ML17059C018
| ML17059C018 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 05/23/1998 |
| From: | Bajwa S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059C019 | List: |
| References | |
| NUDOCS 9806010008 | |
| Download: ML17059C018 (20) | |
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UNITED STATES NUCLEAR'EGULATORYCOMMISSlON WASHINGTON, D.C. 20555-0001 NIAGARAMOHAWKPOWER CORPORATION DOCKET NO. 50-220
'INE MILEPOINT NUCLEAR STATION UNIT 1 AMENDMENTTO FACILITYOPERATING LICENSE
'mendment No. 161 License No.'PR-63
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Niagara Mohawk Power Corporation (the licensee) dated May 2, 1998, as supplemented by letters dated May 21, and 23 (three letters),
1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B. The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and 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 willbe 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 Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-69 is hereby amended to read as follows:
98060%0008 980523 PDR ADOCK 05000220 P
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, both ofwhich are attached hereto, as revised through Amendment No. 161 are hereby incorporated into this license.
Niagara Mohawk Power Corporation shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
In addition, the license is amended to add new page 3B, containing paragraph C(4), to Facility Operating License No. DPR-63 as follows:
C(4)
The licensee shall submit an application for license amendment, including supporting analyses and evaluations by December 18, 1998. This amendment application shall contain the proposed methods for compliance with GDC 19 dose guidelines under accident conditions based upon system design and without reliance upon the use of potassium iodide.
3.
This license amendment is effective as of the date of its issuance to be implemented prior to resumption of power operation.
This amendment is authorized contingent on compliance with commitments provided by the licensee to meet the dose limits associated with Title 10, Code of Federal Regulations, Part 50, Appendix A, General Design Criterion (GDC) 19 by submitting a license amendment application including supporting analyses and evaluations by December 18, 1998, that contains the proposed methods for compliance with GDC 19 dose limits under accident conditions based on system design and without reliance on the use of potassium iodide.
FOR THE NUCLEAR REGULATORY COMMISSION S. Singh Bajwa, Director Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
- 1. Page 3B of License DPR-63'.
Changes to the Technical Specifications Date of Issuance:
May 23, 1998
'Page 3B is attached for convenience, for the composite license to reflect this change.
-3B-C(4)
The licensee shall submit an application for license amendment, including supporting analyses and evaluations by December 18, 1998. This amendment application shall contain the proposed methods for compliance with GDC 19 dose guidelines under accident conditions based upon system design and without reliance upon the use of potassium iodide.
Amendment No. 161
ATTACHMENTTO LICENSE AMENDMENTNO. 161 AMENDMENTNO. -161 TO FACILITYOPERATING LICENSE NO. DPR-63 DOCKET NO. 50-220 4
Replace the following page of the Appendix A Technical Specifications with the attached page.
Remove 99 100 180 246 247 Insert 99 100 180 246 247 247a (new)
UMITINQCONDION FOR OPERATION SURVEILLANCEREQUIREMENT 3.2.4 REACT R
OOLANTACTIVITY 4.2e4 REACTOR OOLANTAC VI A~I Applies to the limits on reactor coolant activity at all operating conditions.
~Ob'e ive:
To assure that in the event of a reactor coolant system line break outside the drywefl permissibfe doses are not exceeded.
~At a.
Applies to the periodic testing requirements of the reactor coolant activity.
~Ob'ee ive:
To assure that limits on coolant activity are not-exceeded.
a.
The reactor coolant system radioactivity concentration in water shall not exceed 9.47 microcuries of total iodine per gram of water.
a.
Samples shall be taken at least every 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> and analyzed for gross gamma activity.
b.
IfSpecification 3.2e4a, above. cannot be met after a routine surveillance check, the reactor shafl be placed ln the cofd shutdown condition within ten hours.
b.
Isotopic analyses of samples shafl be made at least once par month; AMENDMENTNO. D9 161 99
I
BASfS FOR 3.2.4 AND4.2 4 REACTOR COOLANTACTlVITY The primary coolant radioactivity concentration limitof 25 yC3 total fodine per gram of water was cafcufated based on a steamHne break accident which is isolated in 10e5 seconds.
For this accident analysis, all the iodine ln the mass of coolant released fn this time period fs assumed to be refeased to the atmosphere at the top of the turbine building (30 meters).
By Hmiting the thyroid dose at the site boundary to e maximum of 30 Rem, the iodine concentration in the primary coolant is backwafcufated assuming fumigation meteorology, PasquBI Type F at im/sec. The.Iodine concentration in the primary coolant resulting from this analysis fs 25 pCi/gms A radioactivity concentration Hmit of 25 yCi/g total iodine coufd only be reached ifthe gaseous effluants were near the limitbased on the assumed effluent isotopic content fyabfs A-12 of ths FSAftf end ths fact that the primary coolant cleanup systems were inoperative. ~
the cleanup system is operating, ft is expected that the prfmary coofant radioactivity would be about
$2yCI/g total Iodine. The concentrations expected during operatfons with a gaseous eNuent of about 0.1 pCi/sec would be about 1.5 gCi/g total iodine.
The reactor water sample vn11 be used to assure that the limitof Specificatfon 3.2.4 fs not exceeded.
The total radioactive iodine.activity woufd not be expected to change rapidly over a perfod of 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br />.
