GO2-16-079, Erratum for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (Srvs) Setpoint Lower Tolerance

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Erratum for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (Srvs) Setpoint Lower Tolerance
ML16139A161
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 05/18/2016
From: Javorik A
Energy Northwest
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
GO2-16-079
Download: ML16139A161 (5)
v • d • e


Text

Alex L. Javorik Columbia Generating Station P.O. Box 968, Mail Drop PE23 Richland, WA 99352-0968 Ph. 509-377-2354 F. 509-377-8555 aljavorik@energy-northwest.com May 18, 2016 GO2-16-079 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 ERRATUM FOR LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION SURVEILANCE REQUIREMENT (SR) 3.4.3.1 AND SR 3.4.4.1 SAFETY/RELIEF VALVES (SRVs) SETPOINT LOWER TOLERANCE

Reference:

Letter, GO2-16-046, dated May 10, 2016, A. L. Javorik (Energy Northwest) to NRC, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (SRVs) Setpoint Lower Tolerance

Dear Sir or Madam:

Please replace Pages 7 and 8 of Attachment 1 of the referenced letter with the enclosed pages. Errors were found on page 8 of 17 in that the Relief Valve Setpoints in Table 2 erroneously included the pressure switch head correction. The values in the table were revised to reflect removal of the head correction. Also, the table was revised to provide the minimum margin between safety and relief modes of operation at the limiting tolerance values. As a result, the discussion on overlap with the safety function setpoints on page 7 of 17 was corrected.

The conclusions of the original Regulatory Evaluation and Environmental Consideration are unaffected by this correction.

Pursuant to 10 CFR 50.91, a copy of this erratum is being sent to the designated official of the State of Washington.

There are no new or revised commitments with this letter.

If you should have any questions regarding this submittal, please contact Ms. L. L.

Williams, Licensing Supervisor, at 509-377-8148.

G02-16-079 Page 2of2 n day of &r I dlclare under penalty of perjury that the foregoing is true and correct. Executed this

'2016.

Respectfull~j---

A. L. Javorik Vice President, Engineering

Enclosure:

As stated cc: NRC Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector - 988C CD Sonoda - BPA 1399 (email)

WA Horin -Winston & Strawn (email)

RR Cowley - WDOH (email)

EFSECutc.wa.gov- EFSEC (email)

GO2-16-079 Enclosure License Amendment Request To Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (SRVs) Setpoint Lower Tolerance Replacement Pages

GO2-16-046 Page 7 of 17 Table 1 SRV Equipment Test SRV Set As-No. Year/Outage Type S/N Pressure Tolerance found Deviation 4C 2013, R21 C 55 1195 +/- 3% 1257 5.19%

4D 2013, R21 C 62 1205 +/- 3% 1162 -3.57%

5B 2013, R21 CA 61 1205 +/- 3% 1208 0.25%

5C 2013, R21 C 59 1205 +/- 3% 1173 -2.66%

1A 2015, R22 CA 48 1175 +/- 3% 1122 -4.51%

1B 2015, R22 C 45 1165 +/- 3% 1138 -2.32%

1C 2015, R22 CA 139 1165 +/- 3% 1146 -1.63%

1D 2015, R22 CA 49 1175 +/- 3% 1209 2.89%

2A 2015, R22 CA 122 1185 +/- 3% 1185 0.00%

2B 2015, R22 C 134 1175 +/- 3% 1170 -0.43%

2C 2015, R22 CA 50 1175 +/- 3% 1134 -3.49%

2D 2015, R22 C 52 1185 +/- 3% 1133 -4.39%

3A 2015, R22 C 57 1195 +/- 3% 1157 -3.18%

3B 2015, R22 C 138 1185 +/- 3% 1180 -0.42%

3C 2015, R22 CA 54 1185 +/- 3% 1180 -0.42%

3D 2015, R22 C 137 1195 +/- 3% 1208 1.09%

4A 2015, R22 C 135 1205 +/- 3% 1200 -0.41%

4B 2015, R22 C 126 1195 +/- 3% 1186 -0.75%

4C 2015, R22 CA 56 1195 +/- 3% 1277 6.86%

4D 2015, R22 CA 62 1205 +/- 3% 1173 -2.66%

5B 2015, R22 C 61 1205 +/- 3% 1226 1.74%

5C 2015, R22 CA 136 1205 +/- 3% 1214 0.75%

Table Key:

