LR-N16-0126 

JUL 0 5 2016 

PSEG Nuclear LLC 

P.O. Box 236, Hancocks Bridge, NJ 08038-0236 

U.S. Nuclear Regulatory Commission 

ATTN: Document Control Desk 

Washington, DC 20555-0001 

SUBJECT: 

Salem Nuclear Generating Station Unit 1 

Renewed Facility Operating License No. DPR-70 

NRC Docket No. 50-272 

LER 272/2016-001-000 

10 CFR 50.73 

Unanalyzed Condition due to Degraded Reactor Baffle to Former 

Bolts 

Licensee Event Report, "Unanalyzed Condition due to Degraded Reactor Baffle to 

Former Bolts" is being submitted pursuant to 10 CFR 50.73 (a)(2)(ii)(B), "The nuclear 

power plant being in an unanalyzed condition ........ " 

Should you have any questions or comments regarding the submittal, please contact 

Mr. Thomas Cachaza of Regulatory Affairs at 856-339-5038. 

There are no regulatory commitments contained in this letter. 

Sincerely, 

Eric Carr 

Plant Manager 

Salem Generating Station 

tjc 

Enclosure- LER 272/2016-001-000 
Page 2 10 CFR 50.73 

LR-N16-0126 

cc Mr. D. Dorman, Administrator- Region 1, NRC 

Ms. C. Parker, Licensing Project Manager- Salem, NRC 

Mr. P. Finney, USNRC Senior Resident Inspector, Salem (X24) 

Mr. T. Cachaza, Salem Commitment Tracking Coordinator 

Mr. L. Marabella, Corporate Commitment Tracking Coordinator 
NRC FORM 366 

(11-2015) 

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$ i!;<'fQ. �' lf. ...... ii: 

1. FACILITY NAME 

U. S. NUCLEAR REGULATORY COMMISSION 

LICENSEE EVENT REPORT (LER) 

(See Page 2 for required number of 

digits/characters for each block) 

Salem Generating Station - Unit 1 

4. TITLE 

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 10/31/2018 

Estimated burden per response to comply with this mandatory collection request: 80 hours. 

Reported lessons learned are incorporated into the licensing process and fed back to industry. 

Send comments regarding burden estimate to the FOIA, Privacy and Information Collections 

Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, or by 

internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of Information and 

Regulatory Affairs, NEOB-10202, (3150-0104), Office of Management and Budget, Washington, 

DC 20503. If a means used to impose an information collection does not display a currently valid 

OMB control number, the NRC may not conduct or sponsor, and a person is not required to 

respond to, the information collection. 

2. DOCKET NUMBER 3. PAGE 

05000272 1 OF 3 

Unanalyzed Condition due to Degraded Reactor Baffle to Former Bolts 

5. EVENT DATE 6. LER NUMBER 7. REPORT DATE 8. OTHER FACILITIES INVOLVED 

I SEQUENTIAL I REV FACILITY NAME DOCKET NUMBER 

MONTH DAY YEAR YEAR MONTH DAY YEAR NUMBER NO. 05000 

FACILITY NAME DOCKET NUMBER 

05 03 2016 2016- 001 -000 07 05 2016 05000 

9. OPERATING MODE 11. THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR §: (Check all that apply) 

D 20.22o1(b) D 20.2203(a)(3)(i) 50. 73(a)(2)(ii)(A) 50. 73(a)(2)(viii)(A) 

20.2201 (d) 20.2203( a)(3)(ii) M 50. 73( a)(2)(ii)(B) 50.73( a)(2)(viii)(B) 

Defueled 

20.2203(a)(1) 20.2203( a)( 4) 50. 73( a)(2)(iii) 50. 73(a)(2)(ix)(A) 

0 20.2203(a)(2)(i) D 50.36(c)(1 )(i)(A) D 50.73(a)(2)(iv)(A) D 50.73(a)(2)(x) 

10. POWER LEVEL 0 20.2203(a)(2)(ii) 0 50.36(c)(1)(ii)(A) D 50.73(a)(2)(v)(A) D 73.71(a)(4) 

0 20.2203(a)(2)(iii) 50.36( c )(2) D 50.73(a)(2)(v)(B) 73.71(a)(5) 

20.2203(a)(2)(iv) 50.46(a)(3)(ii) 50.73(a)(2)(v)(C) 73.77(a)(1) 

Oo/o 

C 20.2203(a)(2)(v) 0 50.73(a)(2)(i)(A) 50. 73( a)(2)(v)(D) 73.77(a)(2)(i) 

