ML20004C750

Application for Proposed Change 139,Suppl 4 to License DPR-3,changing Wording & Clarifying Items in App a Tech Specs to Reflect Organizational Structure.Class II Amend Fee Encl

ML20004C750
Person / Time
Site:	Yankee Rowe
Issue date:	05/26/1981
From:	Heider L YANKEE ATOMIC ELECTRIC CO.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20004C751	List: ML20004C750 ML20004C753
References
FYR-81-81, NUDOCS 8106050154
Download: ML20004C750 (12)

Text

g JANKEE ATO:10 ELECTRIC C0~PANY

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(* 9f 1671 Worcester Road, Framingham, Massachusetts 01701

• ~TAf% KEE Proposed Change'No. 139 Supplement No. 4 May 26, 1981-N D

hj United States Nuclear Regulatory Commission washington, D.C.

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68 % *IWrons Attention: Office of Nuclear Reactor Regulation CNs A

References:

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(1) License No. DPR-3 (Doc'.at No. 50-29)

(2) Letter, YAEC to USNRC dated May 27, 1976; Proposed Change No. 139 (3) Letter, YAEC to USNRC dated March 23, 1977; Proposed Change No. 139, Supplement No. 1 (4) Letter, YAEC to USNRC dated November 24, 1978; Proposed Change No.

139, Supplement No. 3

Subject:

Technical Soecification Wording Changes and Clarifications Pursuant to Section 50.59 of the Commission's Rules and Regulations, Yankee Atomic Electric Company hereby proposes the following amendment to Appendix A of the Facility License.

PROPOSED CHANGE:

l Reference is made to Operating Licence No. DPR-3 issued to Yankee Atomic Electric Company on the Yankee Rowe Plant. Reference (2) incorporated new Technical Specifications, rewritten into the Westinghouse Standard Technical Specification Format, as Appendix A to this license. References (3) and (4) proposed minor changes which were subsequently incorporated into the License as Amendments NO. 49 and No. 58 respectively. These changes were administrative in nature and were subtnitted for the purpose of clarification of Standard Technical Specification language. Yankee feels that additional word changes and clarifications of the Technical Specifications are again appropria te.

These changes are indicated in At'achment A.

Revised pages are also provided in the attachment.

REASON FOR CHANGE:

The various reasons for the individual changes are present9d as part of Attachment A.

l 8166050154 j

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BASIS FOR CHANGE:

Wording changes and' clarification of items'are. required to reflect' conditions 4

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-that the plant is presently required to operate by.as; imposed by the-Nuclear-Regulatory Commission.

In addition, Yankee-Atomic Electric Company believes that the changes indicated accurately represent the current organizational structures as they exist relative to the plant management staff and ithe offsite organization.

SAFETY CONSIDERATION:

Based on the considerations contained herein, it is concluded that there is reasonable assurance that operation of the Yankee Rowe plant consistant with the proposed Technical Specifications will not endanger the health:and safety

-of the pubal?. This proposed change has been reviewed by the Nucleat Safety Audit and Review Committee.

FEE DETERMINATION:

This proposed change is administrative.in nature and has no safety or environmental significance. For these reasons, Yankee Atomic Electric Company proposes this change as a Class II amendment. A payment of $1,200.00 is.

enclosed.

SCHEDULE ' F CHANGE:

0 The changes described above will be incorporated into the Yankee Bowe-Technical Specifications upon receipt of your approval..

We trust that you will find this submittal satisfactory; however, should you desire additional information, please contact us.

~

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY

.Y L. H. Heider Vice President COMMONWEALTH OF MASSACHUSETTS)

)ss MIDDLESEX COUNTY Then personally appeared before me, L. H. Heider, who, being duly sworn, did state that he is a Vice President of Yankee. Atomic Electric Company,.that he is duly authorized to execute and file the foregoing request in the name and on the behalf of. Yankee Atomic Electric Company, and that the statements therein are true to the best' of his knowledge and ' belief.

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Q f y( Q Robert H. Groce Notary Public 7

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4 ATTACHMENT.A 1.

.Page 2-1 T-S. 2.1.1 Remove reference to. figure 2.1-2 and 3 loop operation.

Change:

Operation in the three loop mode is not permitted until the Reason:

appropriate LOCA analysis for this mode has been approved by_

the NRC.

2.

Page 2-3 Figure 2.1-2 Change:

Eliminate figure 2.1-2.

Reason:

Same as 1 above.

3 Page 2-5 Items 2 & 3 Change:

Remove reference to 3 loop operation.

Reason:

Same as 1 above.

4.