In addition, the trend of the stack offgas relaase rate, which fs continuously monitored, Is a good indicator of the trend of the iodine activity in the reactor coolant.
Since the concentration of radioactivity fn the reactor coolant fs not contlnuousfy measured, coofa'nt sampHng would be tneffective as a means to rapidly detect gross fuel element failures. However. as discussed fn the bases for Specification 3.6.2. some capability to detect gross fuel element faifures fs inherent fn the radiation monitors fn the offgas system and on the main steam Hnes..
A more restrictive reactor coolant total iodine limithas been imposed for Control Room habitabity purposes only. A limitof 9.47yCI/g fs imposed based on the most limiting small break LOCA outside containment.
Provfded reactor coolant iodfne is maintafnad at or below this value, the Control Room AfrTreatment System woufd not be requfred to maintain the radfofogfcal effects of the fina break befow GDG19 dose fimits.
AMENDMENI'No Nf 161 400
BASES FOR 3.4.5 AND 4.4.5 CONTROL ROOM AIR TREATMENTSVSTEM The control room air treatment system is designed to filter the control room atmosphere for intake air. A roughing filter is used for recirculation flow during normal control room air treatment operation.
The control room air treatment system is designed to maintain the control room pressure to the design positive pressure (one-sixteenth inch water) so that all leakage shovld be out leakage.
The control room air treatment system starts automatically upon receipt of a LOCA (high drywell pressure or low-low reactor water level) or Main Steam Line Break (MSLB) (high steam flow main-steam line or high temperature main-steam line tunnel) signal.'he system can also be manually initiated.
High efficiency particulate absolute (HEPA) filters are installed beFore the charcoal adsorbers to prevent clogging of the iodine adsorber.
The charcoal adsorbers are installed to reduce the potential intake of radioiodine to the control room. The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulates.
The laboratory carbon sample test results should indicate a radioactive methyl iodide removal efficiency of at least 90 percent for expected accident conditions.
Ifthe efficiencies of the HEPA filter and charcoal adsorbers are as specified, adequate radiation protection will be provided such that resulting doses will be less than the alfowable levels stated in Criterion 19 of the General Design Criteria for Nuclear Power Plants, Appendix A to 10CFR Part 50.
Operation of the fans significantly different from the design flow willchange the removal efficiency of the HEPA filters and charcoal adsorbers.
~
'f the system is found to be inoperable, there is no immediate threat to the contro'I room and reactor'operation or refueling opeiation may continue for a limited period of time while repairs are being made.
If the makeup system cannot be repaired within seven days, the reactor is shutdown and brought to cold shutdown within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> or refueling operations are terminated.
Pressure drop across the'combined HEPA filters and charcoal adsorbers of less than six inches of water at the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop shovld be determined at least once per operating cycle to show system performance capability.
l The Freqvency of tests and sample analysis are necessary to show the HEPA filters and charcoal adsorbers can perform as evaluated.
The charcoal adsoroer efficiency test procedures should allow for the removal of one adsorber tray, emptying of one bed from the tray, mixing the adsorbent thorough'Iy and obtaining at least two samples'.
Each sample should be at least two inches in diameter and a length eqval to the thickness of the bed.
Iftest resvlts are vnacceptable, all adsorbent in the system shall be replaced with an adsorbent qvalified according to Table 5-1 of ANSI 509-1980.
The replacement charcoal for the adsorber tray removed:for the test should meet the same adsorbent quality. Any HEPA filters found defective shall be repfaced with filters qualified pursuant to ANSI 509-1980.
AMENDMENTNO. J$ P 161 180
TABLE 3.6.2l CONTROL ROOIVI AIR TREATMENTSYSTEM INITIATION Limitin Condition for 0 eration Parameter Minimum No.
of Tripped or 0 erable Tti S stems Ninimum No. of Operable Instrument Channels per Operable Tri S sem
~Se Potnt Reactor Node Switch Position in Which Function Must Be 0 erable c
O CO D.
c p8 3
U)
IK (1)
Low-Low Reactor Water Level a5 inches (Indicator Scale)
~ X X
(2)
High Steam Flow Main-Steam Line a105 psid
.X X
(3)
High Temperature Main-Steam Line Tunnel
<200'F X
X (4)
High Drywell Pressure a3.5 psig (a)
(a)
AMENDMENTNO. Ok 161 246
TABLE4.6.2I CONTROL ROOIVI AIR TREATMENTSYSTEM INITIATION Surveillance Re uirement Parameter (1)
Low-Low Reactor Water Level (2)
High Steam Flow Main-Steam Line Sensor Check Once/day Once/day instrument Channel Tes Once per quarter(")
Once per quarter(")
instrument Channel
~Caiibr8 ion Once per quarter(
Once per quarter(
(3)
High Temperature Main-Steam Line Tunnel (4)
High Drywall Pressure Once/day Once each operating cycle not to exceed 24 months Once per quarter(")
Once each operating cycle not to exceed 24 months Once per quarter(")
AMENDMENTNO. 76 247
( ~
NOTES FOR TABLES 3.6.2l AND4.6.2l la)
May be bypassed when necessary for containment inerting.
(b)
Only the trip circuit will be calibrated and tested at the frequencies specified; the primary sensor will be calibrated and tested once
'per op~rating cycle.
AMENDMENTNO. )g) 247a