S/N= Serial Number Test Type:

C- Test for ASME Code and TS Compliance CA- Additional SRVs tested due to ASME Code Test failure 4.4 Operating Margin The purpose of the lower setpoint tolerance is to ensure sufficient margin exists between the normal operating pressure of the system and the point at which the SRVs actuate in the safety mode. The normal operating pressure of the RPV at power is 1020 psig. Table 2 provides a comparison of the SRV safety setpoints with the relief setpoints and provides the simmer margin between the proposed -5% safety setpoint tolerance and the normal operating pressure. The table shows there is adequate margin between the normal operating pressure and the -5% safety setpoint tolerance. The lowest margin occurs with the lowest SRV setpoint valves with a simmer margin of 86.75 psig.

The table also shows a comparison with the relief mode setpoints along with their established tolerance band of +/- 5 psig. The table shows there is no overlap with the relief setpoints for the proposed safety setpoint lower tolerance of -5%. Additionally, the as-left tolerance of SRVs remains at +/-3%. SRVs which are removed for maintenance are returned to a tolerance of +/-1% prior to being installed for service, thereby returning the margin to original levels. Therefore, the margin is considered adequate and will not impact normal plant operation.

GO2-16-046 Page 8 of 17 Additionally, for the Columbia analyses discussed in section 4.5, there is no specific margin required between event peak pressure and opening safety setpoints for the SRVs or a restriction in the overlap between the range of acceptable SRV safety setpoints for the SRVs and the relief mode opening setpoints.

Table 2 SRV TS TS TS Pressure Relief Relief Relief Relief Simmer Equip Safety Safety Safety Switch Setpoint +5 +5 psig +5 psig Margin No. Setpoint -3% -5% Equip. psig vs vs for -5%

No. Safety Safety

-3% -5%

1A 1175 1139.8 1116.25 39J 1101 1106 33.8 10.25 96.25 1B 1165 1130.1 1106.75 39E 1091 1096 34.1 10.75 86.75 1C 1165 1130.1 1106.75 39L 1091 1096 34.1 10.75 86.75 1D 1175 1139.8 1116.25 39K 1101 1106 33.8 10.25 96.25 2A 1185 1149.5 1125.75 39A 1111 1116 33.5 9.75 105.75 2B 1175 1139.8 1116.25 39F 1101 1106 33.8 10.25 96.25 2C 1175 1139.8 1116.25 39D 1101 1106 33.8 10.25 96.25 2D 1185 1149.5 1125.75 39C 1111 1116 33.5 9.75 105.75 3A 1195 1159.2 1135.25 39B 1121 1126 33.2 9.25 115.25 3B 1185 1149.5 1125.75 39H 1111 1116 33.5 9.75 105.75 3C 1185 1149.5 1125.75 39G 1111 1116 33.5 9.75 105.75 3D 1195 1159.2 1135.25 39V 1121 1126 33.2 9.25 115.25 4A 1205 1168.9 1144.75 39S 1131 1136 32.9 8.75 124.75 4B 1195 1159.2 1135.25 39R 1121 1126 33.2 9.25 115.25 4C 1195 1159.2 1135.25 39M 1121 1126 33.2 9.25 115.25 4D 1205 1168.9 1144.75 39P 1131 1136 32.9 8.75 124.75 5B 1205 1168.9 1144.75 39U 1131 1136 32.9 8.75 124.75 5C 1205 1168.9 1144.75 39N 1131 1136 32.9 8.75 124.75 4.5 Evaluation The proposed safety setpoint lower tolerance change from -3% to -5% was qualitatively evaluated for Columbia by GE Hitachi Nuclear Energy (GEH) in Reference 7 as a supplement to GE-NE-187-24-0992, Revision 2. The results of this evaluation are presented below.

4.5.1 Vessel overpressure protection, anticipated operational occurrence (AOO) thermal limits and anticipate transient without scram (ATWS):

The effects of the proposed change on ATWS and other pressurization events are evaluated below.