Page B 2-1 T.S. 2.1.1 Change:

Remove reference to figure 2.1-2.

Reason:

Same as 1 above.

5 Page B 2-3, T.S. 2.2.1 Remove reference to 3 loop operation from the " Power Range and Change:

Intermediate Power Range, Neutron Flux" Section.

Reason:

Same as 1 above.

6.

Page 3/4 1-21, T.S. 3 1.2.11.b.3 0

0 Minimum solution temperature from "400F" to "120 F-130 F".

Change:

An analysis by our NSSS revealed that plants with signficant Reason:

Reactor Vessel Neutron Exposure could be subjected to conditions that could exceed the NDT provisions of the ASME code after a severe' transient. An evaluation of the Yankee-Rowe Plant was initiated by us to determine if their general findings could exist at Rowe.

The results of the analysis indicated that the safety injection tank water temperature might have to be increased.

a This analysis was very conservative, using worst case values 0

for RT NDT and conservative approximations of plant transients. Although it might have been possible to conduct more detailed analyses to remove some of the' conservatism to justify a low temperature, it was concluded that it would be more prudent to increase the temperature of the safety injection water.

A 10 CFR 50.59 (a) review has been conducted to ensure that the increased water temperature does not impact the results of plant accident analyses.

7 Page 3/4 1-22, T.S. 4.1.2.ll.b 0

Change:

Remove "...When the out,1de air temperature is 435 F..."

Reason:

The safety injection tank water temperature limit of 120 F-130 F should be checked every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> regardless 0

0 of outside air temperature.

8.

Page 3/4 2-1, T.S. 3 2.1 Change:

Remove note regarding 3 loop operation.

Reason:

All T.S. regarding 3 loop operation'have been removed.

9 Page 3/4 3-19, Table 3 3-4, Item 2.C Change:

Alarm set point of." 480 cps to 4 6000 cpm."

Reason:

The steam generator blowdown monitors have been upgraded with new channels.

10. Page 3/4 3-19, T. S. Table 3 3-4 Item 3.a

. Change:

Alarm setpoint & measurement range.

Reason:

The high level radiation monitor has been upgraded with a new high range unit.

11. Page 3/4 4-Sa, T.S. 4.4.2.2.b Change:

Remove"...and valve PR-V-608 to be locked open".

Reason:

An engineering design change has been completed which redirects the discharge of both the pressurizer nafety valves and power operated relief valve to the containment instead of the low pressure surge tank. Valve PR-V-608 is therefore no longer in the flow paths of the pressurizer safety valves and power operated relief valve.

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12. Page 3/4 4-28, T.S. 4.4.9 2 Change:

Inspection frequency from "18 months" to "ISILinterval".

4

-The NRC (then AEC) approval of Yankee Rowe proposed ~ change Reason:

106 to the technical specifications allowed the replacement-of the reactor lower internals.' The original lower internals-was a bolted structure consisting of control' rod shroud tubes.-

which were individually bolted 'to _the lower cort support:

plate and a lower shroud -tie plate. During the course of ten cycles.of operation, some of the bolts in the lower internals -

became disengaged; knd control rod insertion difficulties were e countered.

i' "The originalLlower internals were replaced.with'a unitized structure consisting of control rod shroud tubes positioned and supported by two plates, one on the top. and 'one on the

-bottom. The shroud tubes are attached to.the plates by a combination of welding and bolts.. The unitized structure is.

attached with bolts to the lower core support plates.

Proposed' change 106 committed Yankee'Rowe to perform a series of. inspections to the reactor lower internals at each

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refueling outage. These inspections have been performed for four refueling outages since the commitment was made, with no degradation noted during any' of the inspections.

Having thus demonstrated the ~ integrity of the lower internals -

through three and one-half cycles of operation, it is

[

Yankee's opinion that the inspection frequency can now be relaxed. ASME Section XI,-(Inservice Inspection of Nuclear-Power Plants) requires reactor internals be inspected once l

every 10-year interval. This would be an appropriate' interval. for the inapection of the lower-internals.

13. Page 3/4 4-28, T.S. 4.4.9.4 Change:

Remove the surveillance requirement.

This section of line has been incorporated into-the ISI Reason:

program.

14. Page 3/4 5-1. T.S. 3 5.1 8 Change:

Replace "between" with "at".

Reason:

Clarity.

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15. Page 3/4 5-4, T.S. 4.5.2.b.1 Add note, "May be energized and opened if the charging header Change:

division valve, CH-V-607, is tagged closed."

