NRC Generic Letter 1981-25: Difference between revisions

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| issue date = 06/13/1981
| issue date = 06/13/1981
| title = NRC Generic Letter 1981-025: Change in Implementing Schedule for Submission and Evaluation of Upgraded Emergency Plans
| title = NRC Generic Letter 1981-025: Change in Implementing Schedule for Submission and Evaluation of Upgraded Emergency Plans
| author name = Eisenhut D G
| author name = Eisenhut D
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
| addressee name =  
| addressee name =  
Line 14: Line 14:
| page count = 4
| page count = 4
}}
}}
{{#Wiki_filter:CftLPA REG(,,F EUNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D. C. 20555TO ALL HOLDERS OF CONSTRUCTION PERMITSGentlemen:SUBJECT: CHANGE IN IMPLEMENTING SCHEDULE FOR SUBMISSION AND EVALUATIONOF UPGRADED EMERGENCY PLANS (Generic Letter No. 81-25)On October 31, 1980, you were provided a clarification letter (NUREG-0737)regarding approved TMI Action.Plan items. The implementation schedulefor item III.A.2 Emergency Preparedness in Enclosure 2, NUREG-0737, impliesthat upgraded emergency plans to meet the criteria of NUREG-0654, Revision 1,"Criteria for Preparation and Evaluation of Radiological Emergency ResponsePlans and Preparedness in Support of Nuclear Power Plants" must be submittedprior to fuel load authorization. Full compliance with all elements ofNUREG 0654 is unnecessary for this stage of startup operations.Enclosed is a copy of page 2-11 of Enclosure 2, NUREG-0737, changing theimplementing schedule to require upgraded emergency plans from prior to"fuel load" to prior to "full-power" authorization. The requirementsnecessary for a "fuel load" authorization will be determined on a case-by-case basis.Sincerely,Darrell G. Eisenhut, DirectorDivision of LicensingOffice of Nuclear Reactor RegulationEnclosure:Page 2-11 of Enclosure 2,NUREG-0737PDR ADOC3 0500027 5F D  
{{#Wiki_filter:Cf tLPA REG(,,
s -IV IlENCLOSURE 2 (COtITInUED)Clarifi- Implemen- Plant Require- Clarifi- TechCarion tatlon Applica- ments cation Spec.Iten Title Description Schedule b 1ity Issued Issued Req. Remarks1i.K.3 rFnal Recomfendations, c. New analyses In accordance All
                    F     EUNITED                     STATES
* Encl. 3 NoB6O task force with review(Continued) schedule31. Plant-specific analysis 1/1/03f All
                                    NUCLEAR REGULATORY COMMISSION
* Enc. 3 ho44. Evaluate transients 1/1/lIA OUR
                                            WASHINGTON, D. C. 20555 TO ALL HOLDERS OF CONSTRUCTION PERMITS
* Encl. 3 Aswith single failure required45. Manual depressurization 1/81A OWR
              Gentlemen:
* Encl. 3 No46. Michelson concerns fuel load DMR
              SUBJECT:     CHANGE IN IMPLEMENTING SCHEDULE FOR SUBMISSION AND EVALUATION
