ML20206Q849
| ML20206Q849 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley (DPR-66-A-102) |
| Issue date: | 06/24/1986 |
| From: | Rubenstein L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20206Q855 | List: |
| References | |
| NUDOCS 8607030402 | |
| Download: ML20206Q849 (7) | |
Text
.
((g>3 KEGg UNITED STATES
~ ',
3 NUCLEAR REGULATORY COMMISSION g
. j WASHINGTON, D. C. 20555
\\...../
DUQUESNE LIGHT COMPANY OHIO EDISON COMPANY PENNSYLVANIA POWER COMPANY DOCKET NO. 50-334 REAVER VALLEY POWER STATION, UNIT NO. 1 AMEN 0 MENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. DPR-6f 1.
The Nuclear Regulatory Comission (the Commission) has found that:
A.
The application for amendment by Duquesne Light Company, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated February 5,1986, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 Comission; C.
There is reasonable assurance (1) that the activities authorized I-by this amendment 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 amendment will not be inimical to the common defense and security or to the health and safety of the pubitc; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission'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 R.C.(2) of Facility Operating License No. OPR-66 is hereby amended to read as follows:
8607030402 86064, PDR ADOCK 05000334 P
(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.102, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical I
Specifications.
3.
This amendment is effective on issuance, to be implemented no later than 30 days after issuance.
FOR THE NUCLEAR REGULATORY COWISSION g Lester S. Rubenstein, Director g PWR Proiect Directorate #2 Division of PWR Licensing-A
Attachment:
Changes to the Technical Specifications Date of Issuance: Jur.e 24,1986 0
0
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT.NO. 102 TO FACILITY OPERATING LICENSE NO. DPR-66 DOCKET NO. 50-334 Revise Appendix A as follows:
Remove Pages Insert Pages 3/4 4-18 3/4 4-18 3/4 4-19 B 3/4 4-5 B 3/4 4-5 6-14 6-14 6-23 6-23 e
e 0
O e
e
,e-
i REACTOR COOLANT SYSTEM SPECIFIC ACTIVITY LIMITING CONDITION FOR OPERATION 3.4.8 The specific activity of the primary coolant shall be limited to:
1 1.0pci/ gram DOSE EQUIVALENT I-131, and a.
b.
1 100/EIpCi/ gram.
APPLICABILITY:
MODES 1, 2, 3, 4 and 5 ACTION MODES 1, 2, and 3*
a.
With the specific activity of the primary coolant >1.0 pCi/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limit line shown on Figure 3.4-1, be in HOT STANDBY with Tavg
<500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b.
With the specific activity of the primary coolant > 100/EI l
uCi/ gram, be in HOT STANDBY with Tavg < 500*F within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
MODES 1, 2, 3, 4 and 5 a.
With the specific activity of the primary _ coolant > 1.0 pCi/ gram DOSE EQUIVALENT I-131 or > 100/E pCi/ gram, perform the sampling and analysis requirement of item 4a of Table 4.4-12 until the specific activity of the primary coolant is restored to within its limits.
SURVEILLANCE REQUIREMENTS 4.4.8 The specific activity of the primary coolant shall be determined to be within the limits be performance of the sampling and analysis program of Table 4.4-12.
I l
- With Tavg 1 500*F O
BEAVER VALLEY - UNIT 1 3/4 4-18 (next page is 3/4 4-20)
Amendment No. H,102
.= -
-.-. --.)
i REACTOR COOLANT SYSTEM BASES
,e The ACTION statement permitting POWER OPERATION to continue for limited time periods with the primary coolant's specific activity 1.0 pCi/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.
Operation with specific activity levels exceeding 1.0 pCi/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limits shown on Figure 3.4-1 must be restricted since the activity levels allowed by Figure 3.4-1 increase the 2-hour thyroid dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.
Reducing T
to
<500*F prevents the release of activity avheneratortuberupturesincethesaturationpressure should a
steam of the primary coolant is below the lift pressure of the atmospheric steam relief valves.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action.
Information obtained on iodine spiking will be used to assess the parameters associated with. spiking phenomcna.
A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.
3/4.4.9 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.
These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations.
the various categories of load cycles used for design purposes are provided in Section 4.1.4 of the FSAR.
During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.
During
- heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from compressive at the inner wall to tensile at the outer wall.
These thermal-induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure.
Therefore, a pressure-temperature curve based on steady state conditions (i.e.,
no thermal stresses) represents a lower bound of all similar curves for finite heatup rates when the inner wall of the vessel is treated as the governing location.
BEAVER VALLEY ' UNIT 1 JB 3/4 4-5
/Wendment No.102
=.
RERCTOR COOLRNT SYSTEM BASES a
The ACTION statement permitting POWER OPERATION to continue for limited time ceriods with the primary coolant's specific activity 1.0 uCi/ gram DOSE EQUIVALENT I-131, but within the allowable limit shown on Figure 3.4-1, accommodates possible iodine spiking phenomenon which may occur following changes in THERMAL POWER.
