Bulletin 87-02: Fastener Testing to Determine Conformance with Applicable Material Specifications
SSINS No.: 6820
OMB No.: 31500011
NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
WASHINGTON, D.C. 20555
November 6, 1987
NRC COMPLIANCE BULLETIN NO. 87-02: FASTENER TESTING TO DETERMINE CONFORMANCE
WITH APPLICABLE MATERIAL SPECIFICATIONS
All holders of operating licenses or construction permits for nuclear power
The purpose of this bulletin is to request that licensees 1) review their
receipt inspection requirements and internal controls for fasteners and
2) independently determine, through testing, whether fasteners (studs, bolts,
cap screws and nuts) in stores at their facilities meet required mechanical
and chemical specification requirements.
Description of Circumstances:
Over the past year, some NRC procurement inspections have included the col-
lection and testing of a small sample of fasteners. This limited program was
initiated in response to a concern by the Industrial Fastener Institute over
the potential use of inferior fasteners in military and industrial
applications, including nuclear power plants. The results of NRC testing of
fasteners obtained from San Onofre, Palo Verde and Rancho Seco indicates that
11 out of the 32 fasteners tested do not meet specification requirements for
mechanical and/or chemical properties. Nine of the nonconforming bolts from
Palo Verde and San Onofre were out of specification based on chemistry. Five
nonconforming bolts came from Palo Verde and were all marked as SAE Grade 8
but were actually found to be SAE Grade 8.2. The four nonconforming fasteners
from San Onofre were slightly out of specification for nickel or chromium.
Two bolts from Rancho Seco with ASTM A193 B7 head markings were determined to
have an average ultimate tensile strength of approximately 55 ksi instead of
the specified 125 ksi for ASTM A193 B7 bolting material. The chemical
analysis of these bolts indicated that they were medium carbon steel material.
Rancho Seco is still investigating the extent and safety significance of these
. NRC Compliance
November 6, 1987
Page 2 of 3
In a separate effort, Calvert Cliffs recently tested 1539 fasteners following
their discovery that commercial grade fasteners had been used in
safety-related applications. The test results indicated that 399 failed to
meet specification requirements for mechanical and/or chemical properties.
Based on evaluations performed by Calvert Cliffs, the fasteners which did not
meet specification would have still fulfilled their safety function.
Actions to be Taken:
The results of the limited testing described above have demonstrated the need
to obtain additional information on the adequacy of fasteners used in nuclear
Within 60 days from the receipt of this bulletin, licensees are requested to
provide the following information concerning their receipt inspection and
internal control procedures for fasteners and the results of independent
testing of fasteners:
1. Describe a) the characteristics currently examined during receipt
inspection of fasteners (i.e., head markings for grade and manufacturer
symbols, review of certified material test report or certificate of
conformance), and b) internal controls utilized during storage and
issuance from stock to assure the appropriate use of fasteners.
2. Select a minimum sample of ten (10) non-safety related fasteners (studs,
bolts, and/or cap screws), and ten (10) safety-related fasteners (studs,
bolts, and/or cap screws) from current, in use, stock. The sample is to
be obtained by the licensee with the participation of an NRC inspector.
Fasteners procured to meet the following chemical and mechanical
properties are of interest: A-193 grades B7, B8, and B16; SAE J429
grades 5 and 8; A-449; A-325 Types 1,2 or 3; A-354 grades BB, BC, BD;
A-490; A-320 LTM; A-307; A-563; or equivalent.
3. For the selected sample of fasteners in item 2, include a sample of
typical nuts that would be used with each fastener (one-for-one). In
particular, nuts purchased to the chemical and mechanical speci-fications
of A-194 are of interest.
4. Chemical testing shall be performed on all samples. Mechanical testing
shall be performed on each safety-related fastener. Hardness testing
shall be performed on each nut and non-safety-related fastener. All
testing shall be performed by a laboratory which the licensee has quali-
fied for this type of testing and appears on the licensee's approved
vendor list. Testing performed shall be done in accordance with the
requirements of the fastener's specification, grade, and class, and the
test shall evaluate the ultimate tensile strength, hardness and chemical
properties as required by the fastener's specification, grade, and class.
Each sample shall be tagged with the sample's ID number.
. NRC Compliance
November 6, 1987
Page 3 of 3
5. The results of all tests, together with supporting information, are to be
reported to the NRC utilizing the format shown in Attachments 1 and 2 of
this bulletin. Include the names and addresses of suppliers and
manufacturers of safety-related fasteners and, to the extent possible, of
non-safety-related fasteners. For any fastener found out of specifica-
tion, provide an evaluation of the safety significance including
ation of the most limiting application.
6. Based on the results of the testing and review of current procedures,
describe any further actions being taken to assure that fasteners used in
the plant meet the requisite specifications and requirements and that the
operability of safety-related plant components is not affected.
The written reports shall be submitted to the appropriate Regional
Administrator under oath or affirmation under provisions of Section 182a,
Atomic Energy Act of 1954, as amended. Also, the original copy of the cover
letters and a copy of the reports shall be transmitted to the U.S. Nuclear
Regulatory Commission, Document Control Desk, Washington, D.C., 20555 for
reproduction and distribution.
This request for information was approved by the Office of Management and
Budget under a blanket clearance number 31500011. Comments on burden and
duplication may be directed to the Office of Management and Budget, Reports
Management, Room 3208, New Executive Office Building, Washington, D.C., 20503.
If you have any questions about this matter, please contact one of the
technical contacts listed below or the Regional Administrator of the
appropriate regional office.
Charles E. Rossi, Director
Division of Operational Events Assessment
Office of Nuclear Reactor Regulation
Technical Contacts: J. T. Conway, NRR
E. T. Baker, NRR
J. C. Harper, NRR
1. Fastener Testing Data Sheet
2. Data Summary
3. List of Recently Issued Bulletins
Fastener Testing Data Sheet
Description of Sample Stock Location:
Material Specification as Documented by Licensee Records:
Head Marking (Specification and Manufacturer):
General Plant Application (e.g., Pressure Boundary, Structural)
QA Requirements Imposed on Vendor:
*The sample ID# shall have a prefix that contains the licensee facility
**If applicable, please provide an explanation for your classification system.
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