* Encl. 3 noIII.A.I.I Emergency Sho.t-term improvements Complete nopreparedness,short termIII.A.1.2 Upgrade emergency 1. Establish TSC OSC TOD All 9/27I79 11/9/79 Nosupport facilities EOF (interim bas'sl TOD All 92/ 1/7 To2. Design TOO T BO T OO T BO T hD3. Modifications 100 TOo TOO TOD TOD11I.A.2 Lsimrtqency 1. Upgrade aaergency plans full power All 8/19/11 NIREG- Yespreparedness to App E. 10 CFR 50 (K542. Meteorological data Full power All 6/26/80 NUREG- Yes0654111.U.1.1 Primary coolant Measure leak rates I Full power All 9/27/79 11/9/79 Yesoutside establish program to Encl. 3containment keep leakage ALARA111.0.3.3 Inplant 12 radiation 1. Provide means to Fuel load All 9/27/79 11/9/79 Yesmonitoring determine presence Encl. 3of radio1odine2. Modifications to 1/1/81 or All 9/27/79 11/9/79 Yesaccurately measure prior toradlolodine icensing Encl. 3111.0.3.4 Control-room 1. Identify and evaluate Full power All 6/26/80 End. 3 Nohabitability potential hazards2. Schedule for Full power All 6/26/00 End. 3 omodifications3. Modifications full power All 6/26/80 Encl. 3 YesAFoisr vitonts before operating license Is issued or 4 months before date indicated.*hequirement formally issued by this letter.II-nt0
                          OF UPGRADED EMERGENCY PLANS (Generic Letter No. 81-25)
PLANTS UNDER CONSTRUCTION1.2.3.4.5.Cherokee 1/2/3Beaver Valley 2St. Lucie 2Vogtle 1/2River Bend 1/250-491,50-41250-38950-424,50-458,492, 4934254596.7.8.9.10.11.12.13.Forked RiverNine Mile Point 2Millstone 3Bailly 2Limerick 1/2Hope Creek 1/2Seabrook 1/250-36350-41050-42350-36750-352,50-354,50-443,35335544414.15.16.17.18.19.20.Hartsville 1/2/3/4Phipps Bend 1/2Yellow Creek 1/2WPPSS 1/3/4/5Harris 1/2/3/4FNP50-518,50-553,50-566,50-460,50-400,50-437519,554567508,401,520, 521513, 509402, 403 PLANTS UNDER OL REVIEW1.2.3.4.5.6.7.8.9.10.11.12.13.14.15.16.17.18.19.20.21.22.23.24.25.26.27.28.29.Clinton 1/2Byron 1/2Braidwood 1/2LaSalle 1/2Midland 1/2McGuire 2So. Texas 1/2ShorehamWaterfordGrand Gulf 1/2Diablo Canyon 1/2Susquehana 1/2St. Lucie 2Summer 1San Onofre 2/3Bellefonte 1/2Watts'Bar 1/2Sequoyah 2Comanche Peak 1/250-461/46250-454, 45550-456/45750-373, 37450-329,33050- 37050-498, 49950-32250-38250-416/41750-275, 32350-387, 38850-38950-39550-361, 36250-438, 43950-390, 39150- 32850-445, 446WPPSS-2Fermi 2Ziimmer 1Perry 1/2Palo VerdeCatawbaMarble HillWolf CreekCallaway50-39750-34150-35850-440,50-528,50-413,50-546,50-4 8250-483,441529, 530414547486
              On October 31, 1980, you were provided a clarification letter (NUREG-0737)
}}
              regarding approved TMI Action.Plan items. The implementation schedule          implies for item III.A.2 Emergency Preparedness in Enclosure 2, NUREG-0737,Revision            1, that upgraded emergency plans to meet the criteria         of NUREG-0654,
              "Criteria for Preparation and Evaluation of Radiological         Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" must be submitted prior to fuel load authorization. Full compliance with all elements of NUREG 0654 is unnecessary for this stage of startup operations.
 