C 20.2203(a)(2)(vi) 50.73(a)(2)(i)(B) 0 50.73(a)(2)(vii) D 73.77(a)(2)(ii) 

50.73(a)(2)(i)(C) OTHER Specify in Abstract below or in NRC Form 366A 

12. LICENSEE CONTACT FOR THIS LER 

LICENSEE CONTACT I TELEPHONE NUMBER (Include Aroe Code) 

Thomas J. Cachaza, Senior Regulatory Compliance Engineer 856-339-5038 

13. COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 

CAUSE SYSTEM COMPONENT MANU- REPORTABLE CAUSE SYSTEM COMPONENT MANU- REPORTABLE 

FACTURER TO EPIX FACTURER TO EPIX 

X AB RPV W120 y 

14. SUPPLEMENTAl_ REPORT EXPECTED 15. EXPECTED MONTH DAY YEAR 

0 YES (If yes, complete 15. EXPECTED SUBMISSION DATE) MNO SUBMISSION 

DATE 

ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten fines) 

With Salem Unit 1 in a defueled condition during a planned refueling outage, anomalies were identified on baffle to former bolts 

while conducting a scheduled visual inspection of Reactor Vessel Internals. Due to the visual anomalies, PSEG commenced 

ultrasonic inspection of the baffle to former bolts to determine the extent of condition and determine a repair plan. 

Based on initial results of the analysis of the ultrasonic inspection data received on May 03, 2016, this condition was 

determined to be reportable pursuant to 10 CFR 50.72(b)(3)(ii)(B) , since the as-found conditions were not previously analyzed. 

As a result of the inspection approximately 190 baffle to former bolts were identified as needing replacement. 

NRC FORM 366 (11-2015) 
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 

(11-2015) 

LICENSEE EVENT REPORT (LER) 

CONTINUATION SHEET 

1. FACILITY NAME 2. DOCKET 

Salem Generating Station - Unit 1 05000272 

NARRATIVE 

PLANT AND SYSTEM IDENTIFICATION 

Westinghouse-Pressurized Water Reactor {PWR/4} 

Reactor Coolant System I Reactor Vessel {AB/RPV} 

IDENTIFICATION OF OCCURRENCE 

Event Date: 05/03/2016 

Discovery Date: 05/03/2016 

CONDITIONS PRIOR TO OCCURRENCE 

Salem Unit 1 was defueled 

DESCRIPTION OF OCCURRRENCE 

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2018 

Estimated burden per response to comply with this mandatory collection request: 80 hours. 

Reported lessons learned are incorporated into the licensing process and fed back to 

industry. Send comments regarding burden estimate to the FOIA, Privacy and Information 

Collections Branch {T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-

0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of 

Information and Regulatory Affairs, NEOB-1 0202, (3150-01 04), Office of Management and 

Budget, Washington, DC 20503. If a means used to impose an information collection does not 

display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person 

is not required to respond to, the information collection. 

6. LER NUMBER 

I SEQUENTIAL 

NUMBER 

YEAR 

2016 - 001 

I REVISION 

NUMBER 

- 000 

3. PAGE 

2 OF3 

With Salem Unit 1 in a defueled condition during a planned refueling outage, anomalies were identified on baffle to former bolts 

while conducting a scheduled visual inspection of Reactor Vessel Internals. Due to the visual anomalies, PSEG commenced 

ultrasonic inspection of the baffle to former bolts to determine the extent of condition and determine a repair plan. 

As a result of the inspection approximately 190 baffle to former bolts were identified as needing replacement. 

Based on initial results of the analysis of the ultrasonic inspection data received on May 03, 2016, this condition was 

determined to be �eportable pursuant to 10 CFR 50.72(b)(3)(ii)(B), since the as-found conditions were not previously analyzed. 

The Salem Unit 1 baffle structure includes 832 baffle to former bolts which attach the baffle plates to the former plates. Of the 832 

baffle to former bolts, approximately 190 bolts were identified as needing replacement. 

The number of failed bolts and the pattern of failure did not meet the acceptance criteria for plant startup from the 1 R24 refueling 

outage which has been provided by Westinghouse. 

During Salem Unit 1 1 R24 refueling outage, the condition of the baffle to former bolting in the Reactor Vessel Internals was visually 

examined in which eighteen bolt heads were identified as either broken/missing or protruding from its counter bore. Ultrasonic 

testing (UT) was subsequently performed on baffle to former bolting, which identified an additional population of defective bolting. 