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Reason:

This would allow the use of CH-MCV-522 for isolated loop charging without having to cooldown the main coolant system to 41000 psig. Isolation'of CH-V-607 allows the hot-leg injection system via the normal charging line to the main coolant system to remain functional and isolated from the loop fill header. -

16. Page 3/4 5-4, T.S. 4.5.2.b.1 Change:

Eliminate CH-MOV-523.

Reason:

Proposed change 160 (Amendment 52) modifications to the ECCS has excluded CH-MOV-523 from the hot leg injection flow path.

17. Page 3/4 5-12, T.S. 3 5.4.c 0

0 Change:

Minimum water temperature of "40 F" to "120 F-1300F."

Reason:

Same as 6 above.

18. Page 3/4 5-12, T.S. 4.5.4.b Change:

Remove "...When the outside air temperature is 4 350F".

Reason:

Same as 7 above.

19. Page 3/4 6-6, T.S. 4.6.1.5 Change:

Expand containment temperature monitor locations.

Reason:

Additional RTD'c were installed as part of the containment leak rate monitoring system upgrade.

20. Page 3/4 6-8, T.S. 3.6.1.7.b Change:

"eight" to " fourteen" l

l Reason:

Same as item 19 above.

21. Page 3/4 6-11, Table 3.6.1 Change:

Remove HV-SOV-1 & 2 from the table.

j Rep. son:

The hydrogen vent system is normally secured during plant operations with normally closed valves HV-V-5, 6, & 34 and CA-V-688 & 834 serving as the containment boundary. We also l'

rropose removing the asterisk from HV-V-5 & 6 (see item #23),

l thus subjecting them to type C testing.

l

a J22. Page 3/4 6-11, Table 3 6-1 s

Change:

Function column, "Neutren shield tank sample" to " Neutron shield tank sample"..

Reason:

Typographical error.

23. Page 3/4 6-13, T.S. Table 3.6-1 Change:

Demove the

• on CA-V-746.

Reason:

Test connections & valves have been added allowing Type C test performance on CA-V-746.

24. Page 3/4 6-13, T.S. Table 3.6-11

~hange:

Remove asterisks from HV-V-5 & 6.

Reason:

See item 21 above.

25. Page 3/4 6-13, T.S. Table 3 6-1 Change:

Add hydrogen vent system valves HV-V-34 and HV-V-834.

Reason:

This is a NUREG 0578 topic 2.1 5.a item. Redundant valves were required around normally closed valves HV-V-5 & 6 to provide for single failure.

26. Page 3/4 6-13, Table 3.6-1 Change:

Remove CS-MOV-500 from the Table.

Reason:

This valve is being removed from the type C testing program by changing the VC boundary to the blank flange in the fuel' chute.

27. Page 3/4 6-14, Table 3.6-1 Change:

Remove Cs-CV-215 from the Table.

Reason:

Same as item 26 above.

28. Page 3/4 6-14, T.S. Table 3 6-1 Change:

Remove the C on VD-V-752 and VD-V-754.

Reason:

Test connections and valves have been added allowing type C test performance on VD-V-752 and VD-V-754.

4

29. Page 3/4 6-14, T.S. Table $.6-1 Change:

Remove the 30 second isolation time for BF-CV-1000, 1100, 1200 & 1300.

Reason:

These valves are not containment trip valves and are not associated with the CIS of T.S. Table 3.3-2.

Isolation times are only pertinent to automatic trip valves as listed in T.S.

Table 3.6-1 Section A.

30. Page 3/4 6-14, Table 3.6-1 l

Change:

Remove PP-V-610 from the Table.

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Reason:

This valve is locked open during normal plant operation.

It is an instrument line rated at 2000 psig and is protected by two excess flow check valves. This line haa been placed in category D of Table 3 6-1.

31. page 3/4 6-15. Table 3.6-1 Change:

Add " fuel chute" to category D.

Reason:

See item 26 & 27.

32. Page 3/4 6-15, Table 3 6-1 Change:

Add " pressurizer heise gauge line" to category D.

Reason:

. tem 30 above.

33. Page 3/4 7-1, T.S. 3.7.1.1, Action a Change:

Remove reference to 3 loop operatic.1.

Reason:

Same as 1 above.

34. Page 3/4 7-1, T.S. 3 7.1.1 Note Change:

Remove note regarding 3 loop operation.

Reason:

All T.S. regarding 3 loop operation have been removed.

35. Page 3/4 7-3, Table 3 7-2 Change:

Eliminate Table 3.7-2 Reason:

Same as 1 above.

36. Page 3/4 7-28, Table 3 7 4 Remove pressurizer relief valve discharge line snubbers, HSS-21, 22, 23 & 24 from the Table.