Enclosed is a copy of page 2-11 of Enclosure 2, NUREG-0737, changing           the implementing schedule to require upgraded       emergency plans from prior to
              "fuel load" to prior to "full-power"     authorization.       The requirements necessary for a "fuel load" authorization will be determined on a case- by-case basis.
 
Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Enclosure:
                Page 2-11 of Enclosure 2, NUREG-0737 PDR ADOC305000275 F                    D
 
s - I
                                                                                                                                                V Il ENCLOSURE 2 (COtITInUED)
Clarifi-                                                                 Implemen-       Plant   Require- Clarifi-   Tech Carion                                                                  tatlon         Applica- ments     cation     Spec.
 
Iten           Title                   Description                     Schedule       b 1ity   Issued   Issued     Req.     Remarks
  1i.K.3       rFnal Recomfendations,       c. New analyses             Inaccordance All       *         Encl. 3     No B6O task force                                           with review (Continued)                                             schedule
                                        31. Plant-specific analysis     1/1/03f       All     *         Enc. 3       ho
                                        44. Evaluate transients         1/1/lIA         OUR     *         Encl. 3   As with single failure                                                       required
                                        45. Manual depressurization     1/81A         OWR     *         Encl. 3   No
                                        46. Michelson concerns           fuel load     DMR     *         Encl. 3   no III.A.I.I
III.A.1.2 Emergency preparedness, short term Upgrade emergency Sho.t-term improvements
                                          1. Establish TSC OSC
                                                                          Complete TOD             All All
                                                                                                  9/27I79
                                                                                                  92/
                                                                                                            11/9/79
                                                                                                              1/7 no No To I
                support facilities         EOF (interim bas'sl         TOD
                                                                                        T BO     T OO     T BO       T hD
                                                                                                                                        I
                                          2. Design                      TOO
                                          3. Modifications               100             TOo     TOO       TOD       TOD
11I.A.2         Lsimrtqency             1.Upgrade aaergency plans       full power   All     8/19/11     NIREG-     Yes preparedness                to App E. 10 CFR 50                                             (K54
                                          2. Meteorological data         Full power       All     6/26/80   NUREG-     Yes
                                                                                                            0654
111.U.1.1     Primary coolant           Measure leak rates I             Full power     All       9/27/79   11/9/79   Yes outside                establish program to                                               Encl.3 containment            keep leakage ALARA
111.0.3.3     Inplant12 radiation       1.Provide means to           Fuel load         All     9/27/79   11/9/79   Yes monitoring                  determine presence                                             Encl.3 of radio1odine
                                          2.Modifications to           1/1/81 or         All     9/27/79   11/9/79   Yes accurately measure         prior to radlolodine                  icensing                       Encl.     3                    -
  111.0.3.4       Control-room             1. Identify and evaluate     Full power       All   6/26/80   End.3         No                n habitability                potential hazards
                                          2. Schedule for                 Full power     All   6/26/00   End.3       o                  t0
                                              modifications
                                          3.
 
Modifications                   full power     All     6/26/80 Encl.     3   Yes AFoisr vitonts before operating license Is issued or 4 months before date indicated.
 
*hequirement formally issued by this letter.
 
PLANTS UNDER CONSTRUCTION
    Cherokee 1/2/3              50-491, 492, 493
1.
 
Beaver Valley 2              50-412
2.
 
3. St. Lucie 2                  50-389 Vogtle 1/2                  50-424, 425
4.
 
50-458, 459
5. River Bend 1/2
6.
 
Forked River                50-363
7.
 
Nine Mile Point 2            50-410
8.
 
Millstone 3                  50-423
9.
 
Bailly 2                      50-367
10.
 
50-352, 353
11. Limerick 1/2 Hope Creek 1/2                50-354, 355
12.
 
Seabrook 1/2                50-443, 444
13.
 
14.
 
50-518, 519, 520, 521
15. Hartsville 1/2/3/4 Phipps Bend 1/2              50-553, 554
16.
 
Yellow Creek 1/2            50-566, 567
17.
 
WPPSS 1/3/4/5                50-460, 508, 513, 509
18.
 
Harris 1/2/3/4              50-400, 401, 402, 403
19.
 
