ML17244A475
| ML17244A475 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 04/18/1979 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | White L ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| TASK-03-04.B, TASK-3-4.B, TASK-RR NUDOCS 7905020351 | |
| Download: ML17244A475 (14) | |
Text
4.
Docket Ho. 50-244 APP'. 8 1979 Hr. Leon D. White, Jr.
'ice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649
Dear Hr. Hhite:
- ME:
TOPIC VIII-3.A STATION BATTERY TEST DISTRIBUTION NRC PDR Local PDR ORB 42 Reading NRR Reading VStel,lo DEisenhut BGrimes RVollmer TJcarter WRussell OELD OISE (3)
DLziemann iJShea HSmith DKDavis JRBuchanan REgUIREHENT TERA ACRS (16)
Di'll. Ll(>hr,lg Enclosed is a copy of our draft evaluation of Systematic Evaluation Program Topic VIII-3.A.
You are requested to examine the facts upon which the staff has based its evaluation and respond
- either, by con-
. firming that the facts are correct, or by identifying any error s. If in error, please supply corrected information for the docket.
He encourage you to supply for th'e docket any other material related to
. this topic that mlight-affect the staff's evaluation.
Your response within 30 days o'f the date you receive this letter is requested.
If no response is received within that time, we will assume that you have no comments or corrections.
Enclosure:
Topic VIII-3.A cc w/enclosure:
See next page Si ncerely, l
GrlgkneI signed by 9enn1s 1.. lit."mann Dennis L. Ziemann, Chief Operating Reactors Branch t2.
Division of Operating Reactors 7 fo~o>ass I
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NRC PORM'31S (9761 NRCM 0240 44 4 OOVCNNMONT PNINTINO OrrlCCClt)0 TO ~
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Mr. Leon D. White, Jr.
cc w/enclosure:
Lex K. Larson, Esquire
- LeBoeuf, Lamb, Leiby 5 MacRae 1757 N Street, N.
W.
Washington, D..C.
20036 Mr. Michael Slade 1250 Crown Point Drive
- Webster, New York 14580 Rochester Committee for Scientific Information Robert E. Lee, Ph.D.
P. 0.
Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 KMC, Inc.
ATTN:
Jack McEwen 1747 Pennsylvania
- Avenue, N.
W.
Suite 1050 Washington, D.
C.
20006
SYSTEMATIC EVALUATION PROGRAM BATTERY CAPACITY TESTS R.
E.
GINNA DOCKET NO:
50-244 Topic VIII-3,A Station Battery Test Requirements The objective of this review is to assure that the onsite Class IE battery capacity to supply all safety related D-C loads is verified by periodic testing.
The testing should be in accordance with IEEE Standard 450-1975, IEEE Standard 308-1974, BTP EICSB 6 and the "Standard Technical Specifications for Westinghouse Pressurized Water Reactors" (NUREG-0452).
The required tests are as follows:
l.
At least once per 18 months, during shutdown, a batter service test should be performed to verify that the battery capacity is adequate to supply and maintain in operable status all of the actual emergency loads for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
2.
At least once per 60 months, during shutdown, a batter dischar e test should be performed to verify that the battery capacity is at least 80Ã of the manufacturer's rating.
The R.
E. Ginna Nuclear Station battery surveillance requirements are included in Section 4.6.3 of the station technical specifications.
These specifications require a battery load test at each refueling outage, but do not require a battery discharge test.
However, this battery test is a
more stringent version of a battery service test in that at each refueling outage a test of the batteries for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> at a load which simulates the design basis load is performed.
Accordingly, the R.
E.
Gi.nna Nuclear Station deviates from current licensing requirements in that its technical specifications do not require a battery discharge test.
I This deviation will be evaluated in the context of the'Design Basts Events (DBE) that rely upon these components for mitigating the conse-quences of the DBE. If this deviation is determined to be unacceptable, the Technical Specifications will be appropriately revised.
APP. ] 8 )97/
References 1.
"Ginna Technical Specifications,"
Rochester Gas 8 Electric Company.
2.
Standard Review Plan, Appendix 7-A, BTP EICSB 6, "Capacity Test Requirements of Station Batteries - Technical Specifications,"
U.S. Nuclear Regulatory Commission.
3.
