ML17146A738
| ML17146A738 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/06/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17146A737 | List: |
| References | |
| NUDOCS 8704090083 | |
| Download: ML17146A738 (8) | |
Text
gp,A A6gty UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION
~
SUPPORTING AMENDMENT NO. 63 TO FACILITY OPERATING LICENSE NO. NPF-14 AND AMENDMENT NO. 34 TO FACILITY OPERATING LICENSE NO. NPF-22 PENNSYLVANIA POWER 5 LIGHT COMPANY SUS UEHANNA STEAM ELECTRIC STATION UNITS 1
AND 2
'DOCKET NOS. 50-387 AND 50-388
1.0 INTRODUCTION
By letter dated December 26, 1985, the Pennsylvania Power and Light Company requested several Technical Specification changes for both Units 1 and 2
which were administrative in nature.
These changes are itemized in the following evaluation.
- 2. 0 EVALUATION 1.
Corrections to Table 3.6.3-1 (Units 1 and 2) a.
Containment Instrument Gas Unit 1:
Page 3/4 6-25 of the Unit 1 Technical Speclfscatlons (TTI currently 11sts valve number 1-26-070 as an isolation valve in the Containment Instrument Gas System.
, This change deletes this valve from the Table and adds valve number 1-26-164.
The original design for the isolation valves on this one inch pene-tration was to have check valve 1-26-070 inside containment and a
globe valve (SV-12671) outside containment.
However, the check valve inside containment is subject to severe environmental condi-tions such as suppression pool dynamic loads.
Therefore, check valve 1-26-164 was added outside containment between the penetration and the globe valve.
The licensee observed that containment isola-tion reliance on a check valve outside the containment did not meet the General Design Criterion (GDC) 56 of Appendix A of the Commission's regulation 10 CFR 50, and by a letter dated May 29, 1984, requested exemption from GDC 56.
The staff reviewed the licensee's request and found that the change was acceptable without a need for exemption from GDC 56, because the revised valve con-figuration met the staff's alternate criterion of the Standard Review Plan Section 6.2>>4.
Therefore, substitution of valve 1-26-070 by valve 1-26-164 in Table 3.6.3-1 does not diminish the intended containment isolation function, and the proposed change is acceptable.
Unit 2:
Page 3/4 6-25 of the Unit 2 Technical Specifications lists
~ot the 2-26-164 valve and the 2-26-070 valves as Containment Instrument Gas System isolation valves.
For the same reasons discussed above for Unit 1, the deletion of valve 2-26-070 from Table 3.6.3-1 is acceptable.
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b.
Hiah Pressure Coolant Injection (HPCI).
Unit 1:
Paae 3/4 6-26 lists HV-155F012 as a Minimum Recirculationnnow (penetration X-211) isolation valve.
This amendment adds valve HV-155F046 to this category.
The licensee stated that this valve was inadvertently omitted from the Technical Specifications.
This valVe represents the outer'solation boundary on the X-211 penetration as documented in FSAR Table 6.2-22.
Because this isolation arrangement represents a
deviation from GDC 56 of 10 CFR 50, Appendix A, the licensee requested specific approval.
The staff approved the licensee's specific design via the Safety Evaluation Report (NUREG-0776) Sec-tion 6 and determined that a specific exemption was not necessary.
The licensee stated that the HV-155F046 valve was included in the surveillance program and has been properly leak tested.
The staff finds it acceptable to add valve HV-155F046 to the Technical Specifications.
Unit 2:
Page 3/4 6-25:
This amendment allows the same chanae as Un>~ T ((b) above) for Unit 2.
All of the above justification for Unit 1 applies to Unit 2.
The valve being added to the Unit 2 listina is HV-255F046.
c.
Reactor Core Isolation Coolina (RCIC).
Unit 1:
Paae 3/4 6-26 'lists HV-149F019 as a
RCIC minimum recirculatian aaow (penetration X-216) isolation valve.
This amendment adds HV-149F021 to this cateaory.
The F021 valve was inadvertently omitted from the Technical Specifi-cations.
It represents the outer isolation boundary on the X-216 penetration as documented in FSAR Table 6,2-22.
This isolation arrangement represented a deviation from GDC 56 of 10 CFR 50 Appendix A.
The staff has previously approved this desian in the staff's Safety Evaluation Report (NUREG-0776) Section 6 and deter-mined that a specific exemption was not necessary.
The HV-149F021 valve was included in the surveillance program and has been properly leak tested.
Unit 2:
Page 3/4 6-26:
This amendment provides the same chanae as inst T ((c) above) for Unit 2.
All of the above justification for Unit 1 applies to Unit 2.
The valve which will be added to the Unit 2 listing is HV-249F021.
