ML18081A460
| ML18081A460 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/24/1979 |
| From: | Schneider F Public Service Enterprise Group |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 7911010565 | |
| Download: ML18081A460 (5) | |
Text
~
Frederick W. Schneider Vice President Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 201/430-7373 Production Mr. Boyce H. Grier, Director U.S. Nuclear Regulatory Commission Off ice of Inspection and Enforcement Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Grier:
NRC IE BULLETIN NO. 79-02 SUPPLEMENTAL RESPONSE NO. 1 UNIT SALEM GENERATING STATION September 24, 1979 Pursuant to our initial response dated July 6, 1979 on the subject bulletin, we hereby submit additional information for your review.
This information responds to your letter of August 28, 1979 (ref: IAL No. 79-12) and confirms the discussions held with the NRC staff during the meeting held in Washington, D.C. on August 17, 1979, and subsequent telecon of September 12, 1979.
We trust that the information contained in the enclosed attachment is acceptable and we are accordingly. looking forward to returning Salem No. 1 Unit to service on October 10, 1979.
If you require any further infoimation regarding the attached report, we will be pleased to discuss it with you.
Attach.
CC:
NRC Office of Inspection
& Enforcement Sincerely,
~ £t/.fa~~r.-.L~
)*:z Div. of Reactor Operations Inspection Washington, D.C. 20555 L. J. Norrholm NRC, Hancocks Bridge, NJ 7911 010 5' 6 5
r-- -
NRC IE BULLETIN 79-02 RESPONSE SUPPLEMENT I UNIT NO. 1 SALEM NUCLEAR GENERATING STATION The following is a test program outline for testing and examination of anchor bolt installation in safety related piping systems.
I.
EMBEDMENT VERIFICATION A.
Scope Accessible Seismic Class I pipe support bolts employing wedge type concrete anchors, shall be examined to d~termine embedment length within the concrete.
Piping systems included in the scope of this program are as follows:
- 1.
- 2.
- 3.
Safety Injection
- 4.
Steam Generator Feed
- 5.
Component Cooling
- 6.
Nuclear
- 7.
- 8.
- 9.
Main Steam lQ.
Chilled Water
- 11.
Chemical & Volume Control
- 12.
Control Air ~ Safety Related
- 13.
Diesel Generators Starting Air & Fuel
- 14.
Steam Generator Dr a ins and Blow. Down
- 15.
Spent Fuel Cooling B.
Procedure
- l.
Effective length of installed bolting is determined by means of ultrasonic testing utilizing equipment which is calibrated against bolts of the type utilized in the plant.
- 2.
Ernbedment length is determined by subtracting the m~asured portion of the boltihg extending out of the concrete surface from the total effective bolt length as measured ultrasonically.
- 3.
Measured embedment lengths are compared against embedment required for design load.
- 4.
Corrective actions, if any, required as a result of embedment verification are implemented by means of documented Design Change Requests (DCR's}.
C.
Schedule Completion of the embedment examination aspect of installation verification together with required corrective actions shall be accomplished prior to achieving Mode 4.
II.
ANCHOR BOLT WEDGE SETTING PROGRAM A.
Scope Seismic Class I Systems defined in Section I.A above shall have bolting randomly sampled on a*system by system basis to determine the adequacy of anchor wedge setting during original installation.
Such sampling shall be of sufficient quantity to provide 95% confidence that less than 5% improperly set anchors are i~stalled in any of the specified safe~y related systems.
B.
Procedure
- 1.
The original position of a given load bearing nut *in the sample bolt is marked to establish the *as installed* position.
- 2.
The nut is loosened a sufficient amount as necessary to visually confirm that there is no termination of bolt thread at or outside the interface between the nut and the support steel outer surface.
Nut loosening is also done to verify freedom from any bolt and nut thread binding due to paint, debris or thread damage.
- 3.
The nut is returned to its original position and then tightening is attempted.
~cceptance of the sample is based on the amount of* turning, if any, it takes to bring the nut to the proper level of tightening (approximately one turn being established as the max tolerance}.
C.
Schedule If in performing sample wedge'set testing on a given system, the specified confidence as to proper wedge setting is not confirmed, sufficient additional bolting will be tested with ~ppropriate corrective action to provide for a bolt factor of safety of at least two {per Bulletin 79-02, Revision Ir Supplement I
- B) as f o 11 o ws :
A.
In areas inaccessible during operation, prior to achieving Mode 4, hot shutdown.
B.
In areas accessible during operation prior to November 15,_1979.
III. LOAD TEST VERIFICATION A.
Scope The'test and examination programs discussed in Items I & II. above are considered adeq~ate to justify installation verification aspects of pipe support anchor bolts.
In certain instances, however, bolt design calls for threaded rod and coupling extensions on anchor bolts which are embedded in poured concrete piers.
Such installations which occur primarily where base plates are used, preclude UT or any other known non-destructive embedment verification method.
Also, methods.for verifying anchor wedge set are precluded because the wedge setting mechanism, i.e.
threaded rod coupling, is embedded in cone rete.
To provide confidence that such designs are in fact adequate, a test program for loading these supports has been established on a sample basis.
B.
Program Procedure
- 1.
applied plate.
load.
By means of hydraulic jacks, a test load is on the pipe support attachment to the base This load is a function of the design piping
- 2.
Acceptance criteria of the support is established on the basis of measured elongation of the bolt under test load.
C.
Schedule Base plate bolt load testing together with corrective actions, if any, required from the testing shall be complete prior to Mode 4 operation.
9Ll 0 9/12