ML17058A959

Responds to Request for Addl Info Re Reactor Vessel pressure-temp Limits Tech Spec Amend

ML17058A959
Person / Time
Site:	Nine Mile Point
Issue date:	08/30/1991
From:	Sylvia B NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17058A960	List: ML17058A959 ML18038A379
References
NMP1L-0604, NMP1L-604, TAC-80394, NUDOCS 9109120235
Download: ML17058A959 (24)

Text

FQRB 2 REGUL R INFORMATION DISTRIBUT STEM (RIDS)

ACCESSION NBR:9109120235 DOC.DATE: 91/08/30 NOTARIZED: YES DOCKET ¹ FACIL:50-220 Nine Mile Point Nuclear Station, Unit , Niagara Powe 05000220 AUTH. NAME AUTHOR AFFILIATION SYLVIAiB.R. Niagara Mohawk Power Corp.

RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (D ument Con rol Desk)

SUBJECT:

Responds to request for addi info re reactor vessel pressure

-temperature limits tech spec amend.

DISTRIBUTION CODE: DF01D COPIES RECEIVED:LTR ( ENCL szzE: (~ + Q TITLE: Direct Flow Distribution: 50 Docket (PDR Avail)

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL INTERNAL: NUDOCS-ABSTRACT 1 1 REG FILE 01 1 1 EXTERNAL: NRC PDR 1 1 SsIi 1 1 4W'Don Kr(nk ag TOTAL NUMBER OF COPIES REQUIRED: LTTR 4 ENCL 4

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~0 9 ggOo~g NIAGARAMOHAWKPOWER CORPORATION/301 PLAINFIELDROAD, SYRACUSE, NEW YORK 13212/TELEPHONE (315) 428-7494 B. Raiph Sylvia Executive Vice President Nuclear August 30, 1991 NMP1L 0604 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63 TAC NO. 80394 Gentlemen:

I

SUBJECT:

RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR VESSEL PRESSURE-TEMPERATURE LIMITS TECHNICAL SPECIFICATION AMENDMENT By letter dated May 13, 1991 (NMP1L 0582), Niagara Mohawk submitted an Application for Amendment to the Nine Mile Point Unit 1 Operating 'License.

The Amendment consisted of proposed changes to Technical Specification Section 3.2.2/4.2.2, Minimum Reactor Vessel Temperature for Pressurization, and the associated Bases. In a May 31, 1991 teleconference, your staff requested additional information regarding our submittal. This information was informally telecopied to your staff in June 1991.

In a subsequent teleconference on July 16, 1991, your staff requested that we document in a letter our response to the request for additional information.

Also requested was a copy of the final report entitled, "Nine Mile Point Unit 1 Surveillance Capsule Program," January 1991. The enclosures to this letter provide the information requested and supplements our May 13, 1991 Application for Amendment.

9109120235 910830 PDR ADQCN, 05000220 p PDR 001331LL

0 Pursuant to 10CFR50.91(b)(1), Niagara Mohawk has provided a copy of this additional information to the appropriate state representative.

Very truly yours, B. Ralph Syl ia Exec. Vice President-Nuclear AER/sek 001331LL Enclosures xce Regional Administrator, Region I(w/o Final Report NMEL-90001)

Mr. W. L. Schmidt, Senior Resident Inspector(w/o Final Report NMEL-90001)

Mr. R. A. Capra, Project Director, NRR(w/o Final Report NMEL-90001)

Mr. D. S. Brinkman, Senior Project Manager, NRR Mr. D. R. Haverkamp, Chief, Reactor Projects Section No. 1B(w/o Final Report NMEL-90001)

Ms. Donna Ross Division of Policy Analysis and Planning New York State Energy Office Agency Building 2 Empire State Plaza Albany, NY 12223 Records Management

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Niagara Mohawk Power Corporation Docket No. 50-220 (Nine Mile Point Unit 1)

AFFIDAVIT B. Ralph Sylvia, being duly sworn, states that he is Exec. 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.

NIAGARA MOHAWK POWER CORPORATION B. Ralph ylvia Exec. Vice President-Nuclear Subscribed and sworn to efore me, a Notary Public in and for he State of New York and County of this ~M day of 1991.

