ML20204B371

Forwards Rev 5 to Pump & Valve Inservice Testing Program, for Review.One Anomaly Between NRC Final Technical Evaluation Rept & Rev 4 Program Noted Re Core Spray Check Valves V-20-61,88 & 89

ML20204B371
Person / Time
Site:	Oyster Creek
Issue date:	03/12/1987
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Zwolinsky J Office of Nuclear Reactor Regulation
Shared Package
ML20204B373	List: ML20204B371 ML20204B413
References
NUDOCS 8703250040
Download: ML20204B371 (6)

Text

ENuclear Is = r r -

Route 9 South Forked River.New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Number:

March 12, 1987 Mr. John A. Zwolinski, Director BWR Project Directorate No. 1 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Inservice Testing Program (Rev. 5)

By letter dated July 2,1982, GPUN submitted Revision 4 to the Oyster Creek Nuclear Generating Station Inservice Testing (IST) Program. This program was approved by the NRC on an interim basis, pending final review.

By letter dated December 2,1986, the final Technical Evaluation Report (TER) by the NRC Staff's contractor on the IST Program, Rev. 4, was issued. Based on this evaluation, and both written and verbal exchanges of information, the Oyster Creek Nuclear Generating Station Inservice Testing Program, Rev. 5, has been completed and is attached for your review.

One anomaly between the NRC final TER and the Oyster Creek IST Program, Rev. 4 was noted. In the TER, sections 3.1.1.2 and 3.1.2.2, relating the Core Spray check valves V-20-60, 61, 88, and 89, the NRC quotas GPU Nuclear and states:

"... These valves will be full stroke l

exercised during refueling outages."

l IST Program Rev. 4, notes 11 and 20, do not state that full stroke testing will be performed. The referenced valves are not capable of being full stroke tested without introducing Fire System service water into the Core Spray System.

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pop 0k GPU Nuclear Corporation is a subsidiary of the General Public Utihties Corporation 'l

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If any further information is required, please contact Mr. John Rogers of my staff at (609)971-4893.

Very truly yours,

't edlEr Vice resident and Director Oyster Creek PBF/JR/ dam Attachment cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of. Prussia, PA 19406 Mr. Jack N. Donohew, Jr.

U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue, Phillips Bldg.

Bethesda, MD 20014 Mail Stop No. 314 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 4

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p IN-SERVICE TESTING PROGRAM List of Changes for Revision 5 '

Page Change

1. a) Renumber pages in the Table of Contents'.

b) Add table references c) Deleted section 2D NRC staff guidance for

. preparing pump and valve testing program descriptions.

4 Add the definition of Pressure Isolation Valve 7 Delete reference to Plant Procedure 604.3.008 10 Change the note reference in the " Speed" column from 3 to 4-11 a) Change the note reference in the " Speed" column from 3 to 4.

b) Change the flow rate requirement for the Fire Protection pumps from NR to Q.

13 Delete the alternate testing requirement. A vibration spectrum is obtained at least quarterly for all pumps.

p 14 Add a new Note and label as note 3.

15 a) Renumber notes 3, 4, and 5 to 4,'5, and 6.

b) Delete the original note 6. All pumps have i

flow rate recorded.

17 a) Add GPU ISI boundry drawing numbers to table

, 28-2.

b) Add Cleanup Demineralizer System to table 28-2.

c) Add Condensate Transfer System to table 28-2.

, d) Add Scram Discharge Volume to table 28-2.

4 e) Delete General Physics ISD numbers. Replace

, with GPU ISD numbers.

8 I 29 a) Correct V-14-30, 31, 32, and 33 valve size from '

16 to 10 inches.

b) Move V-14-1, 5 and 19 to page 30.

i 30 a) Add V-14-1, 5 and 19 to page 30 b) Add relief request on V-14-1, 5,19 and 20, 34 Change V-19-16 and 2 from Category C to A/C and add SLT-1.

6

y Page Change 35 a) Move V-21-19 and 20 to page 37.

b) Add V-21-75, 76, 77 and 78 to table.

37- Add V-21-19 and 20.

-38 Add test EF-2 to V-16-1, 2,14 and 61.

39 a) Add note 3A to Y-16-62.

b) Change V-16-62 from category A(3) to category A(1).

40 Move Hydraulic Control Unit Rupture Disc 132 to page 41.

41 a) Add test EF-3 to HCV-106.

b) Delete note 7 and alternate testing for V-15-119,120, and 121.

c) Add test EF-2 to V-15-119,120 and 121.

d) Add valves V-15-133,134,135,136, and 137.

e) Add HCU 132, 42 a) Change V-15-27 and 28 from category C to A/C.

b) Add test SLT-1 to Y-15-27 and 28.

45 a) Change V-20-15 and 40 from Category A3 to A2.

b) Add SLT-1 to valves V-20-15 and 40.

c) Add V-20-92 and 94 to page 48.

46 Move V-20-93 and 95 to page 48.

47 a) Change V-20-21 and 41 from Category A3 to A2.

b) Add SLT-1 to valves V-20-21 aad 41.

48 a) Add test SLT-1 to NZO2-A, B, C and D.

b) Add V-20-92, 93, 94 and 95 with relief requests.

49 a) Change V-31-2 and 5 from category A(3) to A (1).

b) Add note 12A to V-31-2.

c) Add notes 12A and 128 to V-31-5.

d) Change the term " type A" to SLT-1 for V-31-2 and 5.

51 a) Move V-1-7, 8, 9 and 10 to pages 52 and 53.

b) Delete V-1-016,107,110,111.

! 52 and 53 a) Delete test TF-1 from NR-108A, B, C, D and E.

b) Add V-1-8, 7, 9 and 10.

c) Add note 30 and alternate testing for V-1-7, 8, 9 and 10.

55 Add note 15A to V-2-71, 72, 73 and 74.

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Page Change 57 Delete alternate testing and note 16 for V-3-62 and 63.

58 Delete note 19 and alternate testing from V-1-153 and 154.

59 Correct V-11-44 ano 49 valve size from 4 to 3 inches.

62 Correct Y-28-47 valve size from 12 to 2 inches.

63 a) Add V-6-393 and 395.

b) Delete Exemption for V-26-15 and 17.

64 a) Add test EF-4 to V-24-30.

b) Add relief request to V-24-29 and 30, 66 Change V-19-16 and 20 from category C to A/C.

68 Add note 3A for V-16-62.

71 Include refueling outages for alternate testing.

72 Deleted note 7 for V-15-119,120, and 121.

77 Deleted reference to a Section XI leak test (see notes 12A and 128).

78 Add note 12A for V-31-2 and 5.

79 Add note 128 for V-31-5.

80 Add relief request for testing EMRV pressure sensors setpoint. The valves actuate on a signal from the sensor and are not self actuated.

81 Correct valve numbers from V-1-178,179,180 and 181 to V-1-190,191,192 and 193.

83 Add note 15A from V-2-71, 72 , 73 and 74.

84 Delete note 16 for valves V-3-62 and 63.

87 Delete note 19 for V-5-154 and 153.

90 Delete note 22 for V-26-15 and 17.

94 Delete note 26 for V-16-1, 2,14 and 61.

96 Add note 28 for V-21-19 and 20.

r 1 Page Change 97 Add note 29 for HCU-132.

98 Add note 30 for V-1-7, 8, 9 and 10.

99 Add note 31 for V-6-393.

100 Add note 32 for V-6-395.

1 01 Add note 33 for V-14-1, 5,19, 20; V-20-92,93, 94, 95; V-24-29 and 30.

Valve Tables 1 and 3 Change ISD number to GPU drawing number.

i J

(0283A)

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