ML20002C716
| ML20002C716 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 11/28/1972 |
| From: | Haueter R, Lamley R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | Oleary J US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8101100779 | |
| Download: ML20002C716 (11) | |
Text
_
...:-~
Consumers Power Regutatory
+ e95, Company c.n.<. omc.. aia we ' u c nisaa 4 eave. Jac'*oa
- ca saa **2o'
^** C ** 5" '88-
'S November 28, 1972 Mr. John F. O' Leary, Director Re: Docket No 50-155 Directorate of Licensing License DPR-6 United States Atomic Energy Proposed Technical Commission Specification Washington, DC 20545 Change 35
Dear Mr. O' Leary:
Transmitted herewith are three (3) executed and thirty-seven (37) conformed c~nies of a request for a change to the Tech-nical Specifications of License DPR-6, Docket No 50-155, issued to Consumers Power Company on May 1, 1964 for the Big Rock Point Nuclear Plant.
This proposed change (No 35) will incorporate the Big Rock Point Plant reporting requirements program into the Techni-cal Specifications as requested in Mr. Donald J. Skovholt's letter of September 28, liN2.
Yours very truly,
~~
.)
,4 e
JR/dmb Robert L. Haueter Electric Production af D y
Superintendent - Nuclear g
ggy g g-. -
g NOV30m72,.$
(if"*k iDll5gf i
v ?mie
&y h;-
~
y.n.
7/0//OD'77f g;sa,p
(
g,..s
-[j'c ?(i CONSUMERS POWER COMPANY Docket No 50-155 39,.;. g g.g n _ a p _p Request for Change to the Technical Specifications Change No 35 License DPR-6 For the reasons hereinafter set forth, the following changes to the Technical Specifications of License DPR-6, Docket No 50-155, issued to Consumers Power Company on May 1, 1964 for the Big Roch. Point Nuclear Ple.nt are requested:
I.
Section 7 Add the following paragraphs to Section 7 to read as follows:
"7.2.2.1 PLANT REPORTING REQUIREMENTS 7.2.2.1.1 The following information shall be submitted in addition to the reports listed in Table 7.2.2.1-1 and required by Title 10, Code of Federal Regulations.
7.2.2.1.2 Routine Reports:
a.
Operating Reports Operating Reports shall be submitted in writing to the Deputy Director for Reactor Projects, Directorate of Licensing, USAEC, Washington, DC 20515.
4 (1) Semiannual Operating Reports Routine operating reports shall be submitted within 60 days after January 1 and July 1 of each year. These reports should include the following:
(a) Operations Summary A summary of operating experience occurring during the reporting period that relates to the safe operation of the plant, in-cluding a summary of:
(1) changes in plant design; (ii) performance characteristics (eg, equipment and fuelperformance);
(
2 (iii) changes in procedures which were necessitated by (i) and (ii) or which otherwise were required to improve the safety of facility operations; (iv) results of surveillance tests and inspections required by these Technical Specifications; (v) the results of any periodic containment leak rate tests performed during the reporting period; (ti) a brief summary of those changes, tests and ex-periments requiring authorization from the Commission pt:.rsuant to 10 CFR 50 59(a); and (vii) any changes in the plant operating organization which involve positions which are designated as key supervisory per-sonnel consisting of the following: Plant Superintendent, Assistant Plant Superintendent, Technical Engineer, QA Engineer, Maintenance Su-pervisor, Instrument and Control Supervisor, Reactor Engineer and Chem and Radiation Protection Supervisor.
(b) Power Generation A summary of power generated during the reporting period including:
(i) gross thermal power generated (in MWh);
(ii) gross electrical power generated (in MWh);
(iii) net electrical power generated (in MWh);
(iv) number of hours the reactor was critical; (v) number of hours the generator was on-line; and (vi) histogrtun of thermal power vs time.
