ML18102B639

Proposed Tech Specs Changing SG Insp Schedule to Require Next Insp within 24 Months of Mode 2 for Unit 2 Fuel Cycle 10

ML18102B639
Person / Time
Site:	Salem
Issue date:	10/29/1997
From:	Public Service Enterprise Group
To:
Shared Package
ML18102B638	List: ML18102B637 ML18102B639
References
NUDOCS 9711040054
Download: ML18102B639 (4)

Text

Attachment 3 TECHNICAL SPECIFICATION PAGES WITH PROPOSED CHANGES The following Technical Specifications for Facility Operating License No. DPR-75 are affected by this change request:

Technical Specification

4. 4. 6. 3 3/4 4-11 3/4 4-15a 9711040054 971029 PDR ADOCK 05000311 P PDR

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.6.3 Inspection Frequencies - The above required inservice inspections of steam generator tubes shall be performed at the following frequencies:

a. The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality.

Subsequent inservice inspections shall be performed at intervals of not less than 12 nor more than 24 calendar months after the previous ins ection. If two consecutive inspections following service under VT conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previousiy observed degrada-tion has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.

b. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category C-3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.6.3.a; the interval may then be extended to a maximum of once per 40 months.

c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:

1. Primary-to-secondary tubes leaks (not.including Teaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.7.2.

2. A seismic occurrence greater than the Operating Basis Earthquake.

3. A loss-of-coolant accident requiring*actuation of the engineered safeguards.

4. A main steam line or feedwater line break.

SALEM - UNIT 2 3/4 1\-11

e

-1l l

.l I

• . ALTERNATE INSPECTION SAMPLING FOR SALEK UNIT 2

• FOURTH REFUELING OUTAGE During the S~n t 2 Fourth Retualinq

.associated with wal.J. deqradation were dat oup-i. ..

~.:*~n th~

indicationa tubinq ot th* No. 22 and No. 2*4 team Generators. ,

• condition wa*

e*tal:>li*had aa occurr~~ on the inside .. !a.meter of the Row 1 tub** in the tanqentia J:l~ion of the *-bend.

Th* tollowinq alternate adt) n ~~ taken i~ place ot that required by Technical Specif':

• tya~ Tal:>l* 4. 4-2 when the results ot th* initial *ample require at an additional *ample or sample* must be inspected andq , condition tor which the added

• inspection is required i* li;, l.t to the-Row 1 tubeo. When examination result* tall into a c- or C-3 Supplemental Sample Cateqory, pursuant to Te~ical Spa , tication Tal:>le 4. 4-2 a* a result ot Row 1 and/or 'ow 2 u-bend ,tactive or deqraded tubes, additional sample* ma~b* limited to R wa 1 and 2. Th* results ot the examinatiy.n o ~th* Row 1 and Row tube* will be exempt from the additiona amplinq requirements of Technical .

Specification Tab 4.4-2.

Th:!:s chanqe ap iaa to only those steam 9ener~or '8Cldy current inspectio.nn**;. formed durinq th* Salam Unit 2 ~urth Refueling OUtaqa. /f

"------ ----~,-- -- ----~~~-=---*

I /\J ~612T A SALEK - UNIT 2 3/4 4-lSa Amendment No. 63 Effective Date:

October 14, 1988

"INSERT A" Attachment 3 STEAM GENERATOR SURVEILLANCE PERIOD AMENDMENT FOR SALEM NUCLEAR GENERATING STATION UNIT 2 FUEL CYCLE 2R10 Salem Unit 2 was removed from service in June of 1995 for a comprehensive review of plant methods and policies. In May of 1996, a 100% bobbin coil and additional specialty examinations inspection of the Salem Unit 2 steam generators was completed. Permission to restart Unit 2 was given by the NRC in June of 1997 and Mode 2 first achieved on August 17, 1997. After the May 1996 inspection, Unit 2 steam generators were placed in lay-up, using EPRI guidelines, to protect the steam generators from deterioration. PSE&G has a high level of confidence that corrosion growth and new corrosion initiation during the time of lay-up were essentially halted, and the condition of the steam generators has not changed since the May 1996 inspection.

Thus, in order to avoid an unnecessary mid-cycle steam generator inspection forced outage, Technical Specification 3/4.4~6 is hereby amended such that the next steam generator inspection will be required to be performed within 24 months of Mode 2 for Unit 2 fuel cycle 10. This would be by August 17, 1999. Subsequent steam generator inspections will be scheduled accordingly.