Operation with specific activity levels exceeding 1.0 pCi/ gram DOSE EQUIVALENT I-131 for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval or exceeding the limits shown on Figure 3.4-1 must be restricted since the activity levels allowed by Figure 3.4-1 increase the 2-hour thyroid dose at the site boundary by a factor of up to 20 following a postulated steam generator tube rupture.
Reducing T
to
<500*F prevents the release of activity avheneratortuberupturesincethesaturationpressure should a
steam of the primary coolant is below the lift pressure of the atmospheric steam relief valves.
The surveillance requirements provide adequate assurance that excessive specific activity levels in the primary coolant will be detected in sufficient time to take corrective action.
Information obtained on iodine spiking will be used to assess the. parameters associated with spiking phenomena.
A reduction in frequency of isotopic analyses following power changes may be permissible if justified by the data obtained.
3/4.4.9 PRESSURE / TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.
These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations.
the various categories of load cycles used for design purposes are provided in Section 4.1.4 of the FSAR.
During startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.
During
- heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from compressive at the inner l
wall to tensile at the outer wall.
These thermal-induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure.
Therefore, a pressure-temperature curve based on steady state conditions (i.e.,
no thermal stresses) represents a lower bound of all similar curves for finite heatup rates when the inner wall of the vessel is treated as the governing location.
.)
BEAVER VALLEY ' UNIT 1
.]B 3/4 4-5
/Wendment No. 102
ADMINISTRATIVE CONTROLS i,
ANNUAL REPORTS 1 6.9.1.4 Annual reports covering the activities of the unit as I
described below for the previous calendar year shall be submitted prior to March 1
of each year.
The intitial report shall be submitted prior to March 1
of the year following intitial I
criticality.
6.9.1.5 Reports required on an annual basis shall include:
a.
A tabulation of the number of
- station, utility, and other personnel (including contractors) receiving exposures greater than 100 mrem /yr and their associated man-rem exposure according (e.g.,
reactor operations and to work and job functions 2 surveillance, inservice inspection, routine maintenance, special maintenance (describe maintenance),
waste processing, and refueling).
The dose assignments to various duty functions may be estimated based on pocket dosimeter,
- TLD, or fi'im badge measurements.
Small exposures totalling less than 20 percent of the individual total dose need not be acounted for.
In the aggregate, at least 80 percent of the total whole body dose received from external sources should be assigned to specific major work functions.
b.
Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or pressurizer safety valves.
I The results of specific activity analysis in which the primary r
coolant exceeded the limits of Specification 3.4.8.
The j
following information shall be included:
(1)
Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to.the first sample in which the i
limit was exceeded; (2) Results of the last isotopic analysis for i
radiciodine performed prior to' exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine activity was reduced to less than limit.
Each result should include date and time of sampling and the radiciodine concentrations; (3)
Clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration and one other i
radiciodine isotope concentration in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5)
The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.
l 2
A single submittal may be made for a multiple unit site.
The submittal should combine those sections that are commmon to all units at the site.
2 This tabulation supplements the requirements of Section 20.407 of 10 CFR Part 20.
BEAVER VALLEY - UNIT 1 6-14 Amendment No. 74.102 l
-n,..
ADMINISTRATIVE CONTROLS 4
a.
ECCS Actuation, Specifications 3.5.2 and 3.5.3..
j b.
Inoperable Seismic Monitoring Instrumentation Specification 3.3.3.3.
c.
Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
d.
Seismic event analysis, Specification 4.3.3.3.2.
e.
Sealed source leakage in excess of limits, Specification 4.7.9.1.3.
j f.
Fire Detection Instrumentation, Specification 3.3.3.6.
g.
Fire Suppression Systems, Specifications 3.7.14.1, 3.7.14.2 and 3.7.14.3 and 3.7.14.5.
1 i
h.
Miscellaneous reporting requirements specified in the Action Statements for Radiological Effluent Technical i
Specifications.
l 1.
Containment Inspection Report, Specification 4.6.1.6.2.
l 6.10 RECORD RETENTION i
l 6.10.1 The following records shall be retained for at least five (5) years:
a.
Records and logs of facility operation covering time interval at each power level.
b.
Records and logs of principal maintenance activiti$s, inspections, repair and replacement of principal items of equipment related to nuclear safety.
c.
All REPORTABLE EVENTS.
d.
Records of surveillance activities, inspections and calibrations required by these Technical Specifications.
e.
Records of reactor tests and experiments.
f.
Records of changes made to Operating Procedures.
g.
Records of radioactive shipments.
h.
Records of sealed source leak tests and results.
i.
Records of annual physical inventory of all sealed source j
material of record.
BEAVER VALLEY UNIT 1 6-23 Amendment No. H, 102
.