The AOO thermal limits evaluation examined the Columbia Cycle 23 analysis. For the events that establish the operating limit minimum critical power ratio (OLMCPR) and the

Alex L. Javorik Columbia Generating Station P.O. Box 968, Mail Drop PE23 Richland, WA 99352-0968 Ph. 509-377-2354 F. 509-377-8555 aljavorik@energy-northwest.com May 18, 2016 GO2-16-079 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001

Subject:

COLUMBIA GENERATING STATION, DOCKET NO. 50-397 ERRATUM FOR LICENSE AMENDMENT REQUEST TO MODIFY TECHNICAL SPECIFICATION SURVEILANCE REQUIREMENT (SR) 3.4.3.1 AND SR 3.4.4.1 SAFETY/RELIEF VALVES (SRVs) SETPOINT LOWER TOLERANCE

Reference:

Letter, GO2-16-046, dated May 10, 2016, A. L. Javorik (Energy Northwest) to NRC, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (SRVs) Setpoint Lower Tolerance

Dear Sir or Madam:

Please replace Pages 7 and 8 of Attachment 1 of the referenced letter with the enclosed pages. Errors were found on page 8 of 17 in that the Relief Valve Setpoints in Table 2 erroneously included the pressure switch head correction. The values in the table were revised to reflect removal of the head correction. Also, the table was revised to provide the minimum margin between safety and relief modes of operation at the limiting tolerance values. As a result, the discussion on overlap with the safety function setpoints on page 7 of 17 was corrected.

The conclusions of the original Regulatory Evaluation and Environmental Consideration are unaffected by this correction.

Pursuant to 10 CFR 50.91, a copy of this erratum is being sent to the designated official of the State of Washington.

There are no new or revised commitments with this letter.

If you should have any questions regarding this submittal, please contact Ms. L. L.

Williams, Licensing Supervisor, at 509-377-8148.

G02-16-079 Page 2of2 n day of &r I dlclare under penalty of perjury that the foregoing is true and correct. Executed this

'2016.

Respectfull~j---

A. L. Javorik Vice President, Engineering

Enclosure:

As stated cc: NRC Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector - 988C CD Sonoda - BPA 1399 (email)

WA Horin -Winston & Strawn (email)

RR Cowley - WDOH (email)

EFSECutc.wa.gov- EFSEC (email)

GO2-16-079 Enclosure License Amendment Request To Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 and SR 3.4.4.1 Safety/Relief Valves (SRVs) Setpoint Lower Tolerance Replacement Pages

GO2-16-046 Page 7 of 17 Table 1 SRV Equipment Test SRV Set As-No. Year/Outage Type S/N Pressure Tolerance found Deviation 4C 2013, R21 C 55 1195 +/- 3% 1257 5.19%

4D 2013, R21 C 62 1205 +/- 3% 1162 -3.57%

5B 2013, R21 CA 61 1205 +/- 3% 1208 0.25%

5C 2013, R21 C 59 1205 +/- 3% 1173 -2.66%

1A 2015, R22 CA 48 1175 +/- 3% 1122 -4.51%

1B 2015, R22 C 45 1165 +/- 3% 1138 -2.32%

1C 2015, R22 CA 139 1165 +/- 3% 1146 -1.63%

1D 2015, R22 CA 49 1175 +/- 3% 1209 2.89%

2A 2015, R22 CA 122 1185 +/- 3% 1185 0.00%

2B 2015, R22 C 134 1175 +/- 3% 1170 -0.43%

2C 2015, R22 CA 50 1175 +/- 3% 1134 -3.49%

2D 2015, R22 C 52 1185 +/- 3% 1133 -4.39%

3A 2015, R22 C 57 1195 +/- 3% 1157 -3.18%

3B 2015, R22 C 138 1185 +/- 3% 1180 -0.42%

3C 2015, R22 CA 54 1185 +/- 3% 1180 -0.42%

3D 2015, R22 C 137 1195 +/- 3% 1208 1.09%

4A 2015, R22 C 135 1205 +/- 3% 1200 -0.41%

4B 2015, R22 C 126 1195 +/- 3% 1186 -0.75%

4C 2015, R22 CA 56 1195 +/- 3% 1277 6.86%

4D 2015, R22 CA 62 1205 +/- 3% 1173 -2.66%

5B 2015, R22 C 61 1205 +/- 3% 1226 1.74%

5C 2015, R22 CA 136 1205 +/- 3% 1214 0.75%

Table Key:

