ML17256A916
| ML17256A916 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/23/1982 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17256A917 | List: |
| References | |
| NUDOCS 8205120352 | |
| Download: ML17256A916 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 ROCHESTER GAS AND ELECTRIC CORPORATION DOCKET NO. 50-244 R.
E.
GI'NNA NUCLEAR'POWER'PLANT AMENDMENT TO PROVISIONAL OPERATING LICENSE Amendment No.
49 License No. DPR-18 1.
,The Nuclear Regulatory Corrmission (the COIIission) has found that:
A.
The application for amendment by Rochester Gas and 'Electric-Corporatj'ori-'(the".licensee)'o'tar'ize'd April 23
- 1982, 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; 8.
The facility will operate in conformity with the application, the provisins of the Act, and the rules 'and regulations of the Commission; I
C.
There is reasonable assura'nce (i) that the activities authorized'y 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 COIITIIission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and securi ty or to the.health and safety of the public; and 0
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.
.'8205l20352 820423
'"">>,PDR, 'ADOCK 05000244 P,
2 2 ~
Accordingly the license is amended by changes to the Technial
. Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Provisional Operating License No. DPR-18 is hereby amended to read as follows:
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 49 are hereby incorporated in the license.
The licensee shall operate the facility.in accordance with the Technical
'pecifications.
3;
.This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specif>cations Date of Issuance; April 23, 1982 Dennis M. Crutchfield, Ch ef Operating Reactors Branch 85 Division of Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
49 PROYISIONAL OPERATING LICENSE NO.
DPR-18 DOCKET NO. 50-244 Revise Appendix A Technical Specifications by removing. the pages identified below and inserting the enclosed pages.
The revised pages contain the captioned amendment number.and marginal lines which indicate the area of changes.
PAGES 3.14-7 3.'14-8
TABLE 3. 14-1 FIRE DETECTION INSTRUMENTS.
INSTRUMENT LOCATION MINIMUM INSTRUMENTS OPERABLE ***
- 1. Containment "A" Post-Accident Charcoal Bank "B" Post-Accident Charcoal Bank "A" Aux. Filter Charcoal Bank "B" Aux. Filter Charcoal Bank'able Trays Basement. Elev.
Cable Trays Zntermed: Elev.
Cable Trays Operating Floor "A" RCP Intermediate Floor "B" RCP Intermediate Floor Area Detection Operating Floor
- 2. Control Room Area and Cabinet Control Room/Turb. Bldg. Hall
- 3. Relay Room
- 4. Computer Room Under Floor Ceiling
- 5. Battery. Roons "A" Battery Room
'B" Battery Roon
- 6. Control Building Air Handling Room
- 7. Diesel Generator "A" Generator Room "A" Generator Vault "B" Generator Room "B" Generator Vault
- 8. Zntermediate Building Motor Driven Aux. Fd.
Pump Area Turb. Driven Aux. Fd.
Pump 5 Res Cable Trays Basement North "A" Purge Filter Elev. 315'-4" "B" Purge Fi1ter Elev.
3 15 '-4 ".
HEAT 3*
3*
1**
2**
1l*
1**
1**
N/A N/A 4
N/A N/A N/A N/A N/A 2
N/A 2
N/A N/A 1
N/A N/A N/A SiXOKE N/A
,N/A N/A N/A N/A N/A N/A N/A N/A
~..--7 19 N/A 16
~ 3 3
N/A 1'/A 1
9 N/A 14 1
1 3.14-7 Amendment No, H, jA,~
49
INSTRUMENT LOCATION MINIMUM INSTRUMEiNTS OPERABLE HEAT S l1OKE
- 9. Screen House Area Detection Serv. Water'ump and Bus Area Cable Trays Basement
- 10. Standby Auxiliary Feedvater Bldg.
- 11. Cable Tunnel 12.'uxiliary 'uilding Gene al Area Area Basement Fast Area Basement West and RHR Pit Cable Trays/SI Pumps Basement Penetration Area Cable Trays Mezz.
Cable Trays, Elec.
Cab.
Mezz.
Center Cable Trays Mezz. East Area Operating Floor N/A iN/A N/A 10 N/A N/A N/A N/A N/A N/A" N/A N/A 11 4
8 5
9 5
2"
4 4.
13
- Resistance Temperature Detectors (RTD) Only
- Line Type Detectors
- ~ The fire detect'ion instruments located within the containment are not required to be operable during the pei formance of Type A containment leakage rate tests.
Amendment No. 3K'>M> 49 3.14-8
'~p,tE REC'y Cy
~v ClO rp UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EYALUATION-BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.
49 TO PROVISIONAL OPERATING LICENSE NO.
DPR-18 ROCHESTER GAS AND ELECTRIC CORPORATION R.
E.
GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244 1. 0
. INTRODUCTION By application notarized April -23, 1982, Rochester Gas and Electric Corporation (RG&E) requested changes to the Technical'pecifications appended to Pgovisional Operating License No.
DPR-18 for. the R. E.-
Ginna Nuclear Power Plant.
These changes'ould revise the specifi-,
cations dealing with the fire detection system.
2.0 BACKGROUND
The fire detectors-at Ginna have been demonstrated to be sensitive to dust and particles which are stirred up during maintenance activities:-
Pressurization and depressurization of the containment during integrated leak rate testing may cause dust and particles to give spurious fire alarms from the containment.
To avoid such spurious alarms RGSE has r equested authorization to make the containment fire detection instruments inoperable during the containment leak rate test.
3.0 EVALUATION During integrated leak rate tests, no maintenance activities will be taking place.
RG8E conducts a.final inspection of the containment after maintenance activities have ceased, prior to commencing the integrated leak rate tests.-
Therefore the risk of fire caused by welding, buring, grinding or other personnel activities will not exist.
'L During the integrated leak rate test the plant is at cold shutdown with
.the reactor coolant pumps secured.
Therefore, the risk of fire caused by oil leaks onto hot equipment is significantly reduced from the risk at power operation.,
The only significa'nt fire hazards in containment during the test are the operating containment fan coolers.
The fan cooler bearing vibration and
ir-plenum temperature instruments in the control room provide an indication of fan cooler malfunction.
In addition, monitoring the containment temperature during the test will provide an indication of fire.
e
4.0
SUMMARY
Based on our evaluation of the information provided by the.licensee,.
we find that mak'ing the'fire detection system inoperable during the integrated leak rate tests will not result in 'a signifi.cant increase in the risk of fire and is consistent with current licerising practices.
Therefore, we conclude that: the. proposed change -to -the.Technical Specifications is acceptable.
ENVIRONMENTAL CONSIDERATION We have determined that the proposed amendment does not authorize a
change in effluent types, increase in total amounts of effluents, or an increase in power level, and will not resul't in any'ignificant environmental. impact.. Having made this determination, we have concluded-that the amendment involves an action which is insignificant from the standpoint of environmental, impact; and, pursuant to 10 CFR 51.5(d)(4),
that an environmental'mpact statement or negative declaration and environmental impactappraisal need not be prepared in connection with the issuance of this amendment.
6.0 CONCLUSION
'e also conclude, based on the considerations discussed above, that:
(1) because the amendment does not involve a significant increase in the
. probability or consequences of accidents previously considered and does not involve a significant decrease in a safety margin; the amendment does not involve a significant hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not be'ndangered by operation in the proposed manner; and (3) such activities will be conducted in compliance with the Commission's regulations and the.
issuance of this amendment willnot be inimical to the common defense and security or the health and safety of the public.
.0 ACKNOWLEDGMENTS The following NRC personnel has contributed to this evaluation:
JLyons Date:
April 23, 1982