New baffle to former bolting defects were also identified due to the replacement efforts. The total number of defective baffle to 

former bolts identified within the visual and UT examinations as well as during the replacement efforts are described below. 

Eleven baffle to former bolts were visually identified as severed at the bolt head-to-shank area. Nineteen 

baffle to former bolts were visually identified as protruding from their counter bore. One hundred thirty-five baffle to former bolts 

were identified as unsatisfactory through UT examination. Sixteen baffle to former bolts were identified as not able to be UT tested 

(assumed as unsat in analysis). Nine baffle to former bolts were identified having visually cracked lock bar welds. 
NRC FORM 366A U.S. NUCLEAR REGULATORY COMMISSION 

(11-2015) 

.;t"��i!j:f4��1-

! 

� � 

�"'� ••.. ,.··"" LICENSEE EVENT REPORT (LER) 

CONTINUATION SHEET 

1. FACILITY NAME 2. DOCKET 

Salem Generating Station - Unit 1 05000272 

NARRATIVE 

CAUSE OF EVENT 

APPROVED BY OMB: NO. 3150-0104 EXPIRES: 01/31/2018 

Estimated burden per response to comply with this mandatory collection request: 80 hours . 

Reported lessons learned are incorporated into the licensing process and fed back to 

industry. Send comments regarding burden estimate to the FOIA, Privacy and Information 

Collections Branch (T-5 F53), U.S. Nuclear Regulatory Commission, Washington, DC 20555-

0001, or by internet e-mail to lnfocollects.Resource@nrc.gov, and to the Desk Officer, Office of 

Information and Regulatory Affairs, NEOB-1 0202, (3150-01 04), Office of Management and 

Budget, Washington, DC 20503. If a means used to impose an information collection does not 

display a currently valid OMB control number, the NRC may not conduct or sponsor, and a person 

is not required to respond to, the information collection. 

6. LER NUMBER 

I SEQUENTIAL 

NUMBER 

YEAR 

2016 001 

I REVISION 

NUMBER 

- 000 

3. PAGE 

3 OF3 

The failure mechanism of the described bolting is identified as irradiation assisted stress corrosion cracking (IASCC), a known 

industry issue that is inherent within designs that utilize Westinghouse-supplied stainless steel Type 347 baffle to former bolting. 

Exposure to high levels of fast neutrons results in embrittlement of the stainless steel bolting, evidenced by an increase in tensile 

strength and a decrease in ductility. As residual ductility is further reduced and embrittlement progresses, additional stresses via 

neutron irradiation can result in the formation and propagation of cracks. IASCC is a time related degradation that is associated to 

the operating life of the components. The significant factors that contribute to the initiation and propagation of IASCC degradation 

are neutron fluences, time of operation, fatigue inducing loading cycles on the baffle plates, pressure differentials across the baffle 

plates, and temperature. Failure analysis of selected removed bolts will be performed to confirm this cause. 

SAFETY CONSEQUENCES AND IMPLICATIONS 

Westinghouse performed an evaluation, which is based on sound engineering assumptions, concludes that Salem Unit 1 met the 

requirements for core coolability and safe shut-down in its "as-found" state during 1 R24, considering both potential baffle bolt 

failures due to a LOCA and loose parts from degraded baffle-former bolts found during 1 R24. On this basis, safe operation and 

safe shutdown of Salem Unit 1 was assured during Cycle 24. 

SAFETY SYSTEM FUNCTIONAL FAILURE 

This event is not being reported as a safety system functional failure. 

Westinghouse performed an evaluation, which is based on sound engineering assumptions, concludes that Salem Unit 1 met the 

requirements for core coolability and safe shut-down in its "as-found" state during 1 R24, considering both potential baffle bolt 

failures due to a LOCA and loose parts from degraded baffle-former bolts found during 1 R24. On this basis, safe operation and 

safe shutdown of Salem Unit 1 was assured during Cycle 24. 

PREVIOUS EVENTS 

A review of previous events for the past three years identified no similar events. 

CORRECTIVE ACTIONS 

Salem is taking the following actions: 

• The degraded baffle to former bolts are being replaced. 

• Failure analysis of selected removed bolts will be performed to confirm IASCC as the cause. 

• An acceptable bolting pattern analysis was performed to determine the required bolting replacement scope. 

• Required bolting was replaced for one cycle of operation while also relying on original baffle-former bolts that had no UT 

indications 

COMMITMENTS 

There are no regulatory commitments contained in this LER.