"IEEE Standard Criteria for Class IE Power Systems for Nuclear Power Generating Stations," Std, No, 308-1974, The Institute of'lectrical and Electronics Engineers, Inc.
4.
"IEEE Recommended Practice for Maintenance, Testing and Replacement of Large Lead Storage Batteries for Std, No, 450-1975, The Institute of Electrical and Electronics Engineers,
- Inc, 5,
"Standard Technical Specifications for Westinghouse Pressurized Water Reactors,"
NUREG-0452, U,S. Nuclear Regulatory Commission,
r BUTION cket NRC PDR
, Local PDR ORB ¹2 Reading NRR Reading
- VStello, APR 18 ]979 DEisenhut BGrimes tir. Leon D. White, Jr.
RVollmer Vice President Electric and Steam Production Rochester Gas and Electric Corporation 89 East Avenue Rochester, New York 14649 JJShea
Dear Nr.,
Uhite:
- HSmith, RE:
TOPIC III-4.8 TURBINE, t1ISSLES Enclosed is a copy of our draft evaluation of Systematic Evaluation Program Topic III-4.8.
You are requested to examine the facts upon which the staff has. based its evaluation and respond either by con-firming, that the facts are correct, or by identifying any errors.
If in error,'lease supplycorrected information for the docket.
He encourage you to supply for the docket any other material related to this topic that might affect the staff's evaluation.
Docket No. 50-244 Your response within 30 days of the date you receive this letter is requested.
If no response is received within that time, we will assume that you have no comments or corrections.
Sincerely, Or~4nal sI~c4 Py
Q.cggfg I. 2iCmcng Dennis L. Ziemann, Chief Operating Reactors "Branch ¹2 Division of Operating.Reactors
Enclosure:
Topic III-4.8 cc w/enclosure:
See next page ACRS(16)
HFontecilla I'BOSORQ 55/
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Mr. Leon D. White, J r.
<~~ iS
)gag cc w/encl osure:
Lex K. Larson, Esquire
- LeBoeuf, Lamb, Leiby 8 MacRae 1757 N Street, N.
W.
Washington, D.
C.
20036 Mr. Michael Slade 1250 Crown Point Drive
- Webster, New York 1'4580 Rochester Committee for Scientific Information Robert E. Lee, Ph.D.
P. 0.
Box 5236 River Campus Station Rochester, New York 14627 Jeffrey Cohen New York State Energy Office Swan Street Building Core 1, Second Floor Empire State Plaza
- Albany, New York 12223 Director, Technical Development Programs State of New York Energy Office Agency Building 2 Empire State Plaza
- Albany, New York 12223 Rochester Public Library 115 South Avenue Rochester, New York 14604 KMC, Inc.
ATTN:
Jack McEwen
'747 Pennsylvania
- Avenue, N.
W.
Suite 1050 Washington, D.
C.
20006
GINNA TOPIC III-4. B TURBINE MISSILES The safety objective of this review is to assure that all structures, systems and components important to safety are adequately protected against potential turbine missiles.
The Ginna Nuclear Power Plant has a non-peninsular orientation with respect to the containment and most safety-related systems.
- However, all the systems needed for the safe-shutdown of the plant (see Topic YII-3) are either inside or shadowed by the concrete containment building, located below the turbine pedestal, or are out of the low trajectory missiles (LTH) strike zones.
In addition, many of the systems have physically separated redundant components.
On this
- basis, the probability of an LTM striking any of the safety-related systems is considered to be acceptably low.
The probability of high trajectory missile's (HTM's) striking the safety-related systems is obtained by multiplying the conservatively estimated turbine failure and missile ejection rate, 10 per year,'y the strike probability density per turbine failure, 10 per ft,
&7 2
and by the horizontal area occupied by the systems.
A list of the safety-related systems located outside of the containment building and their estimated impact areas is given in Table l.
A conservative estimate of the area occupied by these systems is 12000ft The
-4 turbine failure rate of 10 is also conservative because of the use of a historically observed turbine ai lure data set.
Some of the April 18, 1979
reported failures involved old turbine designs and fabrication techniques which have been improved in currently produced turbines (a new turbine rotor was installed at the Ginna plant during the 1979 refueling outage).
