L-11-359, Response to Request for Additional Information on 10 CFR 50-355a Request RR-A35, Proposed Alternative to System Leakage Test Requirements

Response to Request for Additional Information on 10 CFR 50-355a Request RR-A35, Proposed Alternative to System Leakage Test Requirements

ML113390047
Person / Time
Site:	Davis Besse
Issue date:	12/02/2011
From:	Allen B FirstEnergy Nuclear Operating Co
To:	Office of Nuclear Reactor Regulation, Document Control Desk
References
L-11-359, TAC ME6056
Download: ML113390047 (7)

Text

{{#Wiki_filter:FENOC FirstEnergy Nuclear Operating Company 5501 North State Route 2 Oak Harbor. Ohio 43449 Barry S. Allen Vice President - Nuclear December 2, 2011 L-11-359 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Davis-Besse Nuclear Power Station Docket No. 50-346, License No. NPF-3 10 CFR 50.55a Response to Request for Additional Information on 10 CFR 50.55a Request RR-A35. Proposed Alternative to System Leakage Test Requirements (TAC No. ME6056) By correspondence dated April 15, 2011 (Accession No. ML11109A119), FirstEnergy Nuclear Operating Company (FENOC) submitted a proposed alternative to certain requirements associated with the inservice inspection program for the Davis-Besse Nuclear Power Station. 419-321-7676 Fax: 419-321-7582 By correspondence dated November 3, 2011 (Accession No. ML113060557), the Nuclear Regulatory Commission (NRC) requested additional information to complete its review of the proposed alternative. FENOC's response to this request is attached. Additionally, piping and instrumentation diagrams are provided as Enclosures A and B, and a piping isometric drawing is provided as Enclosure C. There are no regulatory commitments contained in this submittal. If there are any questions or additional information is required, please contact Mr. Phil H. Lashley, Supervisor - Fleet Licensing, at (330) 315-6808. Sincerely,

Attachment:

Response to 11/3/11 Request for Additional Information on Request RR-A35, Proposed Alternative to System Leakage Test Requirements

Davis-Besse Nuclear Power Station L-11-359 Page 2 of 2

Enclosures:

A. Piping and Instrumentation Diagram - Reactor Coolant System B. Piping and Instrumentation Diagram - Decay Heat Removal/Low Pressure Injection System C. Inservice Inspection Piping Isometric - Pressurizer Spray and Surge Lines cc: NRC Region III Administrator NRC Resident Inspector NRC Project Manager Utility Radiological Safety Board

Attachment L-11-359 Response to 11/3/11 Request for Additional Information on Request RR-A35, Proposed Alternative to System Leakage Test Requirements Page 1 of 2 By letter dated April 15, 2011, FirstEnergy Nuclear Operating Company (FENOC) submitted 10 CFR 50.55a Request RR-A35 for Nuclear Regulatory Commission (NRC) review and approval. By letter dated November 3, 2011, NRC staff requested additional information to complete the review. The requested information is presented in bold type, followed by the FENOC response.

1. For the subject auxiliary pressurizer spray system Test Zone DH16:

a. Provide a piping and instrumentation diagram and a piping isometric drawing.

Response

The examination boundary for Test Zone DH16, Pressurizer Spray Line, is from valve DH2735 to valve RC51. Piping and instrumentation diagrams are provided as Enclosures A and B. The piping isometric drawing is provided as Enclosure C.

b. What is the length of the auxiliary pressurizer spray line between RC51 and DH2735?

Response

As determined from Enclosure C, the length of the auxiliary pressurizer spray line from the outlet of valve DH2735 to the inlet of valve RC51 is approximately 127 feet.

c. How many welded connections and what type (butt, socket) are in this segment?

Response

As determined from Enclosure C, there are 42 total socket welds in this segment. This includes the outlet weld of valve DH2735, the inlet weld of valve RC51, and 6 additional socket welds on a double root valve appendage.

d. What is the expected operating pressure of this segment when the reactor coolant pumps are stopped and the decay heat removal pump is operating?

