraph noti-fication shall:
(a) describe, analyze, and evaluate safety Laplications, (b) outline the measures taken to assure that the cause of the condition is deter =ined, '(c) indicate the cor-rective action (including any changes made to the procedures and to the quality assurance program) taken to prevent repetition of the occurrence and of similar occurrences involving si=ilar ccmponents or systems, and (d) evaluate Pn safety implica: ions of the incident in lighr of the cumulative experience obtained from the record of previous failures and malfunctions of st:ilar systems and components at the plant.
- Telegraph notification =ay be sent on :he next working day in :he event of an abnormal occurrence during a weekend or holiday period.
s b.
Unusual Even:s A wri::en repor: shall be forwarded within 30 days to the Diree:or of Licensing and to the Director of the Regional Regulatory Operations Office in the event of:
'l.
Discovery of any substantial-errors in the transient or accident analyses or in the methods used for such analyses, as described in the Safety Analysis Repor or in the bases for the technical specifications.
2.
Discovery of any substantial variance-from performance specifications contained in the technical specifications or in the Safety Analysis Report.
3.
Disecvery of any condition involving a possible single failure which, for a system designed agains: assumed single failures, could result in a loss of :he capability cf :he systan to perform 1:s safety function.
jb. Special Reports
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Special reports shall be submitted in writing within 90 days :o :he Director of Licensing, USA 2C, Washington, D. C.
20545.
Special reports shall be submit:ed covering inspections, :es:s, and maintenance that are appropriate to assure safe operation of the. plant.
The frequency and content of these special reports are determined on an individual case basis and designa:ed in these technical specifica:1ons. Such reports shall include:
a.
In-service inspection.
b.
Special maintenance reports.-
.ec.
Authorization of changes, tests, a'nd experi=ents in accordance with 10 CFR, 50.59.
d.
Containment leak rate tests.
e.
Radioactive effluent releases.
f.
Ma crials rcdia: ion surveillance speci= ens reports.
j g.
Fuel performance following each refueling or partial refueling.
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8-4 Abnor:a1 Occurrence Any of the following:
a.
A safety system se::ing less conservative than the 11:i:ing setting established in :he technical specifica: ions, b.
Viola: ion of a linizing condizion for operatica established in the technical specifica:1ons, c.
An uncontrolled or unplanned release of radioactive material from any plant systes designed to act as a boundary for such
=aterial in an amount of 10% of the limi:s prescribed in
- echnical specifications, d.
Failure of one or more components of an engineered safety feature or plant protection system tha: causes or threatens to cause the feature or system :o be incapable of performing its intended function.
Abnormal degrada: ion of one of :he several boundaries designed a.
to contain the radioactive materials resulting from :he fission
- process, f.
. Uncontrolled or-unanticipa:ed changes in reactivi:y of greater
- han 1% ak/k.
g.
Observed inadequacies in the i=plementation of ad=1:istrative or procedural controls such tha: the inadequacy causes or threarans to cause the existence or developmen: of an unsafe condition in connection with :he operation of the plant, and
' h.
Condizions arising fro: natural or offsite =annade events tha:
affect or threa:en to affect the safa operation of :he plan:.
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