The resulting PHTM is found to be on the order of 10 per year, and the total strike probability from low and high trajectory missiles is conservatively estimated to be less than 10 per year.
Therefore, we conclude that the overall probability of tunbine missiles damaging the Ginna Nuclear Power Plant and leading to consequences in excess of the 10 CFR Part 100 exposure guidelines is acceptably low as specified in the S.R.P. 3.5.1.3, and the S.R.P. 2.2.3.
On the basis of these results, we consider the operation of the Ginna Nuclear Power Plant safe with regard to turbine missiles, and the risk presented by this postulated event similar to that of plants licensed under current criteria.
This completes the evaluation for this SEP topic.
Since the plant conforms to current licensing
- criteria, no additional review is required.
References:
1.
- Bush, S. H., "Probability of Damage to Nuclear Components",
Nuclear ~Safet, Vol. 14, No. 3, Nay - June, 1973.
2.
Regulatory Guide 1.115, "Protection Against the Low-Trajectory Turbine Missiles", Revision 1, July 1977.
3.
Visit to Ginna Nuclear Power Plant, Memo from H. Fontecilla to D. Eisenhut, November 2,
- 1978, Docket No. 50-244..
TABLE 1
TURBINE MISSILE PROTECTION OF SAFETY-RELATED SYSTEMS/COMPONENTS OUTS IOE CONTAINMENT
~Ss tern Component Auxiliary Feedwater Pumps (2 Motor and 1
Turbine.Driven)
. Boric Acid Tanks and Boric Acid Transfer Pumps Component Cooling Mater Heat Exchangers Component Cooling Mater Charging Pumps Refueling Mater Storage Tank Residual Heat Removal Charging Pumps Bus 14 Bus 16 Electrical Su 1
Motor Driven Pumps on Bus 14/Bus 16 Transfer Pumps on Bus 14/Bus 16 Bus 14/Bus 16 Bus 14/Bus 16 Diesel Generator Diesel Generator Location Intermediate Building Elevation 253'-6" Auxiliary Building Elevation 271'uxiliary Building Elevation 271'uxiliary Building Elevation 271'uxiliary Building Elevation 235'-8"-326'uxiliary Bldg Elevation 219'uxiliaryBldg Elevation 271'uxiliaryBldg Elevation 235'8" pst. Str)ke Area ft 300 400 300 50 500 160 l60 Strike Probabilit 3xl0-6 4x10 3xlo-'x10 5x10 5 5x10 6 1.6xl0 1.6xlO
~,
S stem Co onent Service Water Pumps Electrical Su 1
Bus 17/Bus 18 Location Screenwell House Elevation 253'6" Est. Strfke Area ft 50 Strike Probabilit 5x10 Ous 17 Ous 18 Condensate Storage Tank Diesel Generators Control Room Relay Room Battery Room Diesel Generator Diesel Generator Diesel Generator Screenwell House Elevation 253'6" Screenwell House Elevation 253'6" Service Bldg Elevation 253'6" Diesel Generator Bldg Elevation 253'-6" Control Room Bldg Elevation 289'-6" Control Room Bldg.
Elevation 270'-6" Control Room Bldg.
Elevation 253'0" 70 70 100 800 1800 1800 1800 7xl0 7xl0 Bxl0 5 1.8xl0 ~
1.8x10"~
1.8x10
~
3 S stem Co onent Hain Steam Line From Steam Generators A and B Upstream of Hain Steam Line Isolation Valves Hain Steam Line Isolation Valves A and B
Hain Steam Safety Relief Valves Spent Fuel Pool Charging pumps Safety Injection pumps Electrical Su 1
Bus 14/16 Bus 14/16 Location Intermediate Bldg.
Elevation 278'4" Intermediate Bldg.
Elevation 278'4" Intermediate Bldg.
Elevation 278'4" Auxiliary Bldg.
Elevation 278'-4" Auxiliary Bldg.
Elevation 235'8" Auxiliary Bldg.
Elevation 235'8."
Est. Strfke Area ft 120 50 2922 50 50 Strike Probabilit 1.2x.l0 5x10 5x10 2.9x10 5xl0
- ~
I Some of the systems may be located where some degree of protection is provided by floor, walls, or other equi'pment.'his has been neglected in these estimates.
- Strike probability density per turbine failure
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