Respons~: As determined by calculation, the average expected operating pressure in this segment when the reactor coolant pumps are stopped and the decay heat removal pump is operating is approximately 97 pounds per square inch absolute (psia). For this calculation, the segment boundaries (with their respective operating pressures) are the outlet of valve DH2735 (125 psia) and the inlet of valve RC51 (68.2 psia). The test pressure cited in Request RR-A35 (77 psia) is located at valve RC51.

Attachment L-11-359 Page 2 of 2

2. Has there been a plant or industry history of degradation of the subject segments in Test Zones DH16 and RC01 by mechanisms such as stress corrosion cracking or fatigue?

Response

For Test Zones DH16 and RC01, a review of FENOC's corrective action program (CAP) did not reveal any plant history of degradation due to stress corrosion cracking or fatigue. The review was limited to the period of 1999-2011 due to the current CAP database structure. For Test Zones DH16 and RC01, a review of inservice inspection pressure test results from the same time period also revealed acceptable results with no stress corrosion or fatigue related leaks noted. Specific test results reviewed were from the years of 2000,2003,2004, 2006, 2008, and 2010. Industry operating experience (OE), however, has shown the susceptibility of stress corrosion cracking in stainless steel. This OE includes instances of outer diameter initiated stress corrosion cracking (ODSCC) of the pressurizer auxiliary spray lines at the Calloway and Wolf Creek nuclear plants. FENOC evaluated the OE and determined that the susceptibility for ODSCC exists at Davis-Besse. In response to the OE, FENOC evaluated and implemented recommendations from the Pressurized Water Reactor Owners Group (PWROG) interim strategy for identifying ODSCC. This guidance is considered a "Good Practice" recommendation per the Nuclear Energy Institute's "Guideline for the Management of Materials Issues [NEI 03-08]." Additionally, FENOC and its industry peers are collaborating on research to address stress corrosion cracking of stainless steels. The PWROG is leading this initiative that has thus far produced PA-MSC-0563, "Industry Roadmap - Stress Corrosion Cracking of Stainless Steels." FENOC continues to monitor industry activities related to ODSCC for incorporation into Fleet programs.

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2. FOR 151 BOUNDARY DIAGRAM INDEX SHEET AND GENERAL NOTES.

SEE IS 1D2 -001 *

3. FOR PIPING SYMBOLS AND paiD INDEX. SEE DRA~ING M-OOI.

4. UNLESS OTHERWI SE NOTED. ALL VENT CONNECT IONS ARE r..' AND DRAIN CONNECTIONS ARE I '.

LINE IDENTIFICATION IS THE SAME AS THE HEADER.

5. FOR lSI PURPOSES ONLY THE CLASS I PIPING SYSTEMS SUPPLIED BY B B W HAVE BEEN ASSIGNED THE FOLLOWING LINE DESIGNATIONS WHICH ARE SIMILAR TO BUT ARE NOT TO BE CONFUSED WITH M601/M602 DESIGNATIONS:

36'-CBA-I.6 28'-CBA-2 TO 5.7 TO 10 10'-BCA-I 2Yz'-BCA-2 8 3

6. THE FOLLOWING LINE NUMBERS ARE ASSOCIATED ~ITH THE TE-ITEM NUMBERS LISTED:

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• RCB-O RCB-3 RCB-I RCB-4 RCB-2 RCA-O RCA-I RCA-3 RCA-2 RCA-4 PI-O PI-7 PZ-7A

7. RC46 MAY BE CLOSED IF LEAKAGE EXISTS.

8. THE INSTRUMENTATION VALVES OFF THE REACTOR COOLANT SYSTEM PIPING ARE SHOWN ON paiD M-030B. THE lSI CLASS I BOUNDARY EXTENDS TO THE SECOND VALVE OFF THE PIPING.