S/N= Serial Number Test Type:

C- Test for ASME Code and TS Compliance CA- Additional SRVs tested due to ASME Code Test failure 4.4 Operating Margin The purpose of the lower setpoint tolerance is to ensure sufficient margin exists between the normal operating pressure of the system and the point at which the SRVs actuate in the safety mode. The normal operating pressure of the RPV at power is 1020 psig. Table 2 provides a comparison of the SRV safety setpoints with the relief setpoints and provides the simmer margin between the proposed -5% safety setpoint tolerance and the normal operating pressure. The table shows there is adequate margin between the normal operating pressure and the -5% safety setpoint tolerance. The lowest margin occurs with the lowest SRV setpoint valves with a simmer margin of 86.75 psig.

The table also shows a comparison with the relief mode setpoints along with their established tolerance band of +/- 5 psig. The table shows there is no overlap with the relief setpoints for the proposed safety setpoint lower tolerance of -5%. Additionally, the as-left tolerance of SRVs remains at +/-3%. SRVs which are removed for maintenance are returned to a tolerance of +/-1% prior to being installed for service, thereby returning the margin to original levels. Therefore, the margin is considered adequate and will not impact normal plant operation.

GO2-16-046 Page 8 of 17 Additionally, for the Columbia analyses discussed in section 4.5, there is no specific margin required between event peak pressure and opening safety setpoints for the SRVs or a restriction in the overlap between the range of acceptable SRV safety setpoints for the SRVs and the relief mode opening setpoints.

Table 2 SRV TS TS TS Pressure Relief Relief Relief Relief Simmer Equip Safety Safety Safety Switch Setpoint +5 +5 psig +5 psig Margin No. Setpoint -3% -5% Equip. psig vs vs for -5%

No. Safety Safety

-3% -5%

1A 1175 1139.8 1116.25 39J 1101 1106 33.8 10.25 96.25 1B 1165 1130.1 1106.75 39E 1091 1096 34.1 10.75 86.75 1C 1165 1130.1 1106.75 39L 1091 1096 34.1 10.75 86.75 1D 1175 1139.8 1116.25 39K 1101 1106 33.8 10.25 96.25 2A 1185 1149.5 1125.75 39A 1111 1116 33.5 9.75 105.75 2B 1175 1139.8 1116.25 39F 1101 1106 33.8 10.25 96.25 2C 1175 1139.8 1116.25 39D 1101 1106 33.8 10.25 96.25 2D 1185 1149.5 1125.75 39C 1111 1116 33.5 9.75 105.75 3A 1195 1159.2 1135.25 39B 1121 1126 33.2 9.25 115.25 3B 1185 1149.5 1125.75 39H 1111 1116 33.5 9.75 105.75 3C 1185 1149.5 1125.75 39G 1111 1116 33.5 9.75 105.75 3D 1195 1159.2 1135.25 39V 1121 1126 33.2 9.25 115.25 4A 1205 1168.9 1144.75 39S 1131 1136 32.9 8.75 124.75 4B 1195 1159.2 1135.25 39R 1121 1126 33.2 9.25 115.25 4C 1195 1159.2 1135.25 39M 1121 1126 33.2 9.25 115.25 4D 1205 1168.9 1144.75 39P 1131 1136 32.9 8.75 124.75 5B 1205 1168.9 1144.75 39U 1131 1136 32.9 8.75 124.75 5C 1205 1168.9 1144.75 39N 1131 1136 32.9 8.75 124.75 4.5 Evaluation The proposed safety setpoint lower tolerance change from -3% to -5% was qualitatively evaluated for Columbia by GE Hitachi Nuclear Energy (GEH) in Reference 7 as a supplement to GE-NE-187-24-0992, Revision 2. The results of this evaluation are presented below.

4.5.1 Vessel overpressure protection, anticipated operational occurrence (AOO) thermal limits and anticipate transient without scram (ATWS):

The effects of the proposed change on ATWS and other pressurization events are evaluated below.

The AOO thermal limits evaluation examined the Columbia Cycle 23 analysis. For the events that establish the operating limit minimum critical power ratio (OLMCPR) and the

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