(c) Shutdowns Descriptive material covering all outages occurring during the reporting period. For each outage, information shall be provided on:
(i) the cause of the outage; (ii) the method of shutting down the reactor (eg, trip automatic rundown, or manually controlled deliberate shutdown);
(iii) duration of the outage; (iv) unit status during the outage (eg,' cold shutdown or hot shutdown); and (v) corrective action taken to prevent repetition, if appropriate.
(
3 (d) Maintenance A discussion of safety-related maintenance (excluding pre-ventative maintenance) performed during the reporting period on systems and
' components that are designated to prevent or mitigate the consequences of postulated accidents or to prevent the release of significant amounts of radioactive material. Included in this category are systems and components which are part of the reactor coolant pressure boundary defined in 10 CFR 550.2(v), any part of the engineered safety features, or associated service and control systems that are required for the normal operation of engin-eered safety features, part of any reactor protection or shutdown system, or part of any radioactive vaste treatment handling and disposal system or other system which may contain sign'ficant amounts of radioactive ma-terial. For any malfunctions for which corrective maintenance was re-quired, information shall be provided on:
(1) the system or component involved; (ii) the cause of malfunction; (iii) the results and effect on safe operation; (iv) corrective action taken to prevent repetition; and (v) precautions taken to provide for reactor safety during repair.
(e) Changes. Tests and Experiments A summary of all changes in the plant design and procedures that relate to the safe operation of the plant shall be included in the Operations Summary section of the;: seniannual reports. Changes, tests and experiments performed during t!.? r. porting period that require authoriza-tion from the Commission Ix. $'
- 10 CFR 50.59(a) are covered in Para-graph 7 2.2.1.2(1)(a) of thae Techni.?al Specifications; however, those changes, tests and experiments that do not require Commission authoriza-tion pursuant to 550.59(a) shall be addressed. The report shall include a brief description and the summary of the safety evaluation for those changes, tests and experiments carried out without pri.'r Commission ap-proval, pursuant to the requirements of $50 59(b) of the Commission's l
regulations, that 'The licensee shall furnish to the Commission, annually
)
)
or at such shorter intervals as may be specified in the license, a report j
k 4
containing a brief description of such changes, tests and experiments, including a summary of the safety evaluation of each.'
(f) Radioactive Effluent Releases A statement of the quantities of radioactive effluents released from the plant, with data summarized on a monthly basis follow-ing the general format of Appendix A of USAEC Safety Guide 21 of January 1972:
(i)
Gaseous Effluents (a) Gross Radioactivity Releases (1) Total gross radioactivity (in curies),
including noble and activation gases released.
(2) Maximum gross radioactivity release rate during any one-hour period.
(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 limit for I-131 releasad.
(c) Particulate Releases (1) Gross radioactivity (8, 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.
(4) Percent of technical specification limit for particulate radioactivity with half-lives greater than eight days.
(ii)
Liould Effluents (a) Gross radioactivity (8, y) released (in curies) excluding tritium and average concentration released to the un-restricted area.
5 (b) Total tritium and alpha radioactivity (in curies) released _and average concentration released to the unrestricted area.
(c) Total dissolved gas radioactivity (in curies) and average concentration released to the unrestricted area.
(d) Total volume (in liters) of liquid waste released.
(e) Total volume (in liters) of dilution water used prior to release from the restricted area.
(f) The maximum concentration of gross radio-activity (8, y) released to the unrestricted area (averaged over the period of release).
(g) Total gross radioactivity (in curies) by nuclide released, based on representative isotopic analyses performed.
(h) Percent of technical specification limit and 10 CFR Part 20 concentration limits for unrestricted areas.
(iii) Solid Waste (a) The totcl amount of solid waste packaged (in cubic feet).
(b) The total estimated radioactivity (in curies) involved.
(c) The dates of shipment and disposition (if shipped off-site).
(g) Environmental Monitoring (i)
For each medium sampled, eg, air, sediment, sur-iuce water, soil or fish including:
(a) Number of sampling locations.
(b) Total number of samples.
(c) Number of locations at which levels are found to be significantly above local backgrounds.
(d) Highest, lowest and the annual average con-centrations 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.