9. WHERE NOTED THE TANK CAPACITY IS NOMINAL. WHERE APPLICABLE

• SEE DB-PF-06705 (TANK LEVEL CALIBRATION CURVES) FOR INDICATED LEVEL VS. VOLUME RELATIONSHIP. (REF. PCAOR 96-0976).

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DH2733 (SC) 18"-HCB-1 18"-GCB-8 2 2 2 FT 4909 FE 4909 DH4909A DH4909B 2 2 1 8"-CCA-4 2"-HCC-34 6"-GCB-10 11 1 2 DH2AB DH2AA 29-0 29-0 28-3 28-4 28-4 27-4 27-7 27-6 28-7 28-6 28-7 27-7 27-2 27-3 74C-1 74C-0 27-2 27-1 27-1F 27-1E 27-1E 27-1E 27-1D 27-1D 28-1C 27-1 27-1 28-0A 28-1A 28-1 28-1 28-1B 28-1A 28-1 28-0 28-1A1 28-1A1 28-0A 28-1C 28-1 28-1D 28-1E 28-1E 27-1 27-1 28-0 31-7 31-8 28-1B 29-2 29-2D 29-2C 29-2B 29-2A 29-2A 29-2B 29-2C 29-2D 31-7 31-6 31-6 31-2 31-1 31-1 31-0 31-2 31-3 31-8 31-0 29-1B 29-1A 29-1C 29-1D 29-1B 29-1 29-0A 29-0 28-3 28-2 49-0 49-0 28-2 28-1 (L.C.) 2 FROM REFUELING CANAL DRAIN PUMP P204 NO. 1-1 LEVELS 123456789012345678901234567890123456789012345678901234567890 5 12 111111111122222222223333333333444444444455555555 5666 M-033B (E-4) 2 2 SHT.2 SHT.2 SHT.1 SHT.2 28-200-0 SHT.1 SHT.1 Q (SC) PSV 1529 1"-GCB-10 2 DH1529 27-200-0 27-1F SHT.2 SHT.2 SHT.1 SHT.2 SHT.1 SHT.4 SHT.2 SHT.3 SHT.3 SHT.1 SHT.2 SHT.2 SHT.3 SHT.1 SHT.1 SHT.2 SHT.1 29-100-1 SHT.2 SHT.2 SHT.2 SHT.2 SHT.2 SHT.2 SHT.2 SHT.2 SHT.1 SHT.1 DH128 SHT.2 UNLESS OTHERWISE NOTED, ALL VENT CONNECTIONS ARE " 1. 2. 3. 4. 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CB Q CF32A CF33A ISIM2-233B ISIM2-233B ISIM2-233B ISIM2-233B ISID2-033A (K-10) ISID2-033C (D-5) ISIM2-233B 3 2 ISID2-033C (E-3) ISID2-033C (E-3) ISIM2-233C ISIM2-233C ISIM2-235A ISIM2-233B ISIM2-233C ISIM2-233C ISIM2-233C ISID2-030A (D-6) ISIM2-233C ISIM2-233C ISIM2-233F ISIM2-233F ISIM2-231D ISIM2-233C ISIM2-233F ISIM2-233F 2 2 SHT.2 SHT.2 ISID2-033C (A-9) ISIM2-233F ISIM2-235A ISIM2-235A ISIM2-233F ISIM2-233F ISIM2-234D ISIM2-233F ISIM2-234D ISIM2-233B ISIM2-233F ISID2-033A (F-7) ISID2-033A (J-9) ISIM2-233F ISIM2-234D ISID2-033A (G-9) ISID2-033A (G-9) ISIM2-233F ISIM2-234A ISIM2-234A ISIM2-233F ISIM2-233G ISIM2-233F ISIM2-233F ISIM2-233G ISIM2-233F ISIM2-233F ISID2-033A (D-10) ISID2-033C (D-11) ISIM2-230C ISID2-034 (K-3) ISID2-030A (C-9) ISIM2-234A ISIM2-234A ISIM2-234A ISIM2-234A ISIM2-234A ISIM2-234A ISID22-034 (K-8) ISID2-033C (D-11) S/I S/I S/I S/I DH71 DH70 M-033B (D-11) M-033B (D-11) M-033A (G-9) PSV 2797 1"-HCC-34 1"-HSC-75 2" 1" (SC) (SC) X X DH2797 DH74 DH155 DH155A DH156 DH156A DH177 DH75 DH177A DH22 S/I S/I S/I TW DH4B L.O. DH98 DH62 DH61 DH63 DH75A S 2 Q S/I 28-1F SV M-042C (C-6) ENGR. MGR. 4633 DH4633 ASME SECTION XI CLASS CHANGE 1 1 SHT.2 ISIM2-233C ISIM2-233C 2 1 29-1A 29-0A SHT.2 ISIM2-233C ISIM2-233C 29-2 29-1 SHT.1 SHT.1 SHT.3 ISID2-035 (E-3) Q 27-4 27-3 49-1 49-2 49-2 3 49-1 27-200-0B S/I Q (L.C.) TRN RJC TWB MGP ECC 2 9/17/90 ISSUED FOR SECOND 10 YEAR ISI PROGRAM DJR L.C. 5. DH11 AND DH12 PROVIDE COMPLETE ISOLATION IN THE NORMAL FLOW DIRECTION ONLY. REFER TO VDWG M-525-28 FOR SPECIFIC BONNET VENTING DETAILS. NOTE 5 NOTE 5 DH100A 1"-CCB-38 ISIM2-233D DH1517A

