ML20078F117
| ML20078F117 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 01/24/1995 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20078F108 | List: |
| References | |
| NUDOCS 9502010323 | |
| Download: ML20078F117 (9) | |
Text
.
15.6'.5.'.7 (Continued) 2 h) Any indication of an unanticipated deficiency in some aspect of design or operation of safety related structures, systems, or I
components.
- 1) Reports and meeting minutes of the Manager's Supervisory Staff.
AUDITS 15.6.5.2.8 Audits of facility activities shall be performed under the cognizance of the OSRC. These audits shall encompass:
a) The conformance of facility operation to provisions contained within the Technical Specifications and applicable license conditions at le t once per yccr.
b) The performance, training and qualifications of the licensed operating staff t le::t once per year.
c) The results of actions taken to correct defic ~iencies occurring in facility equipment, structures, systems or method of operation that affect nuclear safety :t le::t twice per yc r :t :pprcxi=:tely six
=cnth intervels.
d) The results of quarterly audits by the Quality A::urance Divi:icn j@My[jyRjjj{[j gjjliijjij on the performance of activities required by the Quality Assurance Program to meet the criteria of Appendix B,10 CFR 50, et le :t once per twc year:.
e) Any other area of facility operation considered appropriate by the President.
AUTHORITY 15.6.5.2.9 The OSRC shall report to and advise the President on those areas of responsibility specified in Section 15.6.5.2.7 and 15.6.5.2.8.
i i
Unit 1 - Amendment 15.6.5-6 Unit 2 - Amendment 9502010323 950124 PDR ADOCK 05000266 P
15.6.5.3 Fire Protection Audits a) An independent fire protection and loss prevention inspection and audit shall 50 performed :nn";11y utilizing either qualified offsite license personnel or an outside fire protection firm.
e s,
,.,,..r...,-.
.-. A
.. A 4... c.. L.
- r. e...-r..-.a....
r....-.4...=.
-A
-m_
-..-am -, L.- 1 1 L.
y.-
- t..o m-n.A L,o. -...
4.
4..Aa y..= 1 4. r. t. a.A
- t. i. m..a
... 1 6.
. 6..
mu r,...-
.= 4
- 4.. 4..m m.o 1.,.- a m.a.= 4..- m.
- 4. L..= =..9
,on m.
- 1. e.. e.. e.,.
e-- m.
..., o,-. o..n.......
a-_..
-e.
- 6. L.. ar..a m.
\\
,A, m,.a u.t. au.s t
,ma-=m.a.A..a hm..a a m, n,.,.
.=..
L..= 1 1 k.m mam,f, a. m.-a.A m a. n o, e.
r.
afme 1,1. o, u. 6 41 4.
- 4..a, a 4. +. L..a m.a f. f. e. l. e..n 1 4.,.a. c. a.....
.am, e....n -.a1
- m. m, n
- 4..,,1..A.a r
.o.,1...
.... 1 4 1.a t, i, m-T. k..a
. A t. e.
, L...= 1 1 L..a m.a A. a e..n.A
,,mm..A a
4-
....a.s
- a. y
, m.
s s
. i...
a.s
..v
.i.
Mo.k. i. n.
P. r o E n.. E A, s.1
.a f. r. a, 6. J. o. n e n
- e. n.L a m
- 1., i n..O S.
f4, a-
..r l
l I
Unit 1 - Amendment No.
15.6.5-8 Unit 2 - Amendment No.
degassed (other than normal gas stripping of the letdown flow).
If the monitoring system is out of service for greater than 14 days, in addition to the above sampling, a report of the cause and corrective action for failure and repair of the gas monitor shall be included inthegjjjilS::i:nn;:1MonitoringReport.
jj Note 8:
If the number of channels operable is fewer than the minimum re-quired, effluent releases via this pathway may continue provided grab samples are collected twice per week and analyzed in acaordance with Table 15.7.6-1.
Note 9:
If the number of channels operable is fewer than the minimum re-quired, effluent releases via this pathway may continue provided the flow is estimated or determined with auxiliary indication at least once every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
1 4
Unit 1 Amendment 15.7.3-7 Unit 2 Amendment
NOTES FOR TABLE 15.7.6-1 1.
The principal gamma emitter for which the gamma isotopic LLD applies is Cs-137. Because gamma isotopic analyses are performed, the LLDs for all other gamma emitters are inherently determined by the operating characteristics of the counting system. All identifiable gammaemitterswillbereportedinthe$@@silS::i:::::1 Monitoring Report.