Change:

d relier A post TMI modification to the pressurizer safety an directly valve discharge line has redirected the dischargeor into the vapor container instead of external to the vap Reason:

The section of the container to the low pressure sutse tai.k.

located discharge line which includes the above snubb lear safety.

37. Page 3/4 7-28, Table 3 7 4 Add 8 steam generator seismic restraint snubbers, Change:

Steam generator seismic restraint snubbers have been installed as part of an SEP seismic requirement.

Reason:

38. Page 3/4 8-1, T.S. 3 8.1.1.b.2 4'4" to 4'6.5".

k the To insure that 8000 gallons minimum remains in the tar.

Change:

d to 4'6.5".

minimum height value should be adjusted upwartilize the Reason:

The suction line in the fuel storage tank cannot bottom 4".

A revie' 6.5" when the minimum level of 4'4". fuel oil tank levels in Modes 1 4.

39. Page 3/4 8-1 & 3/4 8-2, T.S. 3 8.1.1 Action b.

hemove action b.

ffsite Change:

Operation @ 6 75% of rated thermal power with one o d

hich is not circuit inoperative would be in the 3 loop mo e w this mode has Reason:

permitted until appropriate LOCA analysis for been approved by the NRC.

40. Page 3/4 8-5, T.S. 3 8.1.2.b.2 2'2" to 2'4.5".

tank the Change:

To insure that 4000 gallons minimum remains in the d to 2'4.5".

minimum height value should be adjusted upwart utilize Reason:

The suction line in the fuel oil storage tank cannoT the bottom 4".

determining the minimum level value of 2'2".ever plant logs show that fuel oil tank levels have n decreased below 2'4.5" when in Hades ; & 6.

41. Page 3/4 8-8, T.S. 3 8.2.2.b Remove "#4-1 and #5-2" Change:

Buses 4-1 & 5-2 were required because the 3 charging pumps A plant design change has Reason:

were powered from these 2 buses.

been completed rearranging the charging pump power supplies such that now each charging pump is supplied from a separ;ts It is no longer required to designate which buses bus.

should be operable; any 2 out of 3 will suffice.

42. Page B 3/4 5-2, T.S. 3/4.5.4 "The SIT water temperature of Add the following:

Change:

120 F-130 F ensures that the reactor vessel is not 0

0 subjected to conditions that could exceed the NDT provisions of the ASME code after a severe transient.

Same as item 6.

Reason:

43. Page B 3/4 6-2, T.S. Bases 3/4.6.1.5 Remove equation.

Change:

Not required with new upgraded containment air temperature Reason:

monitoring system.

l

44. Page B 3/4 7-1, T.S. 3/4.7 1.1 Remove reference to 3 loop operation.

Change:

Reason:

Same as 1 above.

45. Page B 3/4 7 4, T.S. 3/4.7.6 Update bases with latest Westinghouse standard technical Change:

specification version.

This change exempts sealed sources contained within radiation monitoring or boron measuring devices from leak testing Reason:

requirements.

46. Page 6c3, Figure 6.2-1 Updated offsite organization Change:

Reflects changes made to the offsite organizational structure.

Reason:

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47. Page 6-4, Figure 6.2-2 Change:

- Updated facility organization Reason:

Reflects changes made to the onsite organizational structure.

48. Page 6-6, T.S. 6.4.1 Change:

Add "...For the facility NRC licensed staff shall..."

Reason:

The retraining program as stipulated by this technical specification applies only to NRC licensed personnel or those going for licenses, and that it is these people that the training coordinator is responsible to train.

49. Page 6-16, T.S.6 9 4, 1st sentence..

Change:

"reoccurence" to " recurrence".

Reason:

Typographical error.

50. Page 6-6, T.S.6.3 1 Change:

Chemistry & Health Physics Supervisor to Chemistry-Supervisor, Plant Health Physicist to Health Physics Supervisor and add Mainterance Manager.

Reason:

Reflects changes made to onsite organization structure.

51. Page 6-7, T.S.6.5.1.2 Change:

Chemistry & Health Physics Supervisor to Chemistry Supervisor, Plant Hea*th Physicist to Health Physics Supervisor and add Maintenance Manager.

Reason:

Same as 50 above.

52. Page B 3/4 4-9, T.S. Bases Figure B 3/4.4-1 Change:

Revise curve.

Reason:

Reflect the latest fracture analysis as determined by Westinghouse.

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53. Page'3/4 6-8, T.S. 3 6.1.7.d.

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Add..."and/or dew probes"...

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Same as 19 above.

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54. Page 3/4 6-8, T.S. 4.6.1.7.b.

Change:

Add

..."the dew probes"...

Reason:

Same as 19 above.

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