"-GCB-7 1"

ISID2-033C (F-3) NOTES: DELETED F.C. SEE NOTE 6 6. VALVE DH4633 IS SHOWN ON P&ID M-042C. (SC) 2"-CCB-39 L.O. L.O. DH10 DH204 (D) 2"-GCB-7 2"-GCB-7 SHT.1 ISIM2-233I THIS DWG D-12 DH205 (V) 2 "-GCB-12 29-1C SHT.2 ISIM2-233C DH207 2"-GCB-12 DH208 (D) DH209 TEST CONN. 3"-GCB-12 2"-GCB-12 THIS DWG J-6 2"-GCB-12 DH206 SHT.1 ISIM2-233I ISID2-033A (J-5) FROM HPI PUMP 1-1 DISCHARGE 14 DB 12-07-10 DFN= I:/ISID/2SID033B.DGN 4 1 11 14 L.O. DH203 L.C. L.O. DH164B 12 2 5 08 DH180 (V) INC. DCN ISID2-033B-26 PER ECR 05-0159-00 REV.0 & GEN. UPDATE NIPPLE/CAP NOT SHOWN PER THIS DCN FOR VALVE DH180 (G-6) PER M-033B REV.47 & ISI PROGRAM ENGR CONCURRENCE (SEE NOTIF. 600427902) DH112A DH110A S441A CYCLONE SEPARATOR DH114A DH110B S441B CYCLONE SEPARATOR DH112B DH114B 16 09 13 "INITIALS ON FILE" D D HVAC DUCT REFERENCE & CONTINUITY LEGEND (RED) (BLUE) (GREEN) ASME SECTION XI CLASS 1 PIPING ASME SECTION XI CLASS 2 PIPING ASME SECTION XI CLASS 3 PIPING INC. DUN 08-0408-001-005 REV.00 & GEN. UPDATE ADD LINE CODING/COLOR LEGEND BACK (REMOVED IN ERROR AT REV.9 UPDATE) SEE NOTIF. 600500193 SBW SAS DJM CTD TAS 0 SBW INC. DUN 09-0109-001-002 REV.00 14 DH186 (V) SAS JSH TAH

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