ML17139C076
| ML17139C076 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/12/1983 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17139C078 | List: |
| References | |
| NUDOCS 8312280214 | |
| Download: ML17139C076 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 PENNSYLVANIA POWER AND LIGHT COMPANY D CKET N
. 50-3 SUSQUEHANNA S ELEC R
S TION UNIT 1 MENDMENT F CILITY PER TING LI NS Amendment No. 2O License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for amendment filed by the Pennsylvania Power and Light Company, dated August 15, 1983, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's 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 regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized 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 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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2o
, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PPSL shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
83i22802i4 83i2i2 PDR ADOCK 05000387 P
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3.
This amendment is efFective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications 0"'gimel gj~~g hat A. Schwencer, Chief Licensing Branch No.
2 Division of Licensing Date of Issuance:
December 12, 1983 DL L PM RLPerch:pt 11/ZS/83 DL:L
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ATTACHMENT TO LICENSE AMENDMENT NO, 20 C L 0
N.
-3 Replace the following pages of the Appendix "A" Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 3/4 7-41 3/4 7-42 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12 INSERT 3/4 7-41 3/4 7-42 3/4 11-9 3/4 11-10 3/4 11-11 3/4 11-12
LOCATIONS TABLE 3. 7. 6. 5"1 FIRE HOSE STATIONS COLUMN HOSE RACK NUMBER a ~
Control Structure El.
El.
El.
El.
El.
El.
El.
El.
El.
El.
b.
Re ac El.
El.
Fl.
El.
El.
El.
El.
El.
El.
El.
El.
El.
El.
El.
C]
El.
El.
El..
El.
El.
El.
El.
El.
El.
El.
El.
El.
El.
697'-0" 697'-O" 714'-0" 714'-0" 729'-0" 729 I
0ll 754'-0" 754'-O" 771'-0" 771 I
Pll tor Building 645'-0" 645'-0" 645'-o" 645'-0" 645'-0" 645'-0" 67O'-O" 67O'-O" 670'-0" 683'-0" 683'-0" 683'-0" 719'"1" 719'-1" 719'-1" 719'-1" 719'-1" 749'-1" 749'-1" 749'-1" 779 I -1" 779'-1" 779 1
779'-1" 799'-1" 818'-1" 818'-1" 818'-1" L-26 L"32 L-26 L-31 L"25. 9 L-32. 1 L-26 L-32 L-26 L-31 R"29 P-20. 6 U-22 R-37. 4 U"30.5 R-30 Q"27.5 Q-29 T-22 Q-27.5 Q-20.6 T-22 Q-27.5 5-27.5 Q-20.6 T-20.6 T-23. 5 5-27. 5 Q"20.6 T-20.6 P-26.5 S.-26. 5 Q-22 U-20.6 T-23.3 P-26.5 U-26.5 Q-20.6 1HR"171 2HR-171 1HR"162 2HR-162 1HR-158 2HR-158 1HR-136 2HR-136 1HR"125 2HR-125 1HR-271 1HR-272 1HR-273 2HR"271 2HR-272 2HR-273 1HR-261 1HR-262 1HR-263 1HR-251 1HR-252 1HR-253 1HR-241 1HR-242 1HR-243 1HR-244 1HR-245
'HR-231 1HR-232 1HR-233 1HR-221 1HR-222 1HR-223 1HR-224 1HR-211 1HR-201 1HR-202 1HR-203 SUSQUEHANNA " UNIT 1 3/4 7-41 AMENDMENT No.
20
PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES LIMITING CONDITION FOR OPERATION 3.7.6.6 Yard fire hydrants 1FH122 and 1FH104 and associated hydrant hose houses shall be OPERABLE.
APPLICABILITY:
Whenever equipment in the areas protected by the yard fire hydrants is required to be OPERABLE.
ACTION:
With yard fire hydrants 1FH122 and/or 1FH104 and/or associated hydrant hose houses inoperable, route sufficient additional lengths of fire hose of equal or greater diameter located in adjacent OPERABLE hydrant hose house(s) to provide service to the unprotected area(s) within one hour.
Restore the inoperable hydrant(s) and/or hose house(s) to OPERABLE status within 14 days or, in lieu ot any other report required by Specification 6.9. 1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.
b.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
SURVEILLANCE RE UIREMENTS 4.7.6.6 Yard fire hydrants 1FH122 and 1FH104 and associated hydrant hose houses shall be demonstrated OPERABLE:
a.
b.
C.
At least once per 31 days by visual inspection of the hydrant hose hoses to assure all required equipment is at the hose houses.
At least once per 6 months, during March, April or May and during September, October or November, by visually inspecting the yard fire hydrants and verifying that the hydrant barrels are dry and that the hydrants are not damaged.
At least once per 12 months by:
1.
Conducting hose hydrostatic tests at a pressure of 150 psig or
.at least 50 psig above the maximum fire main operating pressure, whichever is greater.
2.