Not ry Pub ic in and for 1

County, New York BEVE t.Y W. RIPKA Nctartr Public Stateol New York Qual. in Oswego Cc rto. 4644NS My Commission gxp~M&9, My Commiss'on Expires:

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NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT UNIT 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING REACTOR VESSEL PRESSURE-TEMPERATURE LIMITS TECHNICAL SPECIFICATION AMENDMENT QUESTION 1 Provide the chemical composition (Cu, Ni), initial RT>>>> and unirradiated Charpy impact upper shelf energy for the following beltline materials and welds:

Beltline Materials U er Shell Course P2074-2/G-307-3 P2076-1/G-307-4 P2091-2/G-307-10 Lower Shell Course P2112-1/G-8-1 P2130-1/G-8-3 P2130-1/G-8-4 Welds Lower Intermediate Shell (heat 86054B), Flux Arcos B-5 (lot 4E5F)

Lower Intermediate Shell (heat 1248), Flux Arcos B-5 (lot 4K13F)

Girth Weld (heat 1248), Flux Arcos B-5 (lot 4M2F)

RESPONSE

The chemical composition and initial RT>>~ for the beltline plates and welds are provided in Attachments 1A and 1B respectively.

The unirradiated Charpy impact upper shelf energy for the beltline materials are presented in Attachment 1C. As noted in Attachment 1C, the unirradiated Charpy impact upper shelf energy for beltline welds 4E5F, 4M2F and 4K13F were not measured and are unavailable.

UESTION 2 Provide the neutron fluence at 18 EFPY and end of life for the beltline materials.

RESPONSE

The neutron fluence at 18 EFPY is provided in Attachment 2A. The neutron fluence at end of life is shown in Attachment 2B.

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QUBSTION 3 Indicate vhich beltline material(s) vill be the limiting material(s) after 18 EFPY.

RESPONSE

The limiting beltline material after 18 EFPY is beltline plate G-307-4 as shown in Attachment 3.

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ATTACHMENT 1A: Chemical Composition Initial RTNDT for Beltline Plates ADJUSTED RTNoT FOR NINE MILE POINT UNIT 1 BELTLINE MATERIALS Plates - Beltline Initial'4't.%

18 EFPY@

Wt.% RTNpT( F)

Heat No. ~b,RT pTLFF MARGIN 'F ~ART p~~F G-8-3/G-8-4(') 0.18 0.56 -3 55 34 86 G-8-1n) 0.23 0.51 36 65 34 135 G-307-3 0.20 0.48 28 57 34 119 G-307-4'" 0.27 0.53 40 73 34 147 G-307-10 0.22 0.51 20 63 34 117 NOTE:

(Peak fast (E>1Mev) fluence is 1.027 x 10 "n/cm't vessel 1/4 T position. All calculations based on Revision 2 to Regulatory Guide 1.99)

(1) These materials are also in the reactor vessel surveillance program.

(2) Limiting plate.

(3) Calculations performed at vessel 1/4 T position using peak beltline flux.

(4) tMA91]

ATTACHMENT 1B: Chemical Compositio d Initial RT for Beltline Welds ADJ USTED RT~DT FOR NINE MILE POINT UNIT 1 BELTLINE MATERIALS Welds - Beltline 18 Wt.%"'t.%"'nitial~ ~

EFPY"'eat/Lot No. RT oT~F ART L'B ~MARGIN 'R ART oT~F W5214/5G13Ft" 0.35 1.0 -50 115 66 131 86054/4E5F 0.35 1.0 '. -50 115 66 131 1248/4K13F 0.35 1.0 -50 115 66 131 1248/4M2F 0.35 1.0 -50 115 66 131 NOTE:

(Peak fast (E>1Mev) fluence is 1.027 x 10"n/cm't vessel 1/4 T position. All calculations based on Revision 2 to Regulatory Guide 1.99)

(1) These materials are also in the reactor vessel surveillance program.

(2) Calculations performed at vessel 1/4 T position using peak beltline flux.

(3) [MA91]

(4) The most conservative approach described in RG1.99(2) was used to demonstrate that the welds are not limiting in comparison with the plate material.

e ATTACHMENT 1C: Unirradiated Charpy Impact Upper Shelf Energy for Beltline Materials C A PY INDICES FOR LA ES es e Data Plate Plate Plate Plate Plate

~G-307- ~G- 3 0 0t 2 F 0 F 0 F 0 F 0 F RT~T () -24 F(I, T) 12 F(L-T) 44F <L-T) 16 F (L-T) 44F RTer -3 F(T-L) 364F(t-L) 284F <t-L) 4 0 F (T-L) 20 F (t-L)

"'0~

11 ft-lb. 10 ft-lb. 11 ft-lb. 10 ft-lb. 10 ft-lb.

