ML17058A555
| ML17058A555 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 06/13/1986 |
| From: | Mangan C NIAGARA MOHAWK POWER CORP. |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| References | |
| (NMP2L-0750), (NMP2L-750), 1694G, NUDOCS 8606180367 | |
| Download: ML17058A555 (12) | |
Text
REGULATORY INFORl'lATION DISTRIBUTION SYSTEI'l (R IDS)
ACCESSION NBR: 8606180367 DOC. DATE: 86/06/13 NOTARIZED: YES FACIL: 50-410 Nine Nile Point Nuclear Station>
Unit 2.
Niagara Noha AUTH. NANE 'UTHOR AFFILIATION NANQAN> C. V.
Niagara Nohaml Paver Corp.
RECIP. NAi'IE RECIPIENT AFFILIATION ADENSAN> E. Q.
BNR Prospect Directorate 3
SUBJECT:
Identifies preoperational tests util plans to defer beyond fuel load> tests requiring 5 not requiring exemptions from 10CFR50. 12(a). Affidavit
~4 supporting documentation> encl.
DIBTRIDUTION CODE:
BCOID COPIEB RECEIVED: LTR
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ENCL J SIZE:~
TITLE: Licensing Submittal:
PSAR/FSAR Amdts 8c Related Correspondence NOTES:
DOCH,ET 05000410 RECIPIENT ID CODE/NANE BNR EB BNR FOB BNR PD3 PD BNR PSB INTERNAL: ACRS 41 ELD/HDS3 IE/DEPER/EPB 36 NRR BNR ADTS FA 04 RN/DDAl'll/NIB EXTERNAL: BNL(Al'lDTS ONLY)
LPDR 03 NSIC 05 COPIES LTTR ENCL 1
1 1
1 6
6 0
1 0
1 1
1 1
0 RECIPIENT ID CODE/NAl'lE BNR EICSB BNR PD3 L*
HAUQHEY l'l 01 BWR RSB ADN/LFNB IE FILE IE/DGAVT/GAB 21 NRR PNR-B ADTS NRR/DHFT/NTB RQNi DNB/DSS (ANDTS)
NRC PDR 02 PNL QRUEL> R COPIES LTTR ENCL 1
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1 0
1 3
3 TOTAL NUl'lBER OF COPIES REGUIRED:
LTTR 36 ENCL 31
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NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 June 13, 1986 (NMP2L 0750)
Ms. Elinor G. Adensam, Director BWR Project Directorate No.
3 U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Washington,'C 20555
Dear Ms. Adensam:
Re: Nine Mile Point Unit 2 Docket No. 50-410 The Niagara Mohawk letter from C. V. Mangan to E.
G. Adensam dated April 7, 1986 identified ten systems whose preoperational tests were planned to be deferred until after fuel load and forwarded pertinent information relative to each system.
A subsequent letter from C.
V. Mangan to E.
G.
Adensam dated May 7, 1986 requested schedular relief under 10 CFR 50.57(b) and also requested exemption from the requirements of 10 CFR Section 50.12(a) for portions of the Automatic Depressurization
- System, Containment Leakage Monitoring System, Offgas System and Containment Monitoring System.
The purpose of this letter is to explicitly identify those preoperational tests which we are planning to defer beyond fuel load, those which require exemptions, and those which do not require exemption from the requirements of 10 CFR 50.12(a).
These
- systems, as discussed in previous correspondence and meetings on this subject, are listed below.
Responses to Nuclear Regulatory Commission staff requests from a May 12, 1986 Status Review meeting and Nuclear Regulatory Commission Project Manager's site meeting of June 3, 1986 have been included in this correspondence.
Test/S stem No.
Final Safety Analysis Report Table 14.2-32/System 8
Final Safety Analysis Report Table 14.2-42/System 17 Final Safety Analysis Report Table 14.2-44/System 2
SbObiS03b7 SbOb13
- PDDR, ADOCH, 05000410 1'-
- PDRQ
~Ss tern Feedwater Heaters and Extraction Steam System Post Accident Sampling System Electrical Hydraulic Control System Exemption
~Re uired No No No Boo I
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.Ms. Elinor G. Adensam Page 2
Test/System No.
Final Safety Analysis Report Table 14.2-59/System 41
~sseem Solid Radwaste Exemption
~Re unbred No Final Safety Analysis Report Table 14.2-60/System 42 Final Safety Analysis Report Table 14.2-108/System 82 Final Safety Analysis Report Table 14.2-112/System 85 Final Safety Analysis Report Table 14.2-114/System 88 Final Safety Analysis Report Table 14.2-78/System 62 Offgas System Containment Atmospheric Monitoring System Reactor Coolant and ECCS Leak Detection System Containment Inerting System DBA Recombiner System Yes Yes Yes No Yes Niagara Mohawk withdraws the exemption requests for the Automatic Depressurization System and Containment Leakage Monitoring System.