Replacement of all degraded gaskets in couplings.
3.
Performing a flow check of each hydrant.
SUS(UEHANNA - UNIT 1 3/4 7-42
RADIOACTIVE EFFLUENTS 3/4. 11.2 GASEOUS EFFLUENTS DOSE RATE LIMITING CONDITION FOR OPERATION
- 3. 11.2.1 The dose rate due to radioactive materials released in gaseous effluents from the site (see Figure 5.1.3-1) shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 mrems/yr to the total body and less than or equal to 3000 mrems/yr to the skin, and b.
For iodine-131, for tritium, and for all radionuclides in particulate form with half lives greater than 8 days:
Less than or equal to 1500 mrem/yr to any organ.
(Inhalation pathways only.)
APPLICABILITY: At al 1 times.
ACTION With the dose rate(s) exceeding the above limits, immediately restore the releas~
rate to within the above limits.
SURVEILLANCE RE UIREMENTS 4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters of the ODCM.
- 4. 11. 2. 1: 2 The dose rate due to iodine-131, tritium, and all radionuclides in particulate form with half lives greater than 8 days in gaseous effluents shall be. determined to be within the above limits in accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4. 11. 2. 1. 2-1.
SUS(UEHANNA - UNIT j.
3/4 11-9
RADIOACTIVE GASEOUS WASTE SAMPLING At<D ANALYSIS PROGRAM Gaseous Release Type
~
A.
Containment Purge B.
Reactor Building Vents, Turbine Building Vents, and SGTS C.
All Release Types as listed in A and B.
Sampling Frequency P
b Each Purge Grab Sample Grab Sample Continuous f Continuous Continuous f Continuous f Continuous f Minimum Analysis Frequency P
b Lach Purge Mb W
Charcoal Sample Wc,d Particulate Sample Composite Particulate Sample Q
Composite Particulate Sample Noble Gas Monitor Type of Activity Analysis Principal Gamma Emitters II-3 Principal Gamma Emitters H-3 I-131 Principal Gamma Emit ters (I-131, Others)
Gross Alpha Sr-89, Sr-90 Noble Gases Gross Beta or Gamma Lower Limit of Detection (LLD)
(IiCi/ml) 1xl0 lxlO lxl0 lxl0 lxl0 12 lxl0 1 xl0 11 lx10 11 1 xl0 (XE-133 equivalent)
TABLE 4. 11. 2. 1.2-1 (Continued)
TABLE NOTATION The LLD is the smallest concentration of=radioactive material that will be detected with 95M probability with 5 m probability of falsely concluding that a
blank observation represents a "real" signal.
For a particular measurement systems (which may include radiochemical separation):
LLD =
4.66 sb E
~
V
~ 2.22 x 106
~
Y exp (-Mt)
Mhere:
LLD is the
~a riori lower limit of detection as defined above (as microcuries per unit mass or volume),
s is the standard deviation of the background counting rate or of tie counting rate of a blank sample as appropriate (as counts per minute),
E ',s the counting efficiency (as counts per disintegration),
V is the sample size (in units of mass or volume),
2.22 x 106 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield (when applicable),
js the radioactive decay constant for the particular radionuclide, and bt is the elapsed time between midpoint of sample collection and time of counting (for plant effluents, not environmental samples)
The value of sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverfied theoretically predicted variance.
Typical values of E, V, Y, and bt shall be used in the calculation.
SUSQUEHANNA - UNIT 1 3/4 11-11
TABLE 4. 11.2. 1.2-1 (Continued)
TABLE NOTATION b.
If the iodine or particulate monitoring channel(s) is(are) inoperative, analyses shall also be performed following shutdown,
- startup, or a THERMAL POWER change exceeding 15 percent of the RATED THERMAL POWER within a one hour period.
c.
Particulate and/or charcoal samples shall be analyzed when an alarm is received indicating rate of activity buildup exceeds 3 times normal d.
Samples shall be changed at least once per 7 days and analyses shall be completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> after changing, or after removal from sampler.
If the iodine or particulate monitoring channel(s) is (are) inoperative, sampling shall also be performed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for at least 7 days following each
- shutdown, startup or THERMAL POWER change exceeding 15 percent of RATED THERMAL POWER in one hour and analyses completed within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of changing.
When samples collected for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> are
- analyzed, the corresponding LLDs may be increased by a factor of 10.
e.
(Dele ed) f.
The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with Specifications
- 3. 11.2. 1,
- 3. 11.2.2 and 3. 11.2.3.
g.
The principal gamma emitters for which the LLD specification applies exclusively are the following radionuclides:
Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particul.ate emissions.
This list does not mean that only these nuclides are to be considered.
Other gamma peaks which are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Sem/annual Radioactive Effluent and Release
- Report, pursuant to Specification 6.9. 1. ll.
h.
Under the provisions of footnote g, above, only noble gases need to be considered.
SUSQUEHANNA - UNIT 1 3/4 11"12 AMENDMENT NO.