~
6 (ii)
If levels of radioactive materials in environmental media indicate the likelihood of public intakes in excess of 5% of those that could result from continuous exposure to the concentration values listed in Appendix B, ' Cable 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.
(iii) If statistically significant variations of off-site t:nvironmental concentrations with time are observed, correlation of these results with effluent release shall be provided.
(h) Occupational Personnel Radiation Exposure A tabulation of personnel exposures shall be reported for the year in the following groups: less than 100 mrem, 100 - 500 mrem, 500 - 1250 mrem,1250 - 2500 mrem, 2500 - 5000 mrem, above 5000 mrem.
7 2.2.1 3 Nonroutine Reports a.
Reporting of Abnormal Events (1) 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 or telegraph to the Director of the Regional Regulatory Operations Office, followed by a written report within 10 days to the Deputy Director for Reactor Projects, Directorate of Licensing (CC to the Director of the Regional Regulatory Operations Office) in the event of the abnormal oc-currences as defined:
(a) Conditions that result in exceeding a safety limit or that result in safety systems settings less conservative than the limiting safety system setting, or that result in violation of a limiting condi-tion for operations ectablished in the Technical Specifications.
(b) Abnormal degradation of one of the several boundaries which are designed to contain radioactive materials, or any unplanned release of radioactive material.
(c) Uncontrolled or unanticipated changes in reactivity which could significantly affect safety of operations.
(d) Incidents or conditions which prevented or could have prevented the performance of the intended safety function of an engin-eered safety feature or of the reactor protection system.
(
(
7 The written report on these abnormal occurrences, and to the extent possible, the prQLaira.ry telephone and telegraph notifi-cation, shall:
(a) describe, antivze and evaluate safety implications,
'(b) outline the measures taken to assure that the cause of the condition is detemined, and (c) indicate the corrective 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 similar components or systems.
In addition, the written report shall relate any fail-ures or degraded performance of systems and components for the incident to similar equipment failures that may have previously occurred at the plant. The evaluation of the safety implications of the incident should consider the cumulative experience obtained from the record of previous failures and malfunctions of the affected systems and com-ponents or of similar equipment.
b.
Reporting of Unusual Events A written report shall be forwarded within 30 days to the Deputy Director for Reactor Projects, Directorate of Licensing, and to the Director of the Regional Regulatory Operations Office, in the event of:
(1) Discovery of any substantial errors in the transient or accident analyses, or in the methods used for such analyses, as de-scribed in the Final Hazards Summary Report or in the bases for the Technical Specifications.
(2) Any substantial variance from performance specifications contained in tbc Technical Specifications or in the Final Hazards Summ ry Report.
(3) Any condition involving a possible single failure which, for a system designed against assumed single failures, could result in a loss of the capability of the system to perform its safety function.
7.2.2.1.4 special Reports Special reports shall be submitted in writing within 90 days to the Deputy Director for Reactor Projects, Directorate of Licensing, USAEC, Washington, DC 20545
k 8
Special reports shall be submitted covering inspections, tests 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 designated in these Techni-cal Specifications. Examples of subjects for such reports include:
(a) Authorization of changes, tests, and experiments in accordance with 10 CFR 50.59 analyzed as an unreviewed safety question.
(b) Containment leak rate tests.
Table 7.2.2.1-1 as attached includes additional items that are to be reported as specified in their respective sections of the Code of Federal Regulations."
CONSUMERS POWER COMPANY f.
f By:
mrmufv Vice President (/
Date: November 28, 1972 Sworn and subscribed to before me this 28th day of November 1972.
AAA" &
J Notary Public, Jg'ckson County, Michigan My commission expires October 14, 1973 j
i TABLE 7.2.2.1-1 Reporting Swamary AEC Regulation Report 20.403(a)
Severe Accident Involving Licensed Material 20.402 Loss of Licensed Material 73.42 Special Nuclear Material Un-accounted for 40.6h(c)
Theft of Unlawful Diversion of Source Material 70 52 Accidental Criticality or Loss of Special Nuclear Material 70.54 Transfer of Special Nuclear Material 40.64(a)
Transfer of Source Material 20.403(b)
Accidents Involving Licensed Material 20.405(a)
Overexposure or Excessive Radiation Level 20.408 Personnel Exposure (Termin-ated Employees) 70 53 Special Nuclear Material Status
AEC D74IBUTION FOR PART 50 DOCKET MA"AIAL (TEMPORARY FORJ.)