2.
A batch release is the discharge of liquid wastes of a discrete volume.
Prior to sampling for analyses each batch shall be isolated and mixed to assure representative sampling.
3.
A continuous release is the discharge of liquid wastes of a non-dis-crete volume; e.g., from a volume of a system that has an input flow during the release.
4.
A continuous composite is one in which the method of sampling employed results in a specimen that is representative of the liquids released.
5.
Identified entrained noble gases shall be reported as gaseous effluents, i
t Unit 1 - Amendment 16.7.6-2 Unit 2 - Amendment
NOTES FOR TABLE 15.7.6-2
- 1. The principal gamma emitters for which the LLD specification applies are Cs-137 in particulates and Xe-133 in gases. Because gamma isotopic analyses are performed, the LLDs for all other gamma emitters are inherently determined by the operating characteristics of the counting system. All identifiaule gamma emitters will be reported in the((isilS::!:::::1MonitoringReport.
- 2. Tritium g.ab samples will be taken every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> when the refueling cavity is flooded.
i
- 3. The ratio of the sample flow rate to the release flow rate shall be t
known or estimated for the time peric9 covered by each sampling i
interval.
- 4. Tritium grab samples will be taken every seven days from the drumming area ventilation exhaust / spent fuel pool area whenever there is spent fuel in the spent fuel pool.
l Unit 1 - Amendment 15.7.6-3 Unit 2 - Amendment
15.7.7 OPERATIONAL ENVIRONMENTAL MONITORING PROGRAM Anolicability i
This section applies to operational environmental radioactivity monitoring and f
sampling.
l l
Ob_iective To verify that plant operations have no significant radiological effects on the environment.
l t
Specifications i
A.
Environmental Monitorina Proaram 1.
Environmental monitoring samples shall be taken at locations specified in the PBNP Environmental Manual according to the sampling and collection frequencies given in Table 15.7.7-1.
2.
Deviations from the required sampling schedule as specified in i
Table 15.7.7-1, are permitted if hazardous conditions, seasonal unavailability, automatic sampling equipment malfunctions, and j
other legitimate reasons make the sample unobtainable.
If the radiological environmental monitoring program is not being con-ducted as specified in Table 15.7.7-1, a description of the reasons for not conducting the program and the plans for preventing a f
recurrence will be submitted with the next FriM1 Semi==1
(
Monitoring Report.
{
3.
If milk or vegetation samples become unavailable from one or more of the sample locations specified in the PBNP Environmental Manual, l
identify locations for obtaining replacement samples and add them to the radiological environmental monitoring program within 30 d:,s..
The specific locations from which samples were unavailable j
may then be deleted from the monitoring program. The cause of the unavailability of samples and replacement samples shall be l
t Unit 1 - Amendment No.
15.7.7-1 I
Unit 2 - Amendment No.
y-,
I
\\
~
identified in the next @^dil S::i===1 Monitoring Report.
Figures and tables in the Environmental Manual are to be revised reflecting the new sample locations.
B.
Detection Capabilities 1.
Environmental samples shall be analyzed as specified in Table 15.7.7-2.
I 2.
The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs).
3.
If circumstances render the stated LLDs in Table 15.7.7-2 unachiev-able, the contributing factors shall be identified and described in next Semiannual Monitoring Report.
j C.
Notification levels 1.
If a measured level of radioactivity in any environmental medium exceeds the notification level listed in Table 15.7.7-3, resampling and/or reanalysis for confirmation shall be completed within 30 days i
of the determination of the anomalous result.
If the confirmed measured level of radioactivity remains above the notification level, a written report shall be submitted to the NRC in accordance with Section 15.7.8.4.B within thirty days of the confirmation. This report is not required if the measured level of radioactivity was not the result of plant effluents.
2.
If more than one of the radionuclides listed in Table 15.7.7-3 are detected in any environmental medium, a weighted sum calculation shall be performed if the sneasured concentration of a detected radionuclide is greater than 25% of the notification levels. For j
those radionuclides with LLDs in excess of 25% of the notification level, a weighted sum calculation need only be performed if the reported value exceeds the LLD. The weighted sum is calculated as follows:
concentration (1)
+
concentration (2)
+...
weighted notification icvel (1) notification level (2) sum j
If the calculated weighted sum is equal to or greater than 1, resampling and/or reanalysis for confirmation shall be completed within 30 days of the determination of the anomalous result.