20. FNP                          50-437
 
PLANTS UNDER OL REVIEW
1. Clinton 1/2                      50-461/462
2. Byron 1/2                       50-454, 455
3. Braidwood 1/2                    50-456/457
4. LaSalle 1/2                      50-373, 374
5. Midland 1/2                      50-329,330
6. McGuire    2                    50-     370
7. So. Texas 1/2                    50-498, 499
8. Shoreham                        50-322
9. Waterford                        50-382
10. Grand Gulf 1/2                  50-416/417
11. Diablo Canyon 1/2                50-275, 323
12. Susquehana 1/2                  50-387, 388
13. St. Lucie 2                      50-389
14. Summer 1                        50-395
15. San Onofre 2/3                  50-361, 362
16. Bellefonte 1/2                  50-438, 439
17. Watts'Bar 1/2                    50-390, 391
18. Sequoyah    2                  50-     328
19. Comanche Peak 1/2                50-445, 446
20.
 
21. WPPSS-2                          50-397
22. Fermi 2                          50-341
23. Ziimmer 1                        50-358
24. Perry 1/2                        50-440, 441
25. Palo Verde                      50-528, 529, 530
26. Catawba                          50-413, 414
27. Marble Hill                      50-546, 547
28. Wolf Creek                      50-4 82
29. Callaway                        50-483, 486}}


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Latest revision as of 03:06, 24 November 2019

NRC Generic Letter 1981-025: Change in Implementing Schedule for Submission and Evaluation of Upgraded Emergency Plans
ML031080613
Person / Time
Site: Beaver Valley, Millstone, Mcguire, Nine Mile Point, Palo Verde, Perry, Fermi, Catawba, Harris, Wolf Creek, Saint Lucie, Watts Bar, Hope Creek, Grand Gulf, Sequoyah, Byron, Braidwood, Susquehanna, Summer, Columbia, Seabrook, Limerick, River Bend, Diablo Canyon, Callaway, Vogtle, Waterford, Clinton, South Texas, San Onofre, Comanche Peak, Midland, Bellefonte, LaSalle, 05000363, 05000000, Zimmer, Washington Public Power Supply System, Shoreham, Satsop, Bailly, Atlantic Nuclear Power Plant, Cherokee, Marble Hill, Hartsville, Phipps Bend, Yellow Creek
Issue date: 06/13/1981
From: Eisenhut D
Office of Nuclear Reactor Regulation
To:
References
GL-81-025, NUDOCS 8107100320
Download: ML031080613 (4)
v • d • e


Cf tLPA REG(,,

F EUNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555 TO ALL HOLDERS OF CONSTRUCTION PERMITS

Gentlemen:

SUBJECT: CHANGE IN IMPLEMENTING SCHEDULE FOR SUBMISSION AND EVALUATION

OF UPGRADED EMERGENCY PLANS (Generic Letter No. 81-25)

On October 31, 1980, you were provided a clarification letter (NUREG-0737)

regarding approved TMI Action.Plan items. The implementation schedule implies for item III.A.2 Emergency Preparedness in Enclosure 2, NUREG-0737,Revision 1, that upgraded emergency plans to meet the criteria of NUREG-0654,

"Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants" must be submitted prior to fuel load authorization. Full compliance with all elements of NUREG 0654 is unnecessary for this stage of startup operations.

Enclosed is a copy of page 2-11 of Enclosure 2, NUREG-0737, changing the implementing schedule to require upgraded emergency plans from prior to

"fuel load" to prior to "full-power" authorization. The requirements necessary for a "fuel load" authorization will be determined on a case- by-case basis.

Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation Enclosure:

Page 2-11 of Enclosure 2, NUREG-0737 PDR ADOC305000275 F D

s - I

V Il ENCLOSURE 2 (COtITInUED)

Clarifi- Implemen- Plant Require- Clarifi- Tech Carion tatlon Applica- ments cation Spec.

