ML20002A494
| ML20002A494 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 08/18/1977 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20002A492 | List: |
| References | |
| NUDOCS 8011170362 | |
| Download: ML20002A494 (8) | |
Text
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L UNITED STATES
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j NUCLEAR REGULATORY COMMISSION g
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YANKEE ATOMIC ELECTRIC COMPANY
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DOCKET NO. 50-29 YANKEE NUCLEAR POWER STATION (YANKEE-ROWE)
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AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 41 License No. DPR-3
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The Nuclear Regulatory Comission (the Comission) has found that:
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A.
The application for amendment by Yankee Atomic Electric Company (the licensee) dated July 5,1977, 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 a(.tivities 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 Comission'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.
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license M.M amendment, and paragraph 2.C. (2) of Facility Operating License lll.~?1~
No. DPR-3 is hereby amended to read as follows:-
"(2) Technical Specifications c=er The Technical Specifications contained in Appendix A, as revised through Amendment No. 41, are hereby incorporated in the license.
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The licensee shall operate the facility in accordance with the Technical Specifications."
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This license amendment is effective as of the date of its issuance, d
FOR THE NUCLEAR REGULATORY COMMISSION
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p A. Schwencer, Chief Ih j
Operating Reactore Branch #1 Divisita of Operating Reactors j
Attachment:
Changes to the Technical Specifications Date of Issuance: August 18, 1977
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.:b h ATTACHMENT TO LICENSE AMENLw.ENT NO. 41 g
FACILITY LICENSE NO. DPR-3 DOCKET NO. 50-29
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Revise Appendix A as follows:
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Remove the following pages and insert newly renuntered pages:
3/47-27/3/47-28 3/4 7-29 /
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B 3/4 7-5 / B 3/4 7-6
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Marginal lines indicate revised area.- Overleaf pages are provided
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for convenience.
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PLANT SYSTEMS
_3/4.7.9 SHOCK SUPPRESSORS (SNL'BBERS)
LIMITINC CONDITION FOR OPERATION hr 3.7.9.1 All shock suppressors (snubbers) listed in Table 3.7.4 shall be OP ER/ ' LE.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
dith one or more snubbers inoperable, restore the inoperable snubber (s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within
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the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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SURVEILLANCE REQUIREMENTS i
4. 7. 9.1.1 Each snubber shall. be det^ ermined OPERABLE in accordance with the inspection schedule of Table 4.7-5 by a visual inspection of the snubber.
/isual inspections of the snubbers shall include, but are not necessarily limited to, inspection of the snubber orientation and linkage tonnectiohs to the piping and anchors.
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l 1ANKEE-ROWE 3/4 7-27 Amendment No. 41
E TABLE 3.7-4 g
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SAFETY RELATED SNUBBERS
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SNUBBER SYSTEM SNUBBER INSTALLED ACCESSIBLE (A) or HIGH RADIATION ESPECIALLY DIFFICULT NO.
ON AND LOCATION INACCESSIBLE (I)
ZONE DURING SilVTDOWN**
TO REMOVE HSS 19A Pressurizer relief valve.
A No No HSS 198 pressurizer cubicle A
No No HSS 20A A
No No HSS 20B A
No Ne
- .c HSS 21 Pressurizer relief valve A
No No n
w HSS 22 discharge line.. pressurizer A
No No 2
HSS 23 cubicle
,A Ne No HSS 24 y
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- Snubbers may be added to safety related systems without prior license amendment to Table 3.7-4 pruvided that Lg a proposed revisibn to Table 3.7-4 is included with the r; ext license amendment request.
- Modifications to this table due to changes in high radiation areas shall be submitted with the next license o
amendment request.
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TABLE 4.7-5 ai SNUBBER INSPECTION SCHEDULE NUMBER OF SNUBBERS FOUND INOPERABLE NEXT REQUIRED DURING INSPECTION OR DURING INSPECTION INTERVAL *
. INSPECTION INTERVAL **
-0 18 months + 25%
1 12 months T 25%
2 6 months T 25%
3 or 4 1
124 days 125%
5, 6, or 7 62 days
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>8 31 days
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- p. _;,' '* Snubbers are categorized into two groups, " accessible" and " inaccessible" in Table 3.7-4.