If Unit 1
^ 0 + ent Ne. !!'
15.7.7-2
,pril IS, la S Unit 2 - fr. d ::t NO. 117
the confirmed calculated weighted sum remains equal to or greater than 1, a written report shall be submitted to the NRC in accordance with Section 15.7.8.4.B within thirty (30) days of the confirmation.
This calculation requirement and report is not required if the measured level of radioactivity was not the result of plant effluents.
3.
All detected radionuclides shall be reported in the f~jpiiH Sc=i nn=1 Monitoring Reports.
Naturally occurring nuclides such as Be-7, K-40, and the U-238 and Th-232 decay series radionuclides shall not be included in this requirement.
D.
Land Use Census 1.
The milk sampling program shall be reviewed annually, including a visual verification of animals grazing in the vicinity of the site boundary, to ensure that sampling locations remain as conservative as practicable.
E.
Interlaboratory Comoarison Prooram 1.
The environmental sampling analyses shall be performed by a laboratory participating in an Interlaboratory Comparison Program.
2.
If the analytical laboratory is not participating in the Inter-laboratory Comparison Program, a description of the corrective actions to be taken to preclude a recurrence shall be submitted in the66hhilSemiannualMonitoringReport.
Basis The operational radiological environmental monitoring program as outlined in Table 15.7.7-1 provides sufficient sample types and locations to detect and to evaluate changes in environmental radioactivity. Although radioactivity in plant effluents is continuously monitored and releases are well below levels which are considered safe upper limits, radiological environmental monitoring is a conservative measure undertaken to determine whether the operation of the Point Beach Nuclear Plant produces any significant radiological change in the surrounding environment.
Radioactivity is released in liquid and gaseous effluents. Air particulate samples and thermoluminescent dosimeters placed at various locations provide means of detecting changes in environmental radioactivity as a result of plant releases to the atmosphere.
Unit 1 - ?:en 6cnt Nc. 97-15.7.7-3
=0ctober 10, 1935 Unit 2 - ? en tent Mc. 101-
1 t
e 15.7.8 ADMINISTRATIVE CON 1ROLS 15.7.8.1 Duties of the Manaaer's Supervisory Staff The duties of the Manager's Supervisory Staff with respect to these radiological effluent technical specifications are listed in Specification 15.6.5.1.6 at Items j. and k.
15.7.8.2 Audits A.
An audit of the activities encompassed by the Offsite Dose Calculation Manual and the Process Control Program and its implementing procedures shall be performed -' '---' ----
cvery 24 = nth: utilizing either offsite licensee personnel or a consulting firm.
B.
An audit of the radiological environmental monitoring program and the results thereof shall be performed :t le::t once every 12 =nths utilizing either offsite licensee personnel or a qualified consulting firm.
C.
The rc: ult: cf th: : dit; in A :nd B abcvc ch:11 he tr:n:
=itted to the Vice Prc ident Nucle:r Pcwcr and the Chair :n cf the Off:ite Review Cc=ittee.
15.7.8.3 Plant Operatina Procedures The ODCM and the PCP shall be established and maintained in accordance with the provisions of specification 15.6.8.
Effluent and i
environmental monitoring shall be addressed in the Quality Assurance Program.
15.7.8.4 RETS Reportina Reouirements The following written reports shall be submitted to the Administra-i tor, U.S. Nuclear Regulatory Commission Region III with a copy to the Director, Office of Inspection and Enforcement, USNRC, Washington, D.C. 20555 within the time periods specified.
A.
Anh^dil Sc icnnual Monitorina Report A report E6?Rf6Ethilyjiipf}66jlf[PBNPZf6f[tlii]pFi@ssilisi]js UO6sW#ifl6OEffiEnssIMEsiCs4MiiWOsEsiEQH sh..^n.1.1. 3. F,7sL6.E_f.t.tsd. Iby~IHa. yi1Es,iEF.jii,f, within 50 d:y: :fter
~~
J:nu:ry 1 :nd July I c:ch ye for th: ;ix rath period cr f
hac-t4cn therecf, ending June 30 :nd Occ=ber 31 containing:
i Unit 1 - Amendment No.
15.7.8-1 Unit 2 - Amendment No.
.