Iten Title Description Schedule b 1ity Issued Issued Req. Remarks

1i.K.3 rFnal Recomfendations, c. New analyses Inaccordance All * Encl. 3 No B6O task force with review (Continued) schedule

31. Plant-specific analysis 1/1/03f All * Enc. 3 ho

44. Evaluate transients 1/1/lIA OUR * Encl. 3 As with single failure required

45. Manual depressurization 1/81A OWR * Encl. 3 No

46. Michelson concerns fuel load DMR * Encl. 3 no III.A.I.I

III.A.1.2 Emergency preparedness, short term Upgrade emergency Sho.t-term improvements

1. Establish TSC OSC

Complete TOD All All

9/27I79

92/

11/9/79

1/7 no No To I

support facilities EOF (interim bas'sl TOD

T BO T OO T BO T hD

I

2. Design TOO

3. Modifications 100 TOo TOO TOD TOD

11I.A.2 Lsimrtqency 1.Upgrade aaergency plans full power All 8/19/11 NIREG- Yes preparedness to App E. 10 CFR 50 (K54

2. Meteorological data Full power All 6/26/80 NUREG- Yes

0654

111.U.1.1 Primary coolant Measure leak rates I Full power All 9/27/79 11/9/79 Yes outside establish program to Encl.3 containment keep leakage ALARA

111.0.3.3 Inplant12 radiation 1.Provide means to Fuel load All 9/27/79 11/9/79 Yes monitoring determine presence Encl.3 of radio1odine

2.Modifications to 1/1/81 or All 9/27/79 11/9/79 Yes accurately measure prior to radlolodine icensing Encl. 3 -

111.0.3.4 Control-room 1. Identify and evaluate Full power All 6/26/80 End.3 No n habitability potential hazards

2. Schedule for Full power All 6/26/00 End.3 o t0

modifications

3.

Modifications full power All 6/26/80 Encl. 3 Yes AFoisr vitonts before operating license Is issued or 4 months before date indicated.

  • hequirement formally issued by this letter.

PLANTS UNDER CONSTRUCTION

Cherokee 1/2/3 50-491, 492, 493

1.

Beaver Valley 2 50-412

2.

3. St. Lucie 2 50-389 Vogtle 1/2 50-424, 425

4.

50-458, 459

5. River Bend 1/2

6.

Forked River 50-363

7.

Nine Mile Point 2 50-410

8.

Millstone 3 50-423

9.

Bailly 2 50-367

10.

50-352, 353

11. Limerick 1/2 Hope Creek 1/2 50-354, 355

12.

Seabrook 1/2 50-443, 444

13.

14.

50-518, 519, 520, 521

15. Hartsville 1/2/3/4 Phipps Bend 1/2 50-553, 554

16.

Yellow Creek 1/2 50-566, 567

17.

WPPSS 1/3/4/5 50-460, 508, 513, 509

18.

Harris 1/2/3/4 50-400, 401, 402, 403

19.

20. FNP 50-437

PLANTS UNDER OL REVIEW

1. Clinton 1/2 50-461/462

2. Byron 1/2 50-454, 455

3. Braidwood 1/2 50-456/457

4. LaSalle 1/2 50-373, 374

5. Midland 1/2 50-329,330

6. McGuire 2 50- 370

7. So. Texas 1/2 50-498, 499

8. Shoreham 50-322

9. Waterford 50-382

10. Grand Gulf 1/2 50-416/417

11. Diablo Canyon 1/2 50-275, 323

12. Susquehana 1/2 50-387, 388

13. St. Lucie 2 50-389

14. Summer 1 50-395

15. San Onofre 2/3 50-361, 362

16. Bellefonte 1/2 50-438, 439

17. Watts'Bar 1/2 50-390, 391

18. Sequoyah 2 50- 328

19. Comanche Peak 1/2 50-445, 446

20.

21. WPPSS-2 50-397

22. Fermi 2 50-341

23. Ziimmer 1 50-358

24. Perry 1/2 50-440, 441

25. Palo Verde 50-528, 529, 530

26. Catawba 50-413, 414

27. Marble Hill 50-546, 547

28. Wolf Creek 50-4 82

29. Callaway 50-483, 486

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