The staff finds this change for both Units 1 and 2 to be acceptable.
d.
Integrated Leak Rate Testing.(ILRT) Unit 1:
Page 3/4 6-24 contained a typographical error.
Valve 1-57-1T9 sSsould be valve 1-57-194.
This valve was properly identified in FSAR Table 6.2-22 (Penetration X-61A), and has been properly identified in all controlling pro-cedures/documents.
The staff finds this correction to be appropriate and acceptable.
2.
Addition to Plant Operations Review Comfttee (PORC) Membership Units I and 2:
This amendment adds the Assistant Superintendent-Outages 2 II II I
I 2
I 2.2.1.2 IIII !
Pt 2 Technical Specifications.
The Assistant Superintendent-Outages meets the qualifications require-ments of Plar t Manager under ANSI/ANS-3.1-1978, Paragraph 4.2.1 (Refer-ence FSAR Subsection 13.1.3.1).
This expansion of PORC membership will increase the experience/expertise base of the PORC.
The addition of the Assistant Superintendent of Plant-Outages to the PORC membership list will vest in that position responsibilities to advise/recomend to the Superintendent on matters related to nuclear safety commensurate with those responsibilities inherent in managing nuclear power plant outage activities.
The qualification/education/training requirements for the Assistant Superintendent-Outages are the same as those for the "operating" Assistant Superintendent, thus making the Assistant Superintendent-Outaaes qualified for manaaement of operating nuclear power plant activities.
The staff finds that thfs proposed change to the PORC composition is consistent with the acceptance criteria in Section 13.4 of NUREG-0800, the Standard Review Plan (SRP),
and is, therefore, acceptable.
3.
Deletion of Offsfte Organization Position.
Units I and 2: The deletion I
I 2 Itt "Pt P
Id
-2 gt I
2 M and the subsequent realignment as indicated in the change to Figure 6.2.1-1 for both units reflects PPSL's shift from construction to operation of the Susquehanna plant.
The personnel requirements of ANSI/ANS 3.1-1978 do not apply to this
- change, since the scope of these guidelines does not rise above the functional level of "Manager".
The staff finds this change to be acceptable as it is consistent with Section 13.1.1 of the Standard Review Plan.
4.
Generic Letter No. 85-19.
Units I and 2: Generic Letter (GL) 85-19
<<d I, ItI~
dt I
Pt I
iodine spiking, ftmedfate notification requirements of 10 CFR 50.72(b)(1)(ff) to repot t unexpected fuel cladding failures, and improvements in the quality of nuclear fuel and licensee responses to abnormal fuel behavior, the staff has concluded that certain Technical Specification reporting requirements can be changed (iodine spiking reporting requirements can be changed from short-term reportfna to an item in the annual report) and limiting conditions for operation (to shutdown a plant if iodine activity limits exceeded 800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br /> in a 12 month period) can be eliminated.
The licensee, in response to recom-mendation of GL 85-19, has requested changes to Technical Specifications
for Units 1 and 2 to change the iodine spiking reporting requirements, and to eliminate the above limiting condition for operation.
The staff has determined that the proposed changes are consistent with the recom-mendations of GL 85-19 and are, therefore, acceptable.
5.
Snubbers Unit 1: 'wo changes are proposed by the licensee to specifi-
'cations 374.M:
- 1) Deletion of references to Table 3.7.4-1.
Removal of the snubber table was approved by NRC via Amendment 36 to the Unit 1 Operating License.
The references to it were inadvertently left in the text of Specification 3/4.7.4.
- 2) Correction of sampling expression.
The correct expression is 35 (1 + C/2).
This typographical error was made in Amendment 36 to the Unit 1 Operating License.
The staff finds it appropriate and acceptable to correct these typo-graphical errors.
- 3. 0 ENVIRONMENTAL CONSIDERATION These amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in surveillances and reporting requirements.
The staff has determined that the amendments involve no significant increase in the
- amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that these amendments involve no significant hazards consideration, and there has been no public comment on such finding.
Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement nor environmental assessment need be prepared in connection with the issuance of these amendments.
4.0 CONCLUSION
The Commission made a proposed determination that these amendments involve no significant hazards consideration which was published in the Federal Register (51 FR 18690) on May 21. 1986, and consulted with the state o~ennsyTWan a.
No public comments were received, and the state of Pennsylvania did not have any comments.
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the public
A
will not be endanaered by operation in the proposed
- manner, and (2) such activities will be conducted in compliance with the Commission's reaulations and the issuance of these amendments will not be inimical to the common defense and security nor to the health and safety of the public.
Principal Contributors:
Mohan C. Thadani, Project Directorate No. 3, DBL T. Schoenfeld,
- FOB, DBL P. Hearn,
- PSB, DBL Dated:
April 6, 1987
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