30

-26 F<L-T) 84F (L-T) -144F (L-t) O'F <L->> -3 F (L-T) 0 F<t L)

~

Upper Shelf Energy

(~'unirradiated) 96 ft-lb.<L-T) 88 ft-lb.(L-t) 112 ft-lb. <L-T) Sift-lb<L-t)115 ft-lb. <L ~ >>

68 ft-lb. (T-L)

(t) L-T orientation. P-T calculations require RT~T to be determined for the T-L orientation.

(~) T-L orientation. Obtained by adding 24 'F to the L-T orientation data for all plates except G-8-3/G-8-4. The value was determined experimentally.

(~) Fracture appearance data are not available for any beltline plates. Upper shelf data

@ac identified by the shape of the curve fit.

NOTES: 1. The unirradiated upper shelf energy for beltline welds 4E5F, 4M2F and 4K13F were not measured and are unavailable.

2. Weld W5214/5G13F is the surveillance capsule weld.. Based on calculations using the irradiated capsule Charpy data, the unirradiated upper shelf energy for this weld was determined to be 128 ft. lb. This weld was not made using the same wire or flux as the beltline welds. However, the surveillance capsule weld materials were manufactured by the same suppliers as the beltline materials (Raco N3 wire, Arco B5 flux) and the Cu and Ni content is representative of the beltline weld 1248/4M2F. Therefore, it has been assumed that the capsule weld material is similar to beltline welds in terms of mechanical behavior.

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ATTACHMENT 2A: Neutron Fluence at 18 EFPY for Beltline Materials

SUMMARY

OF THE ARTOT FOR PLATE G-307-4 AT 18 EFPY USING REVISION (2) OF REGULATORY GUIDE 1.99 Exposure ~n/cm'G1.99(2)

Fluence"'ocation

~EFPY ~ART ()T~F 1/4 T 18 1.027 x 10" 3/4 T 18 4.286 x 10'44 113 (1) The RG1.99(2) DPA attenuation model was used to calculate the 1/4 T and 3/4 T fluences,

ATTACHMENT 2B: Neutron Fluence at En Life (EOL) for Beltline Materials FLUX ANO FLUENCE 1N THE PRESSURE VESSEL MALL OF Fluence in Vessel Mall Full Power Flux in Vessel Mall Behind Capsule (300 ) Haxiaxjw (285.66o)

Energy Location Behind Capsule (300o) Haxieua (285.66'o) Harch 82 (1) EOL (2) Harch 82 (1) EOL (2)

(Hev) (n/cw /sec) x 109 (n/cm /sec) x 109 (n/aa x 1017) (n/cja x 1018) (n/cw x 1018) (n/cja x 1018) 0.1 Surface 3.19 5.56 8.03 3.22 1.40 5.61 0.1 1/4 T 2.85 5.01 7.17 2.88 1.26 5.08 0.1 3/I T 1.31 2.26 3.30 1.32 0.569 2.28 1.0 Surface 1.51 2.80 3.80 1.52 0.705 2.83 1.0 1/4 T 1.02 1.91 2.57 1.03 0.481 1.93 1.0 3/I T 0.281 0.514 0.707 0.284 0.129 0.51 (1) Fluence based on 7.98 effective full power years of operation.

(2) Fluence based on 32 effective full parer years of operation.

4 ATTACHMENT<3,: Limiting Beltli aterial After 18 EFPY, ADJUSTED RT)(or FOR NINE MILE POINT UNIT 1 BELTLINE MATERIALS Plates - Beltline Initial"'t.%

18 EFPY("

Wt.% RTNDY('F)

Heat No. hRT ov~F MARGIN F ~ART D,~F G-8-3/G-8-4'" 0.18 0.56 -3 55 34 86 G-8-1(') 0.23 0.51 36 65 34 135 G-307-3 0.20 0.48 28 57 34 119 G-307-4 027 053 40 73 34 147

'G-307-10 0.22 0.51 20 63 34 117 NOTE:

(Peak fast (E)1Mev) fluence is 1.027 x 10 "n/cm't vessel 1/4 T position. All calculations based on Revision 2 to Regulatory Guide 1.99) 1 These materials are also in the reactor vessel surveillance program.

(2) Limiting plate.

3 a cu at(ons performed at vessel 1/4 T position using peak beltline flux.

(4) tMA91]

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