This categorizati is based upon the snubber's acces These two groups may be g'
inspected independently according;siblity for inspection during reactor operation.
.to the above schedule.
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- The requ. ired inhpection interval shall not be lengthened more than one step at a time.
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G; PLANT SYSTEMS BASES 3/4.7.7 WASTE EFFLUENTS 3/4.7.7.1 RADIOACTIVE SOLID WASTES Radioactive solid wastes are pennitted to be disposed of only at
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licensed offsite disposal areas.
3/4.7.7.2 RADI0 ACTIVE LIQUID WASTE Releases of radioactive materials in effluents will be kept at small fractions of the limits specified in 10 CFR '20 except under
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unusual operating conditions which may temporarily result in releases higher than such small fractions, but still within the limits specified in 10 CFR 20. The Licensee will exert his best efforts to keep levels
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of radioactive materials in effluents as low as reasonably achievable.
Radioactive liquid wastes are diluted in the plant discharge system prior to release up to a maximum dilution multiple of 7.24 x 10"6 x ?;
minutes per gallon times the radioactive release rate in gallons per minute.
Radioactive liquid wastes are collected in tanks until 'a quantity sufficient for processing has accumulated. The processed liquids are directed to separate tanks where they are sampled and analyzed for radioactivity content prior to release. Discharges from the waste disposal system are made through a recorder controller which provides a m asure and control of the volume released. The volume released and the radioactivity analyses provides the basis for record keeping.
3/4.7.7.3 RADIOACTIVE GASEOUS WASTE Releases of radioactive materials in airborne waste will not exceed the concentration limits specified. The limit for iodine isotopes and particulate isotopes with half lives greater than 8 days was further reduced by a factor of 700 to account for reconcentration in the food chain.
Gaseous wastes flow from the low pressure surge tank through the gas compressor (s) which discharge to the waste gas surge drum. The drum is pressurized and then allowed to decay before discharge to the primary
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vent stack. The gaseous discharge is continuously monitorM in the primary vent stack. Coincident with the loss of exhaut fan suction, the vent line flow control valve will close, terminating the release.
1 YANKEE-ROWE B 3/4 7-5
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I PLANT SYSTEMS 3ASES 3/4.7.8 ENVIRONMENTAL MONITORING The operational environmental monitoring program is designed to demonstrate the adequacy of safeguards inherent in plant design and the effectiveress of established control measures for the releases of radio-active materials.
Special attention is given to gamma spectrum analysis of samples in order to identify and reference nuclides present in plant effluents.
Spectra of environmental samples are observed for the ingrowth of plant produced radionuclides.
3/4.7.9 SHOCK SUPPRE5 SORS (SNUBBERS)
Snubbers are designed to prevent unrestrained pipe motion under dynamic loads as might occur during a severe transient, while allowing nomal themal motion during startup and shutdown.
The consequence of an inoperable snubber is an increase in the probability of structural damage to piping as a result of an event initiating dynamic loads.
It is therefore required that all snubbers required to protect the main coolant system or any other safety system or component be OPERABLE during reactor operation.
Because the snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repairs or replace ment.
In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach COLD SHUTDOWN condition will pemit an orderly shutdown con-sistent with standard operating procedures. Since plant startup should i not comence with knowingly defective safety related equipment, startup with inoperable snubbers is prohibitted.
All safety related snubbers are visually inspected for overall l
integrity and OPERABILITY. The inspection will include verification of proper orientation and proper attachment of snubber to piping and structures. l The inspection frequency is based upon maintaining a constant level of snubber protection. Thus the required inspection interval varies inversely with the observed snubber failures. The number of inoperable snubbers found during a required inspection determines the time interval for the next required inspection.
Inspections perfomed before that interval has elapsed may be used as a new reference point to determine the next inspection.
However, the results of such early inspection perfomed before the original required time interval has elapsed (nomal time less 25%) may not be used to lengthen the required inspection interval.
Any inspection whose results require a shorter inspection interval will over ride the previous schedule.
YANKEE-ROWE B 3/4 7-6 Amendment No. 41 L