CONTRG. NO:
6542-FIII' FROM: Consumers Power Co.
DATE OF DOC:
- J:ckson, Michigan 49201 R!bert L. Haueter 11-28-72 11-30-72 X
TO:
/
.Mr. John F. O' Leary
'3 signed 37 CLASS:, @ a0P ISFO INPUT No CYS REC'D DOCKET no:
x 40 50-155 DESCRIP2 ION: Ltr trans the following:
ENCLOSURES: Request for Change to tne 1eca Specs Change No. 35 for Lic. DPR-6 notarize <
11-28-72.....
(3 Orig & 37 conf'd cys enc 1 rec'd)
~ 0 p ' *"" ~ 7 2 F
s h,
' j g A.,. @F T '- ~1, T (
i' d. 2." M b ~ U.
PLANT NAMES:
Big Rock Plant.
J FOR ACTION /INFOR.vXfION DL 11-30-72 BUTLER (L)
SCHENCER(L)
SCHEM3L(L)
KNIGhTON(E)
W/ Copics W/ Copics Copies W/ Copies CLARK (L)
STOLS(L)
IEM/u1N(L)
YOUNGBIDOD(E)
W/ Copics W/ Copics W/9 Copics W/ Copics COLLER(L)
VASSALID(L) ~
CHITUOOD(D:)
SEGAN(E)
W/ Copics W/ Copics W/ Copics W/ Copics
- KNIEL(L)
H. DENTON
.DICEER(E)
W/ Copics W/ Copies W/ Copics W/ Copies INTERHAL DISTRIBUTION EGFIID TECH ELVIEW VOLIRER HARLESS WADE E
C PDR EERJ2IB DENTON SHAFER F&M
~
C, ROOM P-506A SCER0EDER GRIMES F&M BROWN E
MUNTZING/ STAFF MACCARY GAF2 ELL SMILEY G. WILLIAMS E CASE LANGE(2)
KASTNER NUSSBAUMER E. GOULBOUBRE L GIAMBUSSO PAULICKI BALLARD A/T IND BOYD-L(BUR)
SHA0 SPANGLER LIC ASST.
EttAIW.AN DJYOUNG-L(PWR)
KNUTH SEitVICE L SALTZMAN 06KOVHOLT-L STFJID EINIRO M/60N L
P. COLLINS MOORE AULLER WIISON L
PLANS HOUSTON DICKER MAIGRET L FQDONALD VMLE& REGION (2)
IDRG YCUNCBLOOD GEARIN ~ L edUBE JEG OPR TEDESCO KNIGHTON SMITH L
MORRIS LAINAS PROJ ImDER DIGGS L
INFO
~
STELLE BENAROYA TEETS L
C. ICLES I.EE I,
REGAN I
E M RNAL DTSTRIBU E N OOOO f nIOIM E E FUUR LEllillML 1-IDCAL PDR
-MIE ABERWsThT)
(1)(5)(9)-NATIONAL LAB'S 1-FDR-SAN /LA/NY
-NSIC BUCHANAN) 1-3. CARROLL-0C, GT-B227 1-GERALD LELIDUCHE 1 ASLB-YORE /SAYRE DWARD/H'.ST.
l-R. CATLIN, E-256'-GT BROOKHAVEN NAT. LAB 1-CONSULANT'S 1-AGMED(WALTER K0 ESTER, 6-CYS ACRS mnnarX SENI TO LIC ASST.
NEWMARK/BLUME/AGABIAN R:3 C 427, GT)
R. DIGGS ON 11-30-72 1-RD... MULLER...F-309GT