The requested exemptions for the Offgas System, the Containment Monitoring System, and the Reactor Coolant and ECCS Leak Detection System were provided in our May 7, 1986 letter.
- Further, an exemption request to defer the Design Basis Accident Recombiner Testing will be provided under separate cover.
Revised information is provided in Attachment 1 for Electrical Hydraulic Control System, and new information is provided for Post Accident Sampling System.
Niagara Mohawk is ready to meet with the cognizant Nuclear Regulatory Commission personnel to review this matter at your convenience.
Very truly yours, C.
V. Mang Senior Vice President BS:ja 1616G xc: R. A. Gramm, NRC Resident Inspector Project File (2)
l 1
a
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Niagara Mohawk Power Corporation
)
(Nine Mile Point Unit 2)
Docket No. 50-410 AFFIDAVIT C.
V.
Man an
, being duly sworn, states that he is Senior Vice President of Niagara Mohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belief.
Subscribed and swor to bef re me, a Notary Public in York and County of
, this ~3>>
day of d for the State of New 1986.
N tar Public in and for
- County, New York My Commission expires:
JANIS M. MACRo Notary Public tn the Stato of frow Yortr n Onondara County ffo. 4784585 g~ Qotnnrteslon Prrplres "arch our
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Attachment 1
Test No."
FSAR Section 14.2-42 Preop Test 34 System Post-Accident Sample System Schedul e" for Compl etion Six months after fuel load but prior to oper-ation above 5X of rated thermal power System Oescription As described in FSAR Sections 1.10 and 9.3.2, the PASS is designed to obtain representative liquid and gas samples from within the primary containment for radiological analysis in association with the possible consequences of a loss of coolant accident (LOCA).
The system consists of:
1) a piping station located in the reactor building; 2 ) a sampling station located in the radwaste sample room; 3) two control panels situated approximately 10 ft. from the sample station in the sample room; 4) assorted transport equipment; 5) a ventilation system; and 6) assorted interconnecting tubing.
Justification for Not Completin the Test Ouring fuel loading and prior to low power testing no radioactive gaseous effluents can be gener ated.
The operability of the Post-Accident Sample System ensures the system will be available for post-LOCA conditions.
The Post-Accident Sample System can only perform a function during a post-LOCA with degraded core conditions.
This condition is not physically possible until after initiation of operation above low power (5X of rated thermal power).
Basis for Concludin Acceptability Prior to initial power operation, the Post-Accident Sample System can perform no safety function, is not needed, and is not required.
As the test will be per formed prior to oper ation above low power (5X, of rated thermal power), the test schedule is acceptable.
Technical Specification Requirements and Effects There are no technical specifications applicable to this system.
Exemption Requests No exemption requests are required at this time, since there are no deviations from regulatory requirements or plant Technical Specifications.
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Attachment 1
(con'est No; FSAR Tabl e 14.2-44 Preop Test 23 System Electrical Hydraulic Control System Schedule for Completion Prior to opening of the main steam isolation val ves
System Description
As described in FSAR Sections 1.2.5.3, 7.7.1.5 and 10.2.2, the Electrical Hydraulic Control System is used to maintain and control normal power gener ation of the turbine generating system and to provide protection for the Nine Mile Point Unit 2 turbine during transient conditions.
The pressur e
regulator maintains control of the turbine, control of the turbine bypass valves to allow proper generator and reactor r esponse to system load-demand
- changes, while maintaining the nuclear system pressur e essentially constant.
The turbine generator speed-load controls can initiate rapid closur e of the turbine control valves (rapid opening of turbine bypass valves) to prevent turbine overspeed on loss of generator electric load.
Justification for Not Completin
=the. Test This system is nonsafety related and not required for safe operation of the plant - only for power generation.
Basis for Concludin Acceptability Technical Specifications require that the Electrical Hydraulic Control
- Systems, which control the bypass valves, turbine stop valves and control
- valves, are tested in accordance with Section 3/4.3.8.
This equipment is required for operational conditions 1 and 2.
The turbine overspeed protection specification is provided to ensure that turbine overspeed protection system instrumentation and turbine speed control valves are operable and will protect the turbine from excessive overspeed.
Therefore, provided that the system is tested prior to opening of the main steam isolation valves, the Unit will be in full conformance with the technical specifications.
Technical S ecification Requirements and Effects As indicated
- above, Technical Specification 3/4.2.8 describes the applicable requirements for Unit 2 compliance.
Exemption Requests No exemption requests are required at this time, since this is a nonsafety related
- system, and Unit 2 will